Dynatom February 2013

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4 Contents

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EDITORIAL STAFF

/ 编辑团队

CONTENTS

Interviews

News

Nuclear Glossary

Highlights of the Month

Company News

NPP News

International Cooperation

Interview with Alexander L. Berenzon,Head of Public

Relations Department,JSC "Afrikantov” OKBM

Interview with Mr. Alexander Gordeev, Deputy Director,

POLIMASTER INTERNATIONAL

Interview with Alexey Nourlybaev,

Head of Sales and Distribution,SPC"Doza"Ltd.

Interview with Sonia Goual,

Sales Engineer and Nuclear Segment Leader at Crouzet

AECL PASSIVE AUTOCATALYTIC RECOMBINERS

SMRs in China: An Exciting New Sector

Technical Articles

HAF Regulations

Events Calendar

EDITORS / 编辑

Arnaud Lefevre-Baril / 百力

Bessie Wang / 王文贝

NEWS / 新闻

Anna Liu / 刘晓燕

TECHNICAL ARTICLES / 科技文章

Elaine Li / 李益楠

EVENTS / 展会会议


DESIGNER / 设计师

FangHua Design Inc / 芳华设计公司

DYNABOND POWERTECH SERVICE /代邦核讯联系方式

Room 1509, Zhongyu Plaza, A6 Gongti North Road, Chaoyang District, Beijing, China

PHONE / 电话

+86-10-64681222

FAX / 传真

+86-10-64654957

EMAIL / 邮箱

[email protected]

WEBSITE / 网站

www.dynabondpowertech.com

Disclaimer

All rights reserved. No part of this publication may be reproduced in any form or by any means without the permission of its editors and/or its sources

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mailto:[email protected]


Editorial5

List of Agreements between Russia and China in the nuclear field.

• Agreement on Creation of a Joint Non-Ferrous and Rare Metals Corporation. Signed March 27, 1950.

• Aid in Developing Physics Research of the Atomic Nucleus and in Utilization of Atomic Energy for Needs of the National Economy. Signed April 27, 1955; in force April 27, 1955.

• Uranium Survey Agreement. Signed January 30, 1955.

• Aid by USSR in Construction of Industrial Enterprises. Signed April 7, 1956. Note: Included in this is construction of a 6 Megawatt reactor.

• Economic and Scientific Co-operation Agreement. Signed April 24, 1990.

• Agreement on Co-operation on the Construction and Operation of a Fast Neutron Experimental Reactor in China. Signed April 2000.

• Nuclear Co-operation Agreement. Signed July 20, 2001. Note: This includes designing a nuclear energy plant for spacecraft and the manufacture of MOX fuel.

• Fast Reactor Agreement. Signed July 2002.

That happened in February:

Sino-Russian Nuclear Cooperation

China and Russia share sixty years of cooperation in the nuclear field, both military and civil.

Russia has been involved in the design and construction of research reactors in China since the late 1950s: the Heavy Water Research Reactor RFR-10 was in operation from 1958 until it was shut down in 2007.

Since 2010, both countries have agreed to expand nuclear power cooperation in several areas, including VVER technology, fast reactors, exploration of uranium mines, fuel manufacturing, nuclear isotopes, decommissioning of old plants, post-processing technology, building floating power plants and developing markets abroad.

Recently, Wang Qishan, Vice Premier of the State Council and Chinese Chairman of the China-Russia Energy Cooperation Committee (CRECC), reiterated this cooperation program with his counterpart Arkady Dvorkovich, Deputy Prime Minister of the Russian Federation.

Our editorial team will introduce briefly some of the major projects that involve Russian technology in China.

TIANWAN Nuclear Power Plant Phase 1 Tianwan Nuclear Power Plant (TNPP), a VVER-1000 (V-428) 2 x 1060 MW, was promoted by Russia as the first third-generation nuclear power plant (project "AES-91") and the largest economic entity cooperation between China and Russia.

The nuclear power plant is located in Lianyungang, Jiangsu Province.

This intergovernmental agreement was signed on December 18, 1992. The project involved the participation of more than 150 Russian companies, organizations and governmental organizations (e.g. the turbine was manufactured at the Leningrad Metal Works).

In 2004, the Russian Nuclear Regulatory Andrey Malyshev who visited the site already indicated that Russia could participate in the tender for the extension of Tianwan.

The earlier tests revealed 3,300 serious defects or non-conformance in the Russian equipment despite control from Atomstroyexport, and Rostekhnadzor, the inspection organization.

The facility started its commercial operation on May 17 and August 16, 2007.

Baril

Arnaud Lefevre

Editorial 6

insists on retaining intellectual property rights.

Iskorskiye Zavody “Izhora”, part of OMZ, manufactures the reactor pressure vessels with internals and upper units. Delivery should be completed in 2014.

The delegation of the Ministry of Environment Protection of China visited the company in 2011, including representatives from the National Nuclear Security Administration (NNSA), the Northern Regional Office (NRO), the Nuclear and Radiation Security Center (NSC) and JNPC.

The Chinese experts visited the metallurgical and engineering plant production complex to become familiar with all phases of manufacture of equipment for this project.

In 2012, the representat ives of "TSKBM" and OJSC "Atomenergomash" also defined a possible cooperation in the production of PARS and other gas treatment systems.

Areva (with Siemens) supplied the digital safety instrumentation & control system, and also the emergency diesel generator (with Motor and Turbine Union).

JNPC is responsible for about 70% of the project, namely, the civil work, the turbine island with equipment and related infrastructure on the site (note: Harbin Turbine Company provides the turbine design, moisture separator reheater (MSR) and other major auxiliary engine, turbine control, flexible foundation design and other key components of the manufacturing process Machines).

The civil engineering contract was awarded to China Nuclear Industry Huaxing Construction Company (HXCC), and to China Nuclear Industry 23 Construction Co for component installation.

Commercial operation is due in 2018 and 2019.

In December 2012, the Russian Deputy Prime Minister Dmitry Rogozin reported discussions with CNNC regarding phases III & IV of Tianwan (units 5-8), using VVER technology.

Since beginning commercial operation, Atomstroyexport has continued its support to Jiangsu Nuclear Power Corporation (JNPC) through its subsidiaries such as Atomtechenergo (operation of the plant and provides personnel training) and Atomenergoremont (maintains and upgrades systems and components). Recently, Tianwan was provided with information on the safety improvement actions taken at Russian NPPs with regard for additional analysis performed after the Fukushima accident.

The construction of this first phase involved Chinese civil engineering companies who acquired valuable experience, such as China Construction Nuclear Industry Corporation (CNI-23). Many Chinese enterprises manufactured a number of pieces of equipment related to instrumentation and control, low-pressure pipeline, valves and fittings.

In May 2010, JNPC signed the protocols on the final acceptance of the first phase of the Tianwan nuclear power plant.

This cooperation recently led to the creation of a science and technology base, established in Lianyungang, between JNPC and Volgodonsk Nuclear Power Plant. The Council of Sino-Russian nuclear science and technology research and development of international cooperation gathers researchers from the Nuclear Power Institute of China (NPIC), China Institute of Atomic Energy (CIAE), Shanghai Nuclear Engineering Research and Design Institute (SNERDI), Institute of Nuclear and New Energy Technology Research Institute (INET) and other members from JNPC. One of the subjects of cooperation is the molten-core catcher technology, which has improved nuclear safety since September 2010.

TIANWAN Nuclear Power Plant Phase 2 In 2006, Sergei Kirienko informed President Vladimir Putin’s cabinet that Rosatom would resume its expansion in Tianwan nuclear plants and intends to build six more reactors.

In November 2010, the signing of a general contract to build the Phase Two took place in St. Petersburg. The plant was designed by Gidropress.

The contract parties are JSC Atomstroyexport and JNPC.

The key responsibility of the Russian side is the nuclear island. Atomstroyexport provides 30% of the VVER units for €1.3 billion, including nuclear island equipment. The overall project is expected to cost $3.8 billion.

Atomstroyexport will not act as the principal contractor, though it

Editorial7

List of HAF 604 certification awarded to Russian Companies for Tianwan Phase 2

Corporation Equipment Safety Level Range Certificationdate

Pressure VesselBrace

Pipes and pipe fittingsreactor internals Class 3

TankStrobe

Mechanic penetrating pieceAlpha - Lawali Heat exchanger

Liski Pipes and pipe fittingsMechanic penetrating piece

ValveBraceStrobe Class 2

He Class 3Heat exchanger

TankPipes and pipe fittings

BraceHeat exchanger Class 1, 2 & 3

TankPipes and pipe fittings

Brace Baltiysky Zavod Heat exchanger Baltiysky Zavod Tank

OMZ-Special steels Casting and ForgingCentral Design Bureau of Machine Building

Lebedyansky machine-building plantCentral Valve Design Bureau CKBA Valve

Pressure VesselHeat exchanger

Pipes and pipe fittingsReactor Internals

Control rod drive mechanismTankBrace

Kontur Valve Class 2 & 3 ManufactureHeat exchanger Class 3

TankMechanic penetrating piece

ValveFlangeTank

Mechanic penetrating pieceHeat exchanger

Tyazhmash Class 2 ManufacturePDTI «Atomarmproect» DesignJSC «Soyuz-01» Firm Design & Manufacture

EnmashPipes and pipe fittings

BraceFlange

Specialized scientific research institute for instrumentationengineering Cabinets 1E

Design

Design & Manufacture


Manufacture

PumpClass 1, 2 & 3

Class 2 & 3

Class 3

Manufacture

Design & ManufactureClass 2 & 3

Brace

Valve

2012-4-28

Gidropress

Class 2 & 3

Class 1

Class 2

Limited Liability Company “Atomspetsservice”

Limited Liability Company “Polesye”

E4-Centroenergomontazh

Class 2 & 3

Class 3

Ziomar

Class 2 & 3 Manufacture

Class 2 & 3

Class 2 & 3

Zio PodolskClass 2 & 3

Class 2 & 3

2011-3-22

Class 1, 2 & 3

Izhorskiye Zavody

Atommashexport



Design

Editorial 8

CEFR

R&D on fast neutron reactors started in 1964.

In 2003, A 65 MWt fast neutron reactor - the Chinese Experimental Fast Reactor

(CEFR) - was designed and built near Beijing by the China Institute of Atomic

Energy (CIAE) with the support of OKBM Afrikantov, OKB Gidropress, NIKIET

and Kurchatov Institute.

This is known as the Chinese Demonstration Fast Reactor (CDFR) project 1.

The CEFR project received research assistance from the Russian Fast Breeder

Reactor Association and more “detailed design” assistance from experts of the

Beloyarsk Nuclear Power Station.

The main equipment including reactor safety systems, heat exchangers,

reloaders and control devices was installed by OKBM.

The reactor uses highly enriched uranium (HEU) of 64.4% enrichment imported

from Russia.

China intends to use mixed oxide (MOX) fuel in its industrial-scale (600 MW)

China Prototype Fast Reactor envisioned for 2020.

It achieved first criticality in July 2010, and was grid connected in July 2011.

BN-800

In addition to the CDFR project 1, on October 2009, an agreement between the

CIAE, CNEIC and Atomstroyexport confirmed that China would opt for the BN-

800 technology as CDFR project with 70% of the equipment to be localized.

The BN-800 is the first integral type sodium reactor based on the prototype fast

reactor BN-600, which has been in successful operation since 1980. It uses the

closed-end nuclear fuel cycle technologies, has a thermal capacity of 2100 MW,

electric power of 880 MW, installed capacity utilization factor of 80% with an

efficiency of 42%, and a service life of 40 years.

OKBM Afrikantov will build the reactor at Sanmin, an inland part of Fujian

province. Atomenergopoekt is in charge of the design.

Sanmin Nuclear Power Co Ltd is a joint venture company with the Fujian

Investment & Development Corp and local government.

In 2012, a delegation from OJSC “Atomenergomash”, headed by the acting

CEO Boris Arseev, presented the BN-800 reactor, which has been developed

Major international visits to the CEFR since 2011:

October 2011: Russian Deputy Prime Minister Igor Sechin visited the China Experimental Fast Reactor (CEFR) with the Vice-Premier Wang Qishan and Wang Gang, the President of CIAE

October 2011: Alexander Bychkov, Deputy Director General of International Atomic Energy Agency (IAEA) visited the site accompanied by Ren Meizhen, Deputy Secretary General of China Atomic Energy Agency (CAEA).

April 2012: Vyacheslav Pershukov, vice manager of Rosatom, who introduced the p rogress ach ieved on bas ic nuclear research, isotope, fast reactor technology and fuel reprocessing.

August 2012: Nikolai Nikolaevich Ponomarev-Stepnoi from the Russian Academy of Science and pro ject manager Valery N. Vanyukov of State Scientific Center - Research Institute o f A tomic Reactors (RI IAR) . Mr. Ponomorev delivered a speech on “Status and Future of Space Reactors of Russia” and expected to promote related co-operations with CIAE.

Editorial9

by Afrikantov at the Nuclear Industry China Exhibition (NIC) organized by the

Chinese Society of Nuclear Sciences in Beijing.

The first unit is to be in operation in 2018, and the second following about a

year later.

A second phase, with units 3 & 4, is due to commence building in 2015.

ENRICHMENT

In 2010 China needed 3600 tU and 2.5 million SWU of enrichment. In 2020 it

expects to need 10,000 tU and 7 million SWU.

A Russian centrifuge enrichment plant at Hanzhun, SE Shaanxi province,

was set up under 1992, 1993 and 1996 agreements between Minatom/

Techsnabexport (Tenex) and CNEIC, covering a total 1.5 million SWU/yr

capacity in China at two sites.

The first two modules at Hanzhun came into operation between 1997 and

2000, giving 0.5 million SWU/yr as phases1 & 2 of the agreements.

The core business of Tenex is the export of conversion/uranium enrichment

services (SWUs) and enriched uranium product (EUP) produced by the

companies of the nuclear industry. A very prospective area of the Company's

business is the implementation and realization of engineering projects related

to the creation of the Nuclear Fuel Cycle production enterprises, including the

construction of a gas centrifuge uranium enrichment plant in China.

In November 2007, Tenex undertook to build a fourth 0.5 million SWU/yr of

capacity at Hanzhun. The agreement was signed in 2008 for 1 billion USD.

The scope of Tenex’s obligations under the contract include designing the

primary manufacturing facility, supplying key technological and auxiliary

equipment, providing consulting services during the installation and

commissioning, providing designer supervision and training Chinese experts in

Russia.

Over 70 members of the Directorate of Russian technical experts provided

guidance, general supervision and design supervision during installation and

commissioning on site. Chinese experts were trained at Angarsky Electrolysis

Chemical Plant.

FUEL

CNNC is responsible for the fuel fabrication.

TVEL produces nuclear fuel for pressurized water reactors, uranium-graphite,

Over 100 Russian organizat ions, equipment manufacturers and service suppliers, are involved in the fulfillment of the contract, including the following institutes:

• JSC Kovrov Mechanical Plant

• JSC East-European Head Design and Research Institute of Integrated Power Engineering Technology

• JSC Novosibirsk Institute VNIPIET

• JSC Tochmash

• JSC Zarubezhatomenergostroy

• JSC Atomenergoproekt

• JSC Ural Electrochemical Plant

• JSC Angarsky Electrolysis Chemical Plan

First concrete pouring started at Tianwan-3

Credit: Rosatom.ru

Editorial 10

fast neutron reactors as well as for research and vessel-mounted reactors.

JSC Novosibirsk Chemical Concentrate Plant provided the first core and three

reloads for Tianwan 1&2.

In November 2010, TVEL contracted with Jiangsu Nuclear Power Corporation

(JNPC) and CNEIC to supply six fuel reloads for Tianwan 1.

November 2011, TVEL contracted for a supply for six reloads of TVS-2M nuclear

fuel for unit 1.

Starting from the seventh reload, JSC TVEL will transfer its TVS-2M fuel

manufacturing technology to CNNC’s subsidiary China Jianzhong Nuclear Fuel

(JNF) located in Yibin, Sichuan.

In addition, TVEL signed a contract for supply of Russian zirconium components

needed for the China-based manufacture of UTVS fuel for the 6th reload of

TNPS units 1 and 2 and TVS-2M fuel for the 7th reload of TNPS unit 2.

The total value of the contracts totals approximately $500 million.

ISOTOPE

In 1989, the predecessor of the NIIAR, the Scientific Research Institute of Atomic

Reactors initiated cooperation with the CIAE in the production of a variety of

radioactive sources, including californium-252.

The Department of Isotope is an important R&D base for isotope technology with

top maximum technical ability and the greatest scale in China.

It also includes the following entities:

The Research Center for National Isotope Engineering Technology,

The Isotope Committee of China Nuclear Society,

The Isotope Specialty Committee of China Isotope and

The Radiation Profession Association.

The Department of Isotope has been engaging in the R&D work in the area of

isotope technology including:

The development direction of isotope,

Advanced technologies to the industry and economy,

New products development,

The construction of the Akademik Lomonosov

The hull and sections of vessels for the first floating nuclear power plant are under construction at Saint Petersburg.

The reactors were designed by OKBM Afrikantov and are assembled by Nizhniy Novgorod Research and Development Institute Atomenergoproekt. The two reactors on board will be KLT- 40S units similar to those used in Russia's nuclear-powered naval and icebreaker fleets. Izhorskiye Zavody produces the reactor vessels and Kaluga Turbine Plant supplies the turbo-generators.

The nuclear power plant was designed for a life of about 36 years.

Fuels used in the construction can ensure its normal operation for 10 years, during which, its production capacity can meet the lighting and heating demand of a city with a population of 100,000.

The project and its periphery construction will require an investment of 6 billion US dollars, costs of which will be recovered within 10 years.

Floating Power Unit (FPU)

Credit: okbm.nnov.ru

Editorial11

Technology transfer and

Training and other type of education.

The NIIAR has an advanced level in high flux nuclear reactors,

and can produces a variety of high specific activity radionuclides.

In 1992 CNNC and Rosatom created Beijing Shuangyuan

Isotope Technology (Shuangyuan).

The company is an important supplier of medical and industrial

cobalt-60 source and the exclusive californium-252 neutron

source supplier.

The Russian side has provided specialized equipment for

preparation of californium-252 neutron source, technical

information, and technical training for Chinese experts.

Since 1996, Shuangyuan produced medical source of

iridium-192, cobalt-60 medical source, medical californium

-252 source and other derivatives of a cobalt-60 source. Today,

the domestic production of iridium-192 is exclusively from

Shuangyuan. Meanwhile, the company also provides semi-

selenium -75, nondestructive testing of iridium-192 and cobalt-60

source.

Shuangyuan just celebrated its twenty year birthday in October

2012.

FLOATING NUCLEAR POWER PLANTS

During the 2010 annual meeting between Russia and China,

Sergei

Kiriyenko discussed a probable partnership in floating nuclear

power plants with Chen Quifa, chairman of the China Atomic

Energy Authority.

China needs clean energy as its ecological environment

continues to deteriorate. Compared with the traditional nuclear

power plants, floating ones have better antiseismic performance

and a smaller risk of a radiation leaks.

in addition to this, floating plants can support a desalination of

up to 24 million tons of seawater.

Rosatom will be in charge of all the construction, operation and

staff training.

In December 2012, Russia and China held their first meeting

for cooperation in the development of marine nuclear energy for

floating power plants and potentially for the propulsion of large

ships.

Chinese interest in this kind of power source has grown steadily

in recent years and has now reached the level of formal

cooperation. The first meeting for this was held at the end of

November in Chengdu, Sichuan province. Around the table

were representatives of power plant operator Rosenergoatom,

designer OKBM Afrikantov as well as CNNC and its subsidiary

the Nuclear Power Institute of China (NPIC).

The Sino-Russian nuclear cooperation embraces major

segments of the nuclear market. Both countries indicate their will

to export the products of their cooperation, such as the VVER,

and floating nuclear power plants to third countries.

At the same time, we can expect a rising competition between

Rosatom subsidiaries, Rusatom Overseas and Atomstroyexport,

and their Chinese counterparts CNNC, SNPTC and CGNPC in

Argentina, South Africa and other countries that need nuclear

power plant with a strong financing.

As for the sales of small reactors overseas, AKME-engineering

which develops a lead and bismuth coolant 100 MW reactor

unit (SVBR-100) and OKBM that designs the ABV-6M, KLT-40S,

ATETs-80 will face INET and NPIC for their HTR and ACP100.

Sources: Refer to last page of Dynatom

12 Interview of the Month

DPS: Could you share your background with us?

Alexander L. Berenzon: My name is Alexander Berenzon. I am the head of the Department for Public Relations and Exhibition Activity of JSC “Afrikantov OKBM” (Russian Federation). I have been working in the nuclear industry for about 12 years; my activity is in information and analytical work. I worked in the OKBM Department for Scientific and Technical Information for few years as a specialist of search and analysis of scientific and technical information. Nowadays I organize the working process of the Department for Public Relations and Exhibition Activity; I participate in the publicity and exhibition actions, enlightening activity, media relations, cooperation with the local media and stakeholders.

DPS: What is OKBM’s historical background in the nuclear power industry?

Alexander L. Berenzon: Joint Stock Company “Afrikantov OKB Mechanical Engineering” (JSC “Afrikantov OKBM”) was created in 1945 to solve the first Soviet “Atomic Project” tasks. The first head of the organization was Igor Afrikantov, the distinguished designer and creator of new equipment for the atomic and power industries. We are very proud that his name is in the name of our company now. Igor

Afrikantov was the founder of the present structure of our company, which includes the powerful designing division, the experimental production facilities and the research and testing complex. About 500 nuclear reactors and steam-generating units, a few hundred of various kinds of equipment for the nuclear industry, power industry and fleet have been created during recent decades by the projects and with direct participation of OKBM. The total lifetime of their operation is more than 10,000 reactor-years, which is comparable with the time of operation of all power reactors in the world’s experience. Particularly, 25 types of gas-diffusion machines were developed in OKBM in the 1940-1950s, nine machines were put into serial production. The first Soviet manufacturers of enriched uranium were equipped with these machines. Also 9 uranium-graphite reactors and 7 heavy water reactors for production of weapon-grade nuclear materials and isotopes were created by the projects with participation of OKBM. Since the 1950s, a few generations of nuclear steam-generating units for Russian Navy ships have been developed and put into serial production by OKBM. In addition, as you know, Russia is the only country in the world which has a nuclear icebreaker fleet, and “Afrikantov OKBM” is a developer of a few generations of reactor units for nuclear icebreakers - starting from the reactor for the first icebreaker “Lenin” (put into operation in 1959) and including operating ships. Another great page of our company history and the pride of the Russian nuclear industry are fast nuclear reactors. In the 1960s and 1970s OKBM developed and took part in the construction of the fast nuclear power reactors BN-350 in Kazakhstan and BN-600 at Beloyarsk NPP (Sverdlovsk region of Russia). The BN-600 reactor has been operating for more than 30 years confirming the high-level parameters and the correctness of technical ideas which were developed by OKBM engineers few decades ago.

DPS: What services does OKBM provide to the nuclear industry?

Alexander L. Berenzon: Nowadays Joint Stock Company “Afrikantov OKBM” is a part of the machine building

Interview with Alexander L. Berenzon，Head of Public Relations Department，

JSC "Afrikantov "OKBM

BN-600 Reactor (central) Hall

E-mail: [email protected] Phone: +7 (831) 246-98-27



division “Atomenergomash” of the Russian State Atomic Energy Corporation ROSATOM. OKBM is one of the leading scientific, production and design companies of the Russian nuclear industry. Besides the powerful design team, which has created the key technologies of the country’s nuclear industry, OKBM has his own research and production base. This allows for creating various types of reactor units with a large power range (both for ships and for nuclear power plants), some equipment for them is complex. The company is the chief designer and package supplier of the BN-800 fast sodium-cooled reactor unit for the fourth power unit of Beloyarsk NPP (under construction with a generating capacity of 880 megawatts), the small-sized reactor units KLT-40S for the “Akademik Lomonosov” floating nuclear power plant (also under construction). In addition, JSC “Afrikantov OKBM” has developed and supplies a wide range of equipment for nuclear power plants under operation and under construction - including pumps, ventilating equipment, heat exchangers, accessories and nuclear refueling equipment. The OKBM business area also includes creation of general non-standard industrial equipment for enterprises of the fuel-and-energy complex, chemical, oil-refining, gas, shipbuilding and other industries.

DPS: What projects does OKBM have in nuclear industry?

Alexander L. Berenzon: In compliance with the Federal Task Program, JSC “Afrikantov OKBM” is developing the design of the BN-1200 new-generation sodium-cooled fast reactor of 1200 MW (electrical) capacity. This reactor will be competitive with VVER (PWR) reactors of the same capacity for technical and economical parameters. The BN-1200 reactor is planned for serial construction after the year 2020. OKBM developed the detailed design of the RITM-200 innovative reactor unit for a new-generation of universal double-draft nuclear icebreaker. It designs small and medium sized reactors (from 6 to 600 MW), including those as a part of floating nuclear power plants, to be used in the remote regions with decentralized electricity

supplies and expensive fuel, and in developing countries, which do not have their own nuclear energy. Another project among the innovative reactor designs developed nowadays by OKBM with international cooperation is the Russian-American project of the GT-MHR, a high-temperature nuclear reactor with a helium coolant and a gas-turbine power conversion unit. This project has a great future, because it will allow the application of industrial-scale nuclear electricity and heat generation to produce the fuel of the future – hydrogen.

DPS: How much does your R&D take of your annual budget? What’s your strategy toward R&D?

Alexander L. Berenzon: In 2011, R&D accounted for 31.7% of our proceeds- about $122 million. The long-term development strategy of “Afrikantov OKBM” includes the plans to increase this parameter by about two-and-a-half times by the year 2020 – up to $323 million (see our annual report for details).

DPS: When did OKBM enter the Chinese nuclear market?

Alexander L. Berenzon: The cooperation began about sixty years ago. In the 1950s, OKBM participated in the development of the heavy water research reactor for the research center in the People’s Republic of China. Our Chinese colleagues performed complex research on this reactor. A large team of our designers and technologists participated in the mounting activities on the reactor. The participants of this work received Chinese governmental awards for successful completion of construction.

Since the 1990s, OKBM has taken part in a large cooperative work of development of the 65 MW capacity CEFR experimental fast sodium-cooled reactor in China. The construction of the reactor was performed by Chinese specialists in close cooperation with Rosatom’s enterprises, including JSC “Afrikantov OKBM”, JSC “SPbAEP”, SSC RF IPPE, JSC “TVEL”, JSC “ZiO-Podolsk” and others. JSC “Afrikantov OKBM” as the chief designer of the reactor unit and work coordinator, it provided design, manufacture and supply of the equipment, technical consultations and personnel training in equipment operation. In 2011, at the China Institute of Atomic Energy, the CEFR was started up with participation from Russian specialists from “Afrikantov OKBM”. This was a significant landmark in the development of fast reactors and Chinese nuclear energy. As for the future perspectives of Russian-Chinese collaboration, they

Floating Power Unit with KLT-40S Reactor Plant


mainly refer to the Chinese Government’s plans to construct new nuclear power plants in the country. Particularly nowadays, the two countries are negotiating on the construction of a nuclear power plant with two BN-800-type fast reactors in China. We hope this NPP project will be implemented with mutually beneficial conditions for both sides.

DPS: What were the main obstacles and/or technological challenges you have encountered in China?

Alexander L. Berenzon: The CEFR design development was based on the technical requirements of the Chinese side. I have to note that our Chinese colleagues made very strict initial requirements, which were more exacting than Russian requirements for radiation safety, radioactive emissions and incidents, accepted in the Russian nuclear industry during this period. Nevertheless, the long-term positive experience of Russian enterprises (including OKBM) in the development, construction and successful operation of fast sodium-cooled reactors gave the possibility for Russian specialists to meet all requirements of the Chinese side in the CEFR design.

DPS: Do you cooperate with Chinese companies? What do you think of the way they do business?

Alexander L. Berenzon: Our Chinese colleagues are very actively working in the world’s nuclear industry market, and though there was a short timeout in China’s nuclear industry (as in the other countries) following the incident at the Japanese “Fukushima” nuclear power plant, we now see that

Chinese nuclear energy is developing very actively, there are the plans of new NPPs construction, and China’s position in the world nuclear market is becoming stronger. Nowadays our collaboration, as I have already said, is associated with the negotiations about the plans to construct a twin-unit nuclear power plant with BN-800 type fast reactors in China, and with the possible cooperation in the field of creating floating nuclear power plants.

DPS: What’s your future strategy to develop in China?

Alexander L. Berenzon: It depends on the decision of our Chinese colleagues about further deployment of Russian fast reactors in China. As “OKBM Afrikantov” undertakes only a part of the work in a large and complex process of new NPPs construction (our role is to design and package supplies of reactor units and other equipment), the strategy of our presence in the international nuclear markets is developed by our main company – State Corporation ROSATOM and its machine building division “Atomenergomash”. As you know, arrangements were made between Russia and China on construction of third and fourth units of the Tianwan NPP, and if OKBM wins the tender, we plan to supply the equipment made by ourselves, including pumps and heat exchangers, to this plant. Concerning our own vision of OKBM and Rosatom’s future presence in the Chinese nuclear market, we think it is necessary to continue developing the mutually beneficial collaboration of our countries. Russia and China see the great opportunities of the industry’s development and are among major players in the world market of nuclear technologies.

Afrikantov OKBM Buildings Prospect


Interview with Mr. Alexander Gordeev, Deputy Director, POLIMASTER INTERNATIONAL

D P S : C o u l d y o u t e l l u s a b o u t y o u r b a c k g r o u n d , a n d w h e n y o u j o i n e d Polimaster?

Alexander Gordeev: I am both an engineer and a marketer. I graduated from the Belarusian State University with

a major in radio-physics and electronics, I have a master’s

degree and PhD from this university, and I also have an MBA

from Colorado University at Boulder in the US.

I joined Polimaster in 2000 and was responsible for sales and

marketing and technical support for North and Latin America,

Asia, the Middle East and all other regions except the European

and CIS markets. In 2004 we established Polimaster Inc., in

Arlington, Virginia, and I was responsible for establishing the

company. During the first year I was managing the company,

after that I was involved in the set-up of Polimaster Instruments

UAB in Vilniaus, Lithuania, the manufacturing and sales

company in the European Union market. For the last three years

I have been working as director of sales and marketing for the

group of companies for all Polimaster offices worldwide.

Polimaster has production and marketing facilities in four

geographic regions. Our office in the US is responsible for North

and Latin American markets. The office in Minsk is responsible

for the former Soviet Union, Middle East and Asian markets.

Our office in Japan is responsible for Japanese and nearby

regions, and facilities in Lithuania cover sales, manufacturing

and technical support for the European Union.

DPS: Alexander Antonovsky created the company more than 20 years ago, what was his motivation for starting the company? Was it related to the Chernobyl disaster?

Alexander Gordeev: Minsk was a major research and development center for the former Soviet Union in the area

of radiation measurement and all CBRN portable detection

instrumentation in general.

There were large factories and government research institutes

responsible for the design and manufacturing of equipment

such as dosimeters, radiation detectors, monitors and so on

for the different industries, including emergency, nuclear and

aerospace. Therefore there were a lot of professional staff and

engineers who had very good experience in developing such

products and instruments.

When the Chernobyl accident happened, it was a problem to

find dosimeters that could work within high radiation background

levels. This team of engineers in Minsk was responsible for

designing equipment capable of dealing with the Chernobyl

accident and correctly measuring emergency dose rates

and personal exposure, being capable of working in severe

environmental conditions, as well as dosimeters for the public.

Polimaster Phone: +375-17-3963677 Email: [email protected]

Calibration Station



So engineers in Minsk had a lot of experience and in 1992, when

the Soviet Union collapsed, many engineers lost their jobs after

major research institutes closed. They considered their futures,

and Alexander Antonovsky, who was one such engineer decided

to start the company Polimaster to continue the design and

manufacture of dosimeters and radiation detection equipment.

This is how Polimaster was founded in 1992.

DPS: You manufacture some 140 types of equipment. What type of radiation measurement equipment does Polimaster engineer and manufacture?

Alexander Gordeev: We have several product lines and various models within each product line. Basically the product

selection is designated to meet every need of people who deal

with ionizing radiation, and are responsible for the detection of

such radiation.

The first group is electronic personal dosimeters designed to

measure dose, personal dose, and dose rate, as well as sound

an alarm in case thresholds are exceeded. They are used for

personnel safety.

The second group is personal radiation detectors that are much

more sensitive devices compared to electronic dosimeters and

are intended for the search and location of sources of ionizing

radiation, so they have a very good response time to the

variations in the ambient radiation levels and sound immediately

in case of the detection of any presence of ionizing radiation.

The third group is radionuclide identifiers, designed to collect

spectra and tell the user what exactly caused a radiation alarm

and the nature of the radiation detected.

Polimaster also has a product line of the large radiation portal

monitors, which are installed at the border crossing points and

checkpoints of entry and exits of perimeters that need to be

controlled.

There is also a product line of combined instruments designed

to perform several functions such as ionizing radiation detectors,

chemical and biological detectors and contraband detectors.

So, basically, Polimaster has a complete range of equipment

for safety and security in the nuclear industry, environmental

protection and any other fields where prompt and accurate

measurement of ionizing radiation is needed.

DPS: What is your annual production capacity?

Alexander Gordeev: It changes year to year but on average we build about 20,000 pieces of equipment of different

types, from very small pocket dosimeters to very large radiation

portal monitors.

DPS: In 1992 you had 15 employees and 20 years later around 200 employees located in Belarus, Lithuania, Japan, and the United States - how do you explain this fast expansion?

Alexander Gordeev: Mainly this was due to an increase in demand for the type of equipment that Polimaster produces. It

was driven by historical events and world changes.

After the collapse of the Soviet Union, and at the very beginning

of Polimaster’s history, there was a demand to control the illicit

trafficking of radioactive material from the former Soviet Union.

So there were a lot of projects funded by the International Atomic

Energy Agency, US State Department, DOE etc. to test, select

and install equipment that is capable of detecting and controling

trafficking of radioactive and nuclear materials at the borders and

within CIS countries. Polimaster was one of the companies that,

due to very professional engineering team, capable of designing

Calibration Station_Collimator


equipment that fully met international safety requirements and

in fact set up industrial standards for many types of equipment

used for radiation detection and measurement in this area.

Another growth factor in the market for radiation detection

products was the events of September 11, 2001 in the US. The

world understood the threat of using radioactive and nuclear

materials by terrorists and a lot of R&D and government funding

was dedicated to designing better equipment to prevent and

address this.

DP S: You a re loca ted in Tokyo and represented by Marubeni Nuclear Services; have you seen any specific requirement or increase of your operation following the Fukushima accident?

Alexander Gordeev: Yes, the Fukushima accident had one major effect on Polimaster – during the week after it

happened, we sold out all inventory as well as all manufacturing

capacity for the 6 upcoming months. The demand from

the market was huge and any kind of equipment capable

of measuring radiation – dosimeters, radiation detectors,

identification device and so on – were scarce. I recall this was

very similar to the situation after the Chernobyl accident in

the former Soviet Union – there was no instrumentation, no

knowledge, no training, and people did not know what to do

regarding the radiation. In response to this growing demand we

increased production capacities and established Polimaster’s

office in Tokyo to serve as a service center, this was very

important for the Japanese customers.

DPS: Is your market still growing in Japan?

Alexander Gordeev: Right now it is steady, a lot of manufacturers of radiation detection equipment of questionable

quality supplied a lot of products to Japanese markets, but

users in Japan now prefer to acquire quality and professional

specification products, not just any equipment that detects

radiation, so for Polimaster’s equipment which was always high-

end in terms of technical performance and specification, the

demand remains high, but significantly smaller compared to just

after the accident. The market has also shifted to the different

types of radiation detection products, for example equipment for

measuring food or soil contamination, etc.

DPS: You firstly manufacture dosimeters and your range of products even expands to wristwatch gamma indicators - what drives your engineering? How come you offer more than 140 types of equipment - is it to remain leader or address perpetual new demands from the market?

Alexander Gordeev: There are two main factors that drive our engineering; the first one is the demand from the

market. Many products were designed to answer specific market

requests. For example, dosimeters that can work in severe

environmental conditions. We designed ours to meet special

needs of customers such as the uranium mines, first responders

and so on.

The other factor was the challenge to build something that

outperforms the market. For example, you mention the Swiss

watch, it was designed because we just could do this. We could

miniaturize the product and put it in a wristwatch - that was

impossible for any other company in the world to do at that time.

These two factors remain nowadays as well, for example last

year we engineered a food contamination monitor, which was

driven by post Fukushima demand.

DPS: When did you enter the Chinese market?

Alexander Gordeev: We’ve been delivering occasionally to China from the very beginning of Polimaster, but regular sales

Calibration Station_Verification of the instruments


and technical support of radiation detection equipment started

in 2000, when the first official dealer/distributor in China was

assigned – BELAZ Trading and Service Co.

DPS: And who was your first client? A nuclear power plant operator or another client?

Alexander Gordeev: It was thirteen years ago - quite hard to recall now! In general, Polimaster was mostly distributed

for the interest of Environmental Protection Agency throughout

Mainland China at that time. Some models of Polimaster

products were well accepted by such markets as Customs

and Border Protection services, and later on, we entered the

Chinese nuclear industry market with our Products.

DPS: When you entered this market did you see any specific barriers?

Alexander Gordeev: The main barrier we faced at that time and one that we still experience is communication and the

language. It is very hard to understand and to build a complete

picture - who is the customer, what does he need, the type

of products does he really want, how to get products to the

customer, etc. These were the main challenges we experienced

at that time. But now we can say that all this is hard but solvable,

even learning Chinese!

DPS: Right now, who are your major clients in China? The operators? The research institutes? Others?

Alexander Gordeev: Right now we work with a number of distributors who sell our products to several

markets:Environmental protection, medical, public safety and

security as well as NPPs and the nuclear industry. These are

our four major market segments in China.

DPS: You have di f ferent distr ibutors representing you - Belaz China, Wahenyida Science & Technology Development and Kadinuo Science and Technology Trading in Beijing, do they have different markets? How to you use them?

Alexander Gordeev: Actually we have one more distributor in China - Newford Tech & Trade, Ltd. They specialize

in a product range but at the same time have a different client

base. Every company has its own pool of clients and they

usually don’t compete with each other.

Kadinuo, for example, is a very good supplier of products for the

nuclear industry - it provides technical support as well, not only

distribution.

But we treat all distributors equally and intend to work on

new projects with all of them, including markets in the nuclear

industry.

DPS: Why did you originally choose an agent rather than dealing direct?

Alexander Gordeev: We decided to go step by step and use evolutionary approach to optimize business risks. So we

started looking for solid local companies, which already had their

own client base - no problem with communication and cultural

barriers, etc. We do plan to open Polimaster’s own technical

service facility in the future in this market.

DPS: You have specific dosimeters created for the Uranium Mining and Nuclear Fuel Production markets. Do you have clients such as China North Nuclear Fuel (factory 202) in Baotou or Jianzhong Nuclear Fuel (Factory 812) in Yibin?

Alexander Gordeev: No, we did not work with these companies. For the mining business, our main customer is

Cameco in Canada. There are two different types of products we

delivered to them, the PM1604 personal dosimeter, designed for

a very severe operation environment to survive in uranium mine,

as well as new personal dosimeter PM1610.

Dosimeter for Mining PM1604


DPS: Do you have cooperation with the operators, such as Daya Bay Nuclear Management Company?

Alexander Gordeev: Our equipment is very well designed to meet the needs of operators of nuclear power

plants, for the protection of the personnel who work with

any kind of radiation sources. But in China we do not deliver

directly to the operators, although many of them use Polimaster

equipment. However we know well and cooperate with CNNC

and CGNPC, we deliver our products to them, and they supply

our products to different locations and entities.

DPS: Since Fukushima, have you seen new specifications in China for your dosimeters and other gamma detection devices?

Alexander Gordeev: The Fukushima accident had a large influence on the market of radiation protection and

measuring equipment, and we see a lot of changes and

new demands in China as well. A lot of people who are not

professionals, who do not face radiation in day to day business,

but are interested in radiation protection, start to think how to

protect themselves, their relatives and understand what ionizing

radiation is. A completely new market has appeared for products

that are easy to use by non-professionals, and designed for

regular households and the public.

Following market demand, Polimaster designed a couple of

new products; one of them is a radiation detector for the iPhone

called Polismart. Any user who has an iPhone can buy the

Polismart Gamma Detector and plug it in to the dock-port, to see

a map, the radiation level and share it with friends.

Another product that was designed following the Fucushima

demand was a detector for measuring contamination of food

and soil with radioactive nuclides. It is, as everything from

Polimaster, professional but small, designed for households,

and easy to use. All existing equipment that measure food

contamination is very large, heavy and quite expensive so we’re

trying to make this technology available for regular households,

make it smaller but provide the same technical specifications

and performance as those in expensive professional equipment.

DPS: But you have not seen any change from CGNPC or CNNC, such as modification of your products?

Alexander Gordeev: We have several projects and requests from those organizations to design dosimeters that

meet their specific needs and we have introduced a number

of new technologies in new Polimaster models of dosimeters -

some of them were driven by demand from the Chinese market

- for example the fast wireless readout of data from personal

dosimeters.

DPS: China imports most of its uranium, in particular from Kazakhstan; have you provided equipment for border control to the Chinese customs?

Alexander Gordeev: Yes, we provided a different type of equipment because we have a large scope of products for

border protection from radioactive materials and we deliver large

portal monitors in China, and other types of detectors used for

Food Contamination Monitor PM1406

Detector for Iphone PM1904


Polimaster_Minsk_Winter_Manufacturing Facility

customs and border protection purposes.

DPS: The Chinese market is the biggest in terms of construction of nuclear power plants, and will become the biggest operator in the next twenty years. Do you have any specific strategy to expand in China and how important is this market for Polimaster?

Alexander Gordeev: The Chinese market is very interesting for us in terms of growth and expansion of the

nuclear power plants, so we have several strategies to find our

niche in this market. We are involved in several projects with

CNNC and CGNPC and try to understand and meet the specific

requirements of those customers, as a result, we are going to

design several new dedicated products for those customers and

in general the entire nuclear industry in China.

We also see a trend in the market towards localization of the

equipment for the nuclear industry. We expect that “Made in

China” will become a requirement for this type of product and

customers in the future, so we try to explore different solutions

on how to do this, for example, find a local partner who we can

cooperate in the long run and localize products, or alternatively,

establish Polimaster’s own branch for sales manufacturing

and technical service in China; So, we are exploring different

possibilities, how to enter the market and to increase our sales.

DPS: If you have any advice to give to a company that wants to enter the Chinese nuclear power market, what would it be?

Alexander Gordeev: Adapt the strategy and the product to the market, make it specific and find a strong local partner

who you can trust. And of course learn Chinese!


DPS: You are one of the main suppliers of equipment for the radiation monitoring and radioecology applications, could you tell us more about other activities? )

Alexey Nourlybaev: Nowadays Doza is relatively large company for the market segment, employing over 200 people. We have recently finished constructing a separate manufacturing building which boosts Doza’s growth potential significantly. We mainly focus on the following segments in the market: portable radiation monitoring and spectrometry, radiation monitoring systems (RMS), medicine and lab equipment, calibration devices. Doza’s huge range of devices greatly diversifies our income and makes Doza fairly independent from demand changes in the market. We deal with almost every aspect of radiation monitoring and control, looking for a way to offer complete solutions to a customer.

In addition, Doza issues its own scientific magazine “ANRY” which is very popular among radiation monitoring professionals in Russia. We also arrange refresher courses, inviting the best scientists as lecturers. Our private educational institution is called “Monitoring and Safety”. It has all the licenses required

DPS: Could you share your background with us? When did you join Doza and what’s your position?

Alexey Nourlybaev: I graduated from Moscow Engineering and Physics State University in 2003. This university is the main source of well-educated personnel for nuclear facilities in Russia. I have explored different areas of business – information security, video surveillance systems, etc. But finally in 2009 I joined Doza as the Head of Service and Support. Now I have grown to Head of Sales and Distribution, shifting my focus to setting and achieving strategic goals for the company.

DPS: What’s the historical background of Doza? How was Doza created?

Alexey Nourlybaev: SPC “Doza” Ltd. was founded by several employees of the main metrological research institute in Russia straight after the revolution in 1991 when an opportunity of creating your own company had arisen for any man with business acumen. My father, Kubeysin Nurlybaev, who had the initial idea of creating the enterprise, became Doza’s first director. The name “Doza” means “dose” in Russian, it eloquently explains the company’s line of business. Doza started with supplying radiation monitoring equipment almost from scratch and in my opinion company’s success is the result of the incomparably hard work of the founders.

Interview with

Alexey Nourlybaev, Head of Sales and Distribution, SPC “Doza” Ltd.

Email: [email protected] Mobile: +7 985 6446996

New manufacturing machines in Doza

Device for patient dose measurement during X-Ray procedures


2010. We also supplied different kinds of lab equipment such as UMF-2000 spectrometer and portable dosimeters. China has shown fantastic growth in nuclear technologies in recent years, and in my opinion, now is the time to introduce our company’s most advanced products. The portable dosimetry market is fairly full of good devices and I see potential in another area: radiation monitoring systems. We have great experience in supplying and setting up large RMSes as a complete solution - including at the design stage.

DPS: What projects does Doza have in China?

Alexey Nourlybaev: Several months ago Doza took part in the NIC’2012 exhibition in Beijing to evaluate potential customers’ interest in our equipment. I saw people asking detailed questions about different features of our devices. They were technically competent and looked really interested. I see such technicians as one of our main “catalysts” in China. Now the main task is to give them all the information they need on Doza’s equipment.

It is too early to talk about large projects in China. We need to earn customers trust starting from fairly small supplies. However, we made fairly large supplies of portable dosimeters through China to Japan right after the horrible Fukushima Daiichi nuclear disaster.

DPS: What were the main obstacles and/or technological challenges you have encountered in China? How did you overcome them?

Alexey Nourlybaev: The main obstacle we need to

and issues official certificates to its students.

DPS: What’s your strategy to ensure your products’ competitive edge?

Alexey Nourlybaev: The composition of innovative features, high quality and fair prices makes Doza one of the most competitive equipment manufacturers in Russia. The metrological background of our founders allows Doza to provide unique measuring accuracy, which is considered very valuable by Russian specialists. Our experts participate in standards and requirements development as members of several domestic and international technical committees. The radiation monitoring segment is strictly regulated, which makes standards compliance mandatory, requiring Doza to supply equipment only after thorough tests of every piece. It is very important to continue being the leading manufacturer, not only supplier, although many companies which I know have switched from making their own equipment to reselling. In my opinion it is a dead end for a company itself and its activity area.

DPS: What’s your strategy on product R&D? How much share does your R&D take in Doza’s annual budget?

Alexey Nourlybaev: R&D is one of the main departments in Doza. I cannot disclose exact numbers but our R&D account is almost unlimited. The only limit for research is the number of experts in the market. Doza has fairly strong team of researchers and is still headhunting in Russia and abroad. For example, we had to “steal” a highly-skilled scientist from CERN. Doza also employs students from the main technical universities in Russia.

DPS: You are one of the main suppliers of equipment for the radiation monitoring for IAEA, the US Navy and Russia, when did you arrive in the Chinese market?

Alexey Nourlybaev: We started several years ago supplying equipment for Tianwan NPP, which was launched in

Laser cutting machine in Doza

Personal dosimeter


overcome is that Doza is not well-known in China yet. We have equipment, which is cheaper than MGP’s and Canberra’s devices for example, and has better characteristics. We are new in the market, and that is why we need to work hard to show Chinese customers that our devices are among the top products in the world. Moreover, despite our equipment is fully IEC compliant, Chinese customers are often interested in running additional tests. It is hard for us to discover all aspects of the certification processes in China, but we count on Chinese partners help.

DPS:Do you have a local team to support Chinese customers? How many people are working on the support team? If not, how does Doza respond to Chinese customers’ requirements?

Alexey Nourlybaev: We have a partner, which had positive experience of supplying fairly large RMS fully manufactured by our company: Shanghai ZDAN International Co., Ltd. We have also trained ZDAN’s engineer for supporting our equipment, including lectures on physical foundation of our equipment operation. They even have Russian translator, who really helps us to communicate quickly with non-English speaking customers.

DPS: You just received a patent for the dose-rate meter/radiometer MKS-15D “Snegir”. Do you have a strategy for this product in China?

Alexey Nourlybaev: I don’t think any special strategy is needed for that kind of a product. Snegir is beta- and gamma-dosimeter. It has a relatively low price and very handy gamma/

beta switch - I think it can compete successfully with other devices of this type.

What I really want to push hard is our cutting-edge RMS devices: radioactive aerosols monitor UDA-1AB, iodine monitor UDI-1B, noble gas monitor UDG-1B, H-3/C-14 monitor UDGB-01, steam generator leakage monitor UDGP-01 and many others. We tried to make the English version of our website most convenient for getting both general and detailed information on every device. We also gave away hundreds of our catalogues at the NIC’2012 exhibition.

We are open to any offers and requests and I hope all our efforts will result in Doza’s rapid development in the Chinese market of radiation monitoring equipment.

ANRI magazine

Cutting edge technology in radiation monitoring from Doza

24 Interview of the Month Hamon Thermal

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Interview with

Sonia Goual,Sales Engineer and Nuclear Segment Leader at Crouzet

DPS: Could you share some of your personal background? When did you join Crouzet and what’s your position?

Sonia Goual: I majored in business management and marketing. I joined Crouzet in 2006 in Germany. I was a business development manager involved in marketing. My market was related to safety products and furthering our successful applications for the European industrial market. I am now Sales Engineer and responsible for the nuclear power market worldwide.

DPS: What is Crouzet’s history in the nuclear power industry?

Sonia Goual: Crouzet is a brand of Custom Sensors & Technologies (CST), a company specialized in sensing, Control and Motion Products. In 2012 it had a turnover of $604M and 4,400 employees. CST offers reliable and efficient components for mission-critical systems in the most demanding and harsh environments.

Crouzet has been involved in nuclear power since the 1980s, and has been qualified by Framatome (Areva) as a supplier for exporting PWR plants, especially in China’s Daya Bay and Ling Ao. In the nuclear industry, Crouzet has been intimately bound to the development of the Chinese market since 1988, and to Korea since the 1990s. Our standard and custom-made products are qualified for LOCA conditions (K1, K2 and K3 according to RCC-E). They are safety components, which are essentially integrated into valves and actuators and more generally. Our products are used for detecting end-of-travel, movement or position.

DPS: So you work with the manufacturers of actuators and valves?

Sonia Goual: We are working with the leading companies in this market. For instance, the Velan regulation valve is one of

our main applications.

I could have also mentioned Rotork actuators in the EPR project, and also Bernard controls.

Our products are also integrated into non-safety equipment such as hoists and ventilation systems and cranes from the company REEL – in Hague for example.

We serve these customers closely thanks to an international

sales force which I coordinate in China, India, Europe, the US

and South-Korea. The initiated projects are designed by a team

of genuine specialized engineers, such as, a member of the

RCC-E board and a standards expert. We are of course closely

coordinated. So, behind every project a dedicated technical team

is supporting the customer’s requirements. This organization is

supported by plants in Europe (France), US (California) and Asia

(China).

This know-how is recognized by our membership in major nuclear associations like PFCE and GIIN.

E-mail: [email protected] Mobile: +33 (0)6 89 10 31 43

Paul Papelier, Sonia Goual and Michel Dorey : Standards & Approvals Manager



DPS: You mentioned that your background is commercial rather than engineering, which is rare in the nuclear market. What advantages does your academic background bring?

Sonia Goual: The nuclear industry is a circle of specialists. I have been trained, but my sales and marketing background has allowed me to create this coordination role and to seek information on opportunities, products and standards to develop and to follow these projects with our experts.

DPS: Where do you operate geographically?

Sonia Goual: I often travel abroad to visit our customers and follow up their projects. On the other hand, customers and power utilities are visiting France where our nuclear engineering team is localized. We do also have regular sales and technical meetings with our international colleagues in order to exchange on new designs, applications and standards.

DPS: Does your Research and Development for the nuclear power market influence your other markets?

Sonia Goual: The core of the nuclear range of products is hermetically sealed cells. This originates in aeronautic applications (e.g. Thrust Reverser Position) that we re-engineered according to nuclear standards.

This shows that we have synergies between markets where

safety criteria like MTBF are keys. To answer your question, nuclear is driving our expertise in explosion proof (ATEX-Ex) applications.

DPS: Which other geographies apart from China and France are you involved in?

Sonia Goual: We have a subsidiary in India and we sell non-qualified products, I mean potentiometers integrated in power plants outside containment.

In Korea, we are cooperating with AREVA in Ulchin (UL1&2). We are also working in Finland (OL3).

DPS: How do you position yourself in the global market for automation control components? Where are your products used in a nuclear power plant?

Sonia Goual: Crouzet is the leader in France and among the top 3 in the world for the microswitch. Our products are mainly localized in the reactor core and around the plant in K1, K2 and K3 areas such as in the Atex environment.

DPS: What materials are your products made from?

Sonia Goual: Our limit switches comprise a hermetically sealed microswitch which combines a snap-action mechanism and a high degree of resistance to shocks, vibration and temperature. The hermetically sealed microswitch is filled with an inert gas that protects the contacts and enables its use in applications from low-level circuits to higher current situations. The meticulous care taken in the manufacture of this hermetically sealed cell in terms of assembly processes, cleanliness of components as well as inspection procedures, results in a product which is ideal for operation in severe environments where a high level of reliability is essential. The Crouzet hermetically sealed cell is particularly well suited to sectors such as Aerospace, Marine and Nuclear.

DPS: What's your strategy for maintaining your competitive edge?

Sonia Goual: The focus is to be “best in class” in terms of quality, reliability and know-how.

Our competitiveness is expressed through our precise technical answers and innovative solutions to customer’s needs.

K1 Limit Switch


We are spending about 7% of our turnover in Research and Development and we have the ability to engineer solutions based on the most innovative technology - like a proximity sensor with remote electronics.

DPS: Do you have an annual audit by EDF?

Sonia Goual: We are a qualified supplier to EDF and our products are part of their procurement list “Liste du Petit Materiel Electrique” as such, we are regularly audited. This is also the

case for most of our customers, OEM’s or power utilities.

DPS: How do you see the international competition emerging?

Sonia Goual: In the 1980s and 1990s, our accessible market was concentrated in France.

Nowadays, we have noticed that there are new players, especially in China. The technical and standards barriers are so strong that it is difficult for newcomers to compete against current western switch suppliers. The competition concerns the technology used in the power plant (CPR1000/ERP versus AP1000) and is a matter of qualification.

DPS: Do you have the IEEE qualification for the AP1000?

Sonia Goual: Currently our range of products is qualified according to RCC-E. Our business model is to customize our offer to the customer’s technical requests, should that be IEEE qualification, we are ready to adapt to the AP1000 standards and qualify in accordance with IEEE.

DPS: The AP1000 is expected to represent 50% of the Chinese market. How have you adapted your strategy?

Sonia Goual: The market for nuclear power plants is moving from CPR1000 to AP1000. We have decided to invest in

R&D for the AP1000, to focus on this technology and have good

contacts with Westinghouse.

DPS: Do you have HAF 604 accreditation?

Sonia Goual: Our products are not in the scope of HAF 604 accreditation. We are monitoring the evolution of the applicable

list and are ready to file if appropriate.

DPS: You mentioned that you are in the Chinese market for the projects at Daya Bay and Ling Ao via AREVA. Are you working only with CGNPC and in particular on the Taishan EPR?

Sonia Goual: Effectively, our products are used for Taishan in ventilation and valves control applications. Our products are

also embedded in the following Chinese nuclear plants: Fuqing,

Fangjiashan, Hongyanhe, Ningde, Changjiang, Fangchenggang,

Yangjiang, Qinshan and Tianwan.

DPS: I see in your list that you have projects with CNNC.

Sonia Goual: We have good contacts with CNNC, especially in

nuclear power plants.

DPS: When were your direct relationships formed with the Chinese nuclear actors, namely NPP and CNPEC? Has your contact existed since your arrival on Daya Bay and Ling Ao or have you recently developed your network?

Sonia Goual: Our historical partnership has increased with the restart of the nuclear market in China, that is to say,

from 2006 to 2007. We have direct relationships with most

of the Chinese power utilities, and we are working with their

engineering related companies.

Paul Papelier, Design Quality Assurance / member of RCC-E board


DPS: You mentioned that you provide components for local manufacturers of valves. What is the part of your sales with these local suppliers?

Sonia Goual: Our sales are equally shared between Chinese and foreign manufacturers.

DPS: What have been the main obstacles and/or technological chal lenges you have encountered in China? How did you overcome them?

Sonia Goual: By far the main obstacle was the language. At the beginning, the understanding of our qualification reports was a major issue because all of our plans and documents were in French.

They have now been translated into English and Chinese by our

local team.

DPS: Do you have a local factory in China?

Sonia Goual: We have a plant located in Huizhou in the Guangdong province. It was launched in 2009 and employs 250 people. The objective of this entity is to be closer to our Asian customers. Initially, we followed one of our largest industrial customers who wanted to develop its supply chain in China. We have duplicated our French company’s organization including our quality system (ISO 9001) and our Customer Adaptation Center (CAC).

DPS: Is this plant having a great level of autonomy?

Sonia Goual: The plant, which is a fully owned subsidiary, has won a lot of autonomy since its creation and our objective is

"Vue aérienne LPA"

Courtoy™

Global market leader incompression technology

for nuclear fuel pellets

engineering for a better world gea-ps.com/Courtoy

GEA Process Engineering nv . Bergensesteenweg 186, 1500 Halle, Belgium . Tel. +32 2 363 83 00 . Fax +32 2 356 05 16 . [email protected]

GEA Process Engineering China Ltd . Hexian Road 99, 201109 Shanghai, PR China . Tel. +86 21 2408 2288 . Fax +86 21 2408 2222 . [email protected]

• Purpose-designed compression machines for uranium oxide and MOX•Machine design adapted for integration into glove box• Unique air compensator technology for high-precision pellet density control• New “constant density” control algorithm for fast machine set-upand highly accurate process control

• Automated in-line pellet density measuring with feedback to the press

• New high-performance powder feeding system• Hold-up / hold-down system for smooth ejection andavoiding cracks in pellets

• Proven reliability, with presses in operation in a nuclearenvironment for over 40 years

• Service teams based in Europe, USA and China


"Vue aérienne LPA"

Courtoy™

Global market leader incompression technology

for nuclear fuel pellets

engineering for a better world gea-ps.com/Courtoy

GEA Process Engineering nv . Bergensesteenweg 186, 1500 Halle, Belgium . Tel. +32 2 363 83 00 . Fax +32 2 356 05 16 . [email protected]

GEA Process Engineering China Ltd . Hexian Road 99, 201109 Shanghai, PR China . Tel. +86 21 2408 2288 . Fax +86 21 2408 2222 . [email protected]

• Purpose-designed compression machines for uranium oxide and MOX•Machine design adapted for integration into glove box• Unique air compensator technology for high-precision pellet density control• New “constant density” control algorithm for fast machine set-upand highly accurate process control

• Automated in-line pellet density measuring with feedback to the press

• New high-performance powder feeding system• Hold-up / hold-down system for smooth ejection andavoiding cracks in pellets

• Proven reliability, with presses in operation in a nuclearenvironment for over 40 years

• Service teams based in Europe, USA and China

to allow the plant to become as independent as possible.

DPS: Will your Chinese entity be able to directly follow your Chinese customers?

Sonia Goual: For the moment, all our nuclear products are manufactured in France. We do not meet specific demands from Chinese customers. However, if this were to be the case, we would have no problem transferring nuclear expertise to our Chinese factory.

More globally speaking, our intent is to have local teams managing their domestic markets on both commercial and manufacturing sides. Our teams in Korea, Singapore and India and other countries act locally with the help of French experts when they are needed. This organization allows us to be closer to our customers and to understand them better.

DPS: Are you working on other types of reactors, such as the HTR or Fast breeders?

Sonia Goual: Currently we are on the PWR and VVER.

DPS: Fukushima has had the effect of directing a number of foreign companies to purchase guaranteed high quality and know-how. Have you felt this change or rather a tendency to look at mainly the price of the component?

Sonia Goual: In the nuclear industry, we never felt bound by the price trends. We are in different markets that are very price-sensitive, such as automotive, but quality is key. With Fukushima, we had to respond to more questions about qualifications. We have been very pleased with these questions as we were able to prove that we were fulfilling the most demanding requirements.

DPS: Can you explain why you will stay number one in France and a world leader?

Sonia Goual: Crouzet, a brand of CST, has existed since 1921 and has 40 years experience in the nuclear market.

In addition, Custom Sensors & Technologies (CST) is a financially healthy company and a durable partner.

http://www.gea-ps.com/npsportal/cmsdoc.nsf/WebDoc/ndkw73fafk

http://www.gea-ps.com/npsportal/cmsdoc.nsf/WebDoc/ndkw73fafk


Kabelwerk EUPEN AG is an independant and fully integrated

manufacturer of Electric Cables & Wires, employing 930 people in its

factories in Belgium.

The product range includes MV & LV Power Cables, Instrumentation

& Control Cables, Telecommunication Cables (Copper, Coaxial,

Fibre Optics) and last but not least Halogen-free Fire Safety Cables.

Within the last product family, EUPEN also stands for 30 years

experience in manufacturing 1E-LOCA qualified cables and cables

for use outside containment of Nuclear Power Plants.

NPP Qualified Accident-P

roof Cables

NPP Qualified Halogen-fr

ee Cables

A4 Blatt China Nuclear 2_A4 Blatt London Nuclear 18/12/12 14:54 Seite 1

31 HAF Regulations

Kabelwerk EUPEN AG is an independant and fully integrated

manufacturer of Electric Cables & Wires, employing 930 people in its

factories in Belgium.

The product range includes MV & LV Power Cables, Instrumentation

& Control Cables, Telecommunication Cables (Copper, Coaxial,

Fibre Optics) and last but not least Halogen-free Fire Safety Cables.

Within the last product family, EUPEN also stands for 30 years

experience in manufacturing 1E-LOCA qualified cables and cables

for use outside containment of Nuclear Power Plants.

NPP Qualified Accident-P

roof Cables

NPP Qualified Halogen-fr

ee Cables

A4 Blatt China Nuclear 2_A4 Blatt London Nuclear 18/12/12 14:54 Seite 1

Supervision and Management Regulations

for Civilian Nuclear Equipment (HAF601)

Chapter 1: General Provisions

Article 1 – In order to strengthen the supervision and administration of the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment, the present regulations are promulgated in accordance with the Regulations on the Supervision and Management of Civilian Nuclear equipment.

Article 2 – These Regulations shall be applicable to business units engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment.

Where maintenance is carried out for any civilian nuclear equipment outside of civilian nuclear facilities, the regulations relating to the manufacturing of civilian nuclear equipment shall be complied with.

Article 3 – The catalogue of civilian nuclear equipment is compiled and released in batches by the nuclear safety administration department and relevant departments of the State Council.

Article 4 – Any business unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment is required to obtain a permit for the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment and to carry out the activities with regard to the design, manufacture, installation and non-destructive testing of civilian nuclear equipment in line with the types, scope and conditions of activity specified in the permit.

Article 5 – The operational units of the civilian nuclear facilities shall conduct the quality management and process control of the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment, and will handle the supervision of manufacturing, inspection and acceptance of such equipment. Furthermore, they are to undertake the inspection, testing and repair of civilian nuclear equipment in service and take full responsibility for the application of the present regulations and

the operational safety of the equipment.

Article 6 – The nuclear safety administration department of the State Council, also known as China’s National Nuclear Safety Administration (hereinafter abbreviated as “NNSA”), shall implement the supervision and management of activities such as the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment.

Chapter 2: Permits

Article 7 – Any unit applying for a permit to design, manufacture, install or conduct non-destructive testing of civilian nuclear equipment shall submit an application to the NNSA according to the type of activities, category of equipment and level of nuclear safety considered.

Any unit applying for the permit to conduct non-destructive testing of civilian nuclear equipment shall submit an application to the NNSA according to the methods of non-destructive testing that are being considered. Methods of non-destructive testing include the following: radiographic test (RT), ultrasonic test (UT), magnetic powder test (MT), eddy current test (ET), penetrant test (PT), leakage test (LT), visual test (VT), etc.

Article 8 – Any unit applying for a permit to design, manufacture, install or conduct non-destructive testing of civilian nuclear equipment shall meet the following conditions:

1. Be a legal person;

2. Have been engaging in work connected with or similar to the activity considered for more than five years;

3. Have on its staff one or several professional technician(s) suitable for the activity it is planning to engage in and will be certified to conduct. Professional technician(s) engaged in welding and non-destructive testing of civilian nuclear equipment should have obtained the corresponding permits;

32HAF Regulations

4. Have available the workplace, facilities and equipment needed to conduct the proposed activity;

5. Have in place a complete management system and a sound quality assurance system in conformity with the regulations on the supervision and management of nuclear equipment.

The specific technical requirements for unit(s) applying for a permit to design, manufacture, install or conduct non-destructive testing of civilian nuclear equipment of different types and levels of nuclear safety shall be stipulated by the NNSA.

Any unit applying for a permit to manufacture or install civilian nuclear equipment shall produce a typical prototype based on the type of equipment, level of nuclear safety, scope of activity, manufacturing and installation technique, material trademark and structure, etc. as shown in its application.

The specific requirements for producing such a prototype shall be stipulated by the NNSA.

Any unit applying for permits to design and manufacture civilian nuclear equipment at the same time shall have to complete the corresponding verification tests during the process of producing the prototype.

Article 9 – Any unit applying for a permit to design, manufacture, install or conduct non-destructive testing of civilian nuclear equipment shall submit the application and the certificates in compliance with the conditions specified in Article 8.

Any unit applying for a permit to manufacture or install civilian nuclear equipment shall also submit the production scheme, quality plan and other documentation in relation to the prototype.

Any unit applying for a permit to design and manufacture civilian nuclear equipment at the same time shall also submit a verification test outline and all necessary related documentation.

Article 10 – The nuclear safety administration department shall undertake the formal examination of applications submitted and accept all applications that meet requirements.

Article 11 – In the process of examining a permit application, the nuclear safety administration department shall call on experts to undertake technical assessments, and seek comments from the State Council’s competent department for nuclear industry activities and other relevant departments. The methods of technical assessment include the inspection of documentation, discussion following inspection and onsite checks, etc.

Where a prototype needs to be produced, the technical assessment shall also include the inspection of the prototype’s production scheme, quality plan and other documentation, and the onsite supervision and observation of the production process, etc.

The NNSA shall complete the inspection within forty-five working days following acceptance of the application, grant the permit to any qualified unit and make a public announcement with regard to the permit granted. It shall send a written notice to any unit whose application has failed to meet requirements and explain the reasons for the rejection of the application.

It shall arrange for the technical assessment to be carried out in accordance with the provisions of Paragraph 1 and Paragraph 2, and not account for the technical assessment in the period specified in Paragraph 3.

Article 12 – Any unit that has been granted a permit to design, manufacture, install or conduct non-destructive testing of civilian nuclear equipment can engage in the relevant activities at the lower level of nuclear safety within the same type of activity, category of equipment, type and scope of equipment, except otherwise specified in the permit.

Article 13 – The permit for the design, manufacture, installation and nondestructive test of civilian nuclear equipment shall contain the following information:

1. The name, address and legal representative of the unit;

2. The type and scope of activities the unit will be allowed to engage in;

3. Period of validity;

4. The issuing authority, issuance date and permit number.

Article 14 – To engage in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment without a permit, or not in accordance with the type and scope of activities specified in the permit is prohibited.

One may not entrust any unit with the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment if the unit does not hold the corresponding permits to engage in such activities.

The forgery, alteration and transfer of a permit are not allowed.

Article 15 – The period of validity of a permit for the design,

33 HAF Regulations

manufacturing, installation and non-destructive testing of civilian nuclear equipment is five years.

Article 16 – Any unit engaging in the design, manufacture, installation and non-destructive testing of civilian nuclear equipment shall apply to the NNSA for a permit extension and submit the extension application and supporting documentation at least six months prior to the permit’s expiry date, in cases where the unit:

1. Has engaged in the design, manufacturing, installation or non-destructive testing of civilian nuclear equipment throughout the period of validity of the permit, and plans to continue undertaking the same activities beyond the permit’s expiry date;

2. Has been engaged in the design, manufacturing, installation or non-destructive testing of civilian nuclear equipment, and cannot complete related projects by the permit’s expiry date.

Any unit that has not engaged in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment during the period of validity of the permit held shall have to re-apply for a permit in line with the procedure specified in this article.

Article 17 – In cases where an application to extend the period of validity of a permit has been made by a unit engaged in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment, the NNSA shall decide on whether to approve the extension before the expiry date of the permit. Should no decision have been explicitly made by such date, the extension of the permit will be deemed granted.

Article 18 – Should any unit engaged in design, manufacturing, installation and non-destructive testing of civilian nuclear equipment change its name, address or legal representative, it will have to apply to the NNSA for the amendment of its permit within twenty working? days following such changes, and submit the application for permit amendment, documentation of its registration with the Administration for Industry and Commerce, a description of the changes involved and the relevant change certificates.

The NNSA shall verify the authenticity of the application for permit amendment. Once the application has been verified, the permit can be reissued. The period of validity of the original permit shall re-apply to the amended permit.

Art ic le 19 – Should a un i t engaging in the des ign,

manufacturing, installation and non-destructive testing of civilian nuclear equipment wish to change the type or scope of activities specified in its permit, it shall have to re-apply to the NNSA for a new permit.

Chapter 3: Quality Management and Control

Article 20 – Any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment shall enhance its safety awareness, establish and effectively implement a quality assurance system, ensure the quality and reliability of the civilian nuclear equipment produced, and submit itself to inspection by the relevant supervisory authorities.

Article 21 – Any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment shall prepare a sub-outline of its project quality assurance plan in accordance the requirements of the operating unit of the civilian nuclear facilities where the equipment produced will be used before it starts any relevant activities. The sub-outline of the unit’s project quality assurance plan will have to be [applicable, complete and definite regarding interface relation], reviewed and approved by the operating unit of the civilian nuclear facilities using the equipment produced.

Any unit engaging in the manufacturing and installation of civilian nuclear equipment shall prepare the corresponding quality plan for the specific activity and provide it to the operating unit of the civilian nuclear facilities using the equipment produced for review and approval.

Any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment shall control the whole process as required by the sub-outline of its project quality assurance plan, and investigate and rectify any problem uncovered.

Article 22 – Any unit engaging in the design of civilian nuclear equipment shall, before engaging in such activities, first ensure that its designers have analyzed and understand the design requirements proposed by the operating unit of the civilian nuclear facilities where the equipment will be used. The unit must also ensure that it is fully aware of and has specified the requirements for design input, and that it has determined the design interface control measures, methods and content of design verification, and design change control measures.

The design unit shall undertake the design verification with regard to its design using approved methods of design

34HAF Regulations

verification at each stage of the design process. The staff in charge of design verification shall have a certain level of experience in design, the ability to perform verifications and a relative degree of independence.

The design unit shall take the control measures for the design change during the design, which are equal to those for the original design.

After the design is completed, the design unit shall continue to provide design services as needed to the unit operating the civilian nuclear facilities using the equipment designed.

Article 23 – Any unit engaging in the manufacturing and installation of civilian nuclear equipment shall, before engaging in such activities, first ensure that its relevant personnel analyzes and understands the technical requirements proposed by the design unit, prepares the manufacturing and installation execution plans in accordance with these technical requirements, and strictly implements the execution plans.

The manufacturing or installation unit shall complete the necessary technical tests and technical assessments for the approved special technique.

The manufacturing or installation unit shall strictly implement the quality plan reviewed and approved by the unit operating the civilian nuclear facilities using the equipment produced.

The manufacturing or installation unit shall test the quality of the civilian nuclear equipment manufactured or installed. Any equipment that has been untested or that has failed testing shall be not handed over for acceptance.

Article 24 – Any unit engaging in the non-destructive testing of civilian nuclear equipment shall prepare and strictly implement the non-destructive testing procedure followed to undertake the specific testing proposed, based on the structure and material features of the equipment to be tested.

The non-destructive testing unit shall issue a non-destructive testing report in an objective and accurate manner.

Non-destructive testing of civilian nuclear equipment shall be conducted under the lead of non-destructive testing operators with Class II or above qualification.

The non-destructive testing report shall be prepared and examined by non-destructive testing operators with Class II or above qualification, who shall handle the relevant approval procedure.

Article 25 – Any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment shall not subcontract the critical technical link as determined by the NNSA to other units.

The list of critical technical tasks shall be prepared by the NNSA.

Article 26 – The operating unit of the civilian nuclear facilities where the nuclear equipment is used shall take full responsibility for the safe operation of civilian nuclear equipment. Before starting activities such as the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment, the operating unit of the civilian nuclear facilities where the nuclear equipment is used shall examine and approve a sub-outline of the project quality assurance plan prepared by any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment.

The operating unit of the civilian nuclear facilities where the nuclear equipment is used shall supervise the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment by overseeing or observing these activities as they are being carried out, and handling the inspection and acceptance of the equipment involved. The equipment shall be not accepted if any of the following were to occur:

1. Where the quality control cannot be verified to have been carried out as required by the quality assurance plan;

2. Where any serious quality problems have not been resolved.

Article 27 – Both the unit engaged in manufacturing, installation and non-destructive testing of civilian nuclear equipment and the operating unit of the civilian nuclear facilities where the nuclear equipment is used shall hire personnel holding welder, welding operator and non-destructive testing operator permits to carry out the welding and non-destructive testing of civilian nuclear equipment.

The welders, welding operators and non-destructive testing operators of civilian nuclear equipment shall carry out their activities in strict accordance with operational specifications.

Chapter 4: Reporting and Filing

Article 28 – Any unit engaging in the design of civilian nuclear equipment shall submit the following documentation to the NNSA for filing within thirty days prior to starting work on the design activities:

35 HAF Regulations

1. List of sub-outlines and outlined procedures for the design project’s quality assurance plan;

2. Contents and schedule of the design work to be carried out;

3. List of standards and regulations complied with and list of computer software used in the process;

4. List of design verification activities.

Article 29 – Any unit engaging in the manufacturing and installation of civilian nuclear equipment shall submit the following documentation to the NNSA for filing within thirty days prior to starting work on the manufacturing and installation activities:

1. List of sub-outlines and outlined procedures for the manufacturing and installation project’s quality assurance plan;

2. Technical specifications of the manufacturing and installation work to be carried out;

3. List of sub-contracted work;

4. Manufacturing and installation quality plan.

Article 30 – Any unit engaging in the non-destructive testing of civilian nuclear equipment shall submit the following documentation to the NNSA for filing within fifteen days prior to starting work on non-destructive testing:

1. List of sub-outlines and outlined procedures for the non-destructive testing project’s quality assurance plan;

2. Contents and schedule of the non-destructive testing to be carried out;

3. The standards, regulations, directory and acceptance rules the non-destructive testing process will complying with.

Article 31 – Any unit engaging in the design of civilian nuclear equipment shall submit, within seven working days of each quarter-end, an activity report for the previous quarter to the NNSA, including mainly:

1. The list of completed designs and list of designs planned for launch and for completion over the next quarter;

2. The list of design alterations put through;

3. The design verification completion list.

Article 32 – Any unit engaging in the manufacturing and installation of civilian nuclear equipment shall, within seven working days of each quarter-end, submit an activity report for the previous quarter to the NNSA, including mainly:

1. The list of completed products and installation work, and a list showing product output and installation work planned for launch and for completion over the next quarter;

2. The list of quality plans for completed products and installation work;

3. A statistic chart showing non-conform products and installation work.

Article 33 – Any unit engaging in the non-destructive testing of civilian nuclear equipment shall report the contents and results of the non-destructive testing to the NNSA within ten working days of having completed the non-destructive testing.

Article 34 – Any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment shall report to the NNSA in accordance with the following regulations:

1. Any major activity conducted in relation to nuclear safety, such as important meetings or discussions, etc. shall be reported seven working days prior;

2. Any serious quality problem noted shall be reported within twenty-four hours;

3. The condition that the operating unit of civilian nuclear facilities commands to stop the activity due to its impact on the quality of nuclear equipment and nuclear safety shall be reported within 3 working days.

Article 35 – Any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment shall carry out an annual assessment of its design, manufacturing, installation and non-destructive testing activities and submit the assessment report for the previous year to the NNSA before April 1st of each year.

The assessment report shall include the description of:

1. All changes to the unit’s workplace, facilities, equipment, staff, etc.;

2. The implementation of the unit’s quality assurance system;

36HAF Regulations

regulations and rules on the supervision and management of nuclear safety;

4. Be honest and upright, handle affairs in a fair manner, work carefully and have an appropriate attitude.

Article 39 – The supervisory inspection of civilian nuclear equipment includes ensuring the following:

1. Compliance with conditions specified in the permit;

2. Qualifications of personnel involved;

3. Implementation of quality assurance plan outline;

4. Conformity with the adopted technical standards and relevant technical documentation;

5. Implementation of critical processes in the design, manufacturing, installation or non-destructive testing of civilian nuclear equipment;

6. Investigation and resolution of serious quality issues, and implementation of requirements for their rectification issued by the NNSA and its subsidiary inspection agencies;

7. Acceptance and verification by the NNSA and its subsidiary inspection agencies of the design, manufacturing, installation or non-destructive testing of civilian nuclear equipment;

8. Manufacturing supervision of the operating unit;

9. Other necessary supervision tasks.

Article 40 – Upon receiving the documentation submitted in accordance with these Regulations by any unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment, the NNSA and its subsidiary inspection agencies shall work out the corresponding supervision plan and notify the unit applying for a permit. This unit shall then prepare to submit itself to supervisory inspection in line with the requirements specified in the supervision plan.

The unit engaging in the design, manufacture, installation and nondestructive test of civilian nuclear equipment shall notify the NNSA and its subsidiary inspection agencies in writing based on the actual progress of the relevant activity ten working days before implementing the activity specified in the supervision plan.

Article 41 – The supervisory inspection of civilian nuclear equipment can be classified in two sub-categories: routine inspection and non-routine inspection. Non-routine inspection

3. Any serious quality issues uncovered and their resolution;

4. The implementation of requirements for rectification proposed by the operating unit of civilian nuclear facilities where the equipment is used;

5. The implementation of requirements for rectification proposed by the NNSA and its subsidiary inspection agencies.

Chapter 5: Supervisory Inspection

Article 36 – The NNSA and its subsidiary inspection agencies shall have the right to supervise and inspect a unit’s activities in design, manufacturing, installation and non-destructive testing of civilian nuclear equipment.

The inspected unit shall cooperate in the supervisory inspection process carried out by the NNSA and its subsidiary inspection agencies, present true facts, provide necessary documentation and not reject or impede the inspection. The inspected unit shall carefully implement all requirements for rectification proposed during the supervisory inspection.

Article 37 – Civilian nuclear equipment shall be supervised and inspected in accordance with:

1. The Regulations on the Supervision and Management of Civilian Nuclear Equipment and other regulations on the supervision and management of nuclear safety;

2. The conditions and scope specified in the permit granted for design, manufacturing, installation and non-destructive testing of civilian nuclear equipment;

3. The national standards, industry standards and the standards approved by the NNSA with regard to civilian nuclear equipment;

4. The quali ty assurance plan outl ine and outl ined procedures examined and approved by the NNSA.

Article 38 – Personnel in charge of supervising and inspecting civilian nuclear equipment shall meet the following conditions:

1. Have graduated from junior college, or received higher education or an equivalent level of education;

2. Have more than five years of engineering experience with civilian nuclear equipment or more than three years of nuclear safety management experience, master the relevant professional know-how, have good communication skills and be able to make correct judgments independently;

3. Be familiar with the relevant laws, administrative

37 HAF Regulations

may not be notified in advance to the unit inspected.

Supervisory inspection can be further classif ied into: comprehensive inspection, special inspection and checkpoint inspection mainly carried out by means of site inspection, documentation inspection, record verification or interviews, etc.:

1. Comprehensive Inspection: includes quality assurance inspection and technical inspection. Quality assurance inspection mainly focuses on whether the quality assurance plan outline has been implemented effectively. The technical inspection primarily includes a spot check on whether the process of designing, manufacturing, installing and non-destructive testing civilian nuclear equipment meets the requirements set by the current standards, regulations and relevant technical documentation.

2. Special Inspection: refers to the inspection for special purposes carried out by the NNSA and its subsidiary inspection agencies on a unit with respect of any issues uncovered or likely to emerge. It mainly involves inspecting the implementation of any technical item or any part of the quality assurance plan outline, as well as the implementation of requirements for rectification issued by the NNSA and its subsidiary inspection agencies.

3. Checkpoint Inspection: refers to the inspection carried out on site, at specific check points.

Whenever necessary, the NNSA and its subsidiary inspection agencies can carry out the verification independently by means of recomputation or inspection verification.

While carrying out the comprehensive inspection or checkpoint inspection of any unit engaged in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment, the NNSA and its subsidiary inspection agencies shall review the adequacy of the personnel in charge of supervising the manufacturing of civilian nuclear equipment and the implementation of such supervisory task.

Article 42 – While carrying out supervisory inspection, the NNSA and its subsidiary inspection agencies shall record the contents of each inspection, the issues uncovered and their resolution, and have the record signed and approved by the personnel in charge of supervisory inspection and the relevant personnel in charge of the unit being inspected. Objective evidence shall be kept if necessary.

Should the personnel in charge of the unit under supervision and inspection refuse to sign the record, the supervisory and inspection personnel will take note of this refusal in the record.

The NNSA and its subsidiary inspection agencies shall prepare

the supervisory inspection report with regard to the information of each supervisory inspection carried out and the corresponding rectification requirements issued, and send it to the inspected unit and other units concerned.

The inspected unit shall implement the rectification measures against issues uncovered during the supervisory inspection requested by the NNSA and its subsidiary inspection agencies, and submit a rectification report to the NNSA and its subsidiary inspection agencies. The NNSA and its subsidiary inspection agencies shall examine the rectification report and undertake to verify the implementation of the requirements for rectification during a follow-up supervisory inspection.

Article 43 – The personnel in charge of conducting the supervisory inspection of civilian nuclear equipment shall have the right to take the following measures:

1. Investigate and gather information from the legal representative of the unit inspected and other people involved;

2. Enter the inspected unit’s premises for onsite investigation or verification;

3. Consult and duplicate relevant documentation, records and other relevant materials;

4. Request that the unit inspected submit relevant explanations or a follow-up resolution report.

The personnel in charge of conducting the supervisory inspection of civilian nuclear equipment shall, in the course of carrying out their duties, immediately stop any conduct found to be outside the conditions and scope of the permit granted, or in violation of nuclear safety supervision and management regulations and of the standards for civilian nuclear equipment. Should such an event occur, a report shall have to be prepared and submitted to the NNSA and its subsidiary inspection agencies.

The NNSA and its subsidiary inspection agencies shall have the right to temporarily seal for safekeeping civilian nuclear equipment or major equipment parts where serious quality issues have been uncovered and are supported by evidence. The temporarily sealed civilian nuclear equipment or major equipment parts shall be submitted to follow-up resolution, and the seal removed only after the NNSA and its subsidiary inspection agencies have verified that the equipment or equipment parts have re-qualified for use.

Supervisory inspection shall be carried out by at least two persons in charge of the supervisory inspection of civilian nuclear equipment, who must present their relevant permits. Such inspection personnel must not disclose the inspected

38HAF Regulations

units’ technology and business secrets. They shall not abuse their power, infringe on the legitimate rights and interests of the companies involved, or receive financial advantages from the convenience of duty, and shall not engage in or participate in operational activities in the civilian nuclear equipment industry.

Article 44 – The NNSA and its subsidiary inspection agencies’ safety inspection personnel shall take full responsibility for the inspection work carried out.

Chapter 6: Legal Responsibilities

Article 45 – The NNSA shall require that corrective measures be taken within a limited period of time if any unit engaged in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment is found to have done the following:

1. Where it has failed to submit the relevant documentation to the NNSA for record before carrying out the non-destructive testing of civilian nuclear equipment in accordance with regulations;

2. Where it has failed to report to the NNSA its activities of design, manufacturing, installation and non-destructive testing of civilian nuclear equipment in the previous quarter in accordance with regulations;

3. Where it has failed to report to the NNSA the contents and results of non-destructive testing after completing the non-destructive testing of civilian nuclear equipment;

4. Where it has failed to report to the NNSA serious issues that were brought up during important meetings and discussions regarding nuclear safety, or circumstances where the operating unit of civilian nuclear facilities has had to suspend operations due to the impact of such issues on the safety of the nuclear equipment being used.

Article 46 – Should any unit engaging in the design, manufacture, installation and nondestructive test of civilian nuclear equipment and the operating unit of civilian nuclear facilities using the equipment have violated the present Regulations, they shall be punished in accordance with provisions contained in these Regulations and other relevant laws and regulations.

Chapter 7: Supplementary Articles

Article 47 – Should any unit applying for a permit to manufacture or install civilian nuclear equipment be planning to independently carry out non-destructive testing of the civilian nuclear equipment manufactured or installed by itself, the unit is not required to apply for a permit to conduct non-destructive testing.

Article 48 – The related terms in the present Regulations are defined as follows:

1. Prototype: refers to a product sample produced by a unit applying for a permit to manufacture and install civilian nuclear equipment following the requirements of the NNSA. The prototype is to be produced on a scale of 1:1 or any appropriate scale, and using materials, structure and characteristics, etc. that are identical or similar to those of the final product targeted. The product must be produced using the same processes, and be submitted to the same inspection and verification processes, etc. as those expected to be used to produce the final product targeted.

2. Verification Test: refers to the test to verify the material object, which is carried out on the prototype during the design process in order to ensure that the design satisfies the preset design performance indices. The verification test includes a functional test, a seismic test and an environmental test (including an aging test and a design basis accident test), etc.

3. Checkpoint: refers to a work process or work node selected for inspection by the NNSA and its subsidiary inspection agencies, based on documentation submitted by the unit engaging in the design, manufacturing, installation and non-destructive testing of civilian nuclear equipment. In terms of different inspection methods, checkpoints are normally classified as either a record confirmation point (R-point), onsite witnessing point (W-point) or hold point (H-point).

Article 49 – The Regulations shall come into effect starting from January 1st, 2008. Meanwhile, the Regulations on the Supervision and Management of Civilian Nuclear Pressure? Equipment (HAF601) promulgated by State Bureau of Nuclear Safety, the Ministry of Machinery Building and Electronics Industry and the Department of Energy on March 4th, 1992 shall be nullified.

Annex I: Forms and Contents of Application for a Civilian Nuclear Equipment Permit, Form for the Scope of Applicant Activities and Application Documents (in duplicate and submitted with electronic files).

Annex II: Form and Contents of a Civilian Nuclear Equipment Permit.

Annex III: Forms and Contents of Application for Extending a Civilian Nuclear Equipment Permit, Form for the Scope of Applicant Activities and Application Documents (in duplicate and submitted with electronic files).

L-3 MAPPS’ Power Systems and Simulation Business Celebrates

40 Years of LeadershipContact: Sean Bradley Senior Communications Specialist L-3 MAPPS (514) 787-4953

MONTREAL, February 12, 2013 – L-3 MAPPS announced today that it is celebrating its 40th anniversary in the power plant simulation business. To commemorate this important milestone, L-3 MAPPS has released a limited edition, 112-page book for its employees and customers titled, “The First 40 Remarkable Years of L-3 MAPPS Power Plant Simulation Leadership.” The book chronicles how four decades of innovation and solid customer partnerships have resulted in the company’s emergence as a market leader.

“From our beginnings as a Canadian start-up in 1973 to our current leadership position in global power plant simulation, our success has been made possible by our esteemed customers and end users. They have empowered us to push technological boundaries and seek state-of-the-art solutions for their most challenging requirements,” said Michael Chatlani, vice president of marketing & sales for L-3 MAPPS Power Systems and Simulation. “It is thanks to them that we are who we are today – a company of people committed to creating value through innovation, working hard to provide high-fidelity simulators that improve the safety of power plants around the world.”

L-3 MAPPS’ many years of pioneering simulation technologies have led to its industry-leading suite of Orchid® software tools, which are widely recognized for their robustness, ease of use and interoperability. In addition, L-3 MAPPS has supplied its state-of-the-art full scope simulators, classroom simulators, part-task trainers, engineering simulators, simulator Digital Control System (DCS) implementations, advanced model upgrades and rehosts to numerous satisfied customers over the past 40 years. It has built simulators for plants of various designs – North American, European and Chinese – that are installed worldwide.

L-3 MAPPS, a division of L-3 Marine & Power Systems, has over 30 years of experience in pioneering technological advances in the marine automation field and over 40 years of experience in delivering high-fidelity power plant simulation to leading utilities worldwide. In addition, the company has more than four decades of expertise in supplying plant computer systems for Canadian heavy water reactors. L-3 MAPPS also provides targeted controls and simulation solutions to the space sector. To learn more about L-3 MAPPS, please visit the company’s website at www.L-3com.com/MAPPS.

Comprising 25 operating companies, L-3 Marine & Power Systems (L-3 M&PS) is a worldwide leader in maritime

automation and control, navigation, communications, dynamic positioning, and power distribution and conditioning for the U.S. Navy, allied foreign navies and commercial customers worldwide. L-3 M&PS also produces full-fidelity simulators for increased operator proficiency, resulting in safe operations for leading utilities and ship operators worldwide. With over 85 locations in 19 countries, L-3 M&PS is a cohesive, global partner with extensive capabilities and a proven track record in delivering the highest level of technology, service and integration. To learn more about L-3 Marine & Power Systems, please visit the company’s website at www.L-3com.com/MPS.

Headquartered in New York City, L-3 employs approximately 51,000 people worldwide and is a prime contractor in C3ISR (Command, Control, Communications, Intelligence, Surveillance and Reconnaissance) systems, aircraft modernization and maintenance, and national security solutions. L-3 is also a leading provider of a broad range of electronic systems used on military and commercial platforms. The company reported 2012 sales of $13.1 billion. To learn more about L-3, please visit the company’s website at www.L-3com.com.

Safe Harbor Statement Under the Private Securities Litigation Reform Act of 1995

Except for historical information contained herein, the matters set forth in this news

release are forward-looking statements. Statements that are predictive in nature,

that depend upon or refer to events or conditions or that include words such as

“expects,” “anticipates,” “intends,” “plans,” “believes,” “estimates,” “will,” “could”

and similar expressions are forward-looking statements. The forward-looking

statements set forth above involve a number of risks and uncertainties that could

cause actual results to differ materially from any such statement, including the risks

and uncertainties discussed in the company’s Safe Harbor Compliance Statement

for Forward-Looking Statements included in the company’s recent filings, including

Forms 10-K and 10-Q, with the Securities and Exchange Commission. The

forward-looking statements speak only as of the date made, and the company

undertakes no obligation to update these forward-looking statements.

# # #

Orchid is a trademark of L-3 Communications MAPPS Inc. All other products are

trademarks of their respective companies.

www.L-3com.com/MAPPS

www.L-3com.com/MPS

www.L-3com.com

40Events Calendar

March

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42Events Calendar

South China Forum and Exhibition of Smart Grid Construction and Development Equipment

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Platts 4th AnnualSmall Modular Reactors ConferenceManaging the Technical, Cost, and Regulatory Challenges to Develop a New Nuclear IndustryMay 29-30, 2013 • Mandarin Oriental Hotel • Washington, DC

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46 Technical Articles

Technical Articles




Int. Conf. Future of HWRs Paper 41

Ottawa, Ontario, Canada, Oct. 02-05, 2011


L.B. Gardner1 and K. Marcinkowska1

1Atomic Energy of Canada Limited, Chalk River, Ontario, Canada

Abstract

Atomic Energy of Canada L imi ted’s (AECL) Passive Autocatalytic Recombiner (PAR) is a passive device used for hydrogen mitigation under post-accident conditions in nuclear reactor containment. The PAR employs a proprietary AECL catalyst which promotes the exothermal reaction between hydrogen and oxygen to form water vapour. The heat of reaction combined with the PAR geometry establishes a convective flow through the recombiner, where ambient hydrogen-rich gas enters the PAR inlet and hot, humid, hydrogen-depleted gas exits the outlet.

AECL’s PAR has been extensively qualified for CANDU and light water reactors (LWRs), and has been supplied to France, Finland, Ukraine, South Korea and is currently being deployed in Canadian nuclear power plants.

1. Introduction

Atomic Energy of Canada L imi ted’s (AECL) Passive Autocatalytic Recombiner (PAR) is designed for use in post-accident conditions in which hydrogen is present in reactor containment. The recombiner converts hydrogen and oxygen into water vapour and heat by means of a catalytic reaction. The heat of reaction along with the PAR geometry creates a natural convective flow through the recombiner, eliminating the need for pumps or fans to bring fresh hydrogen to the surface of the catalyst (see Figure 1).

The AECL PAR has undergone extensive qualification testing for design basis accident (DBA) and severe accident (SA) scenarios for CANDU reactors and light water reactors (LWRs).

The qualification testing was performed in the Large-Scale Vented Combustion Test Facility (LSVCTF) and the Containment Test Facility (CTF) at Whiteshell Laboratories (WL, AECL), at Chalk River Laboratories (CRL, AECL) and international facilities (H2PAR and REKO-1 – France, THAI – Germany).

PAR catalyst is potentially susceptible to degradation/poisoning by volatile organic compounds (VOCs). Due to low

Figure 1 Principle of PAR Operation


concentrations of VOCs in nuclear reactor containment, periodic regeneration of the PAR catalyst plates may be necessary. AECL’s whole plate tester (WPT) is used to inspect catalyst plates in-service to determine if they require regeneration.

In addition to the current qualified designs, AECL is currently completing qualification of a larger design. AECL has supplied PARs to France, Finland, Ukraine, South Korea and is currently being deployed in Canadian nuclear power plants.

The intention of this paper is to discuss the qualification testing performed on the AECL PAR and the on-site, in-service testing required to assure the PAR is ready for service as well as to provide an update on the commercial accomplishments of AECL PARs. Prior to this, the characteristics, features and performance of the recombiner and the AECL PAR test facilities will be described.

2. AECL PAR characteristics, features and performance

AECL’s PAR design consists of flat rectangular catalyst plates arranged vertically in an open ended box (housing), with an attached cover. Oxygen and hydrogen react at the surface of the catalyst producing water vapour and heat. The heat generated at the catalyst surface combined with the PAR geometry creates a natural convective flow through the recombiner without external power or operator action. Warm humid air with unreacted hydrogen is exhausted through the PAR outlet.

Owing to its compact design, the PAR can be easily installed individually or in groups, and the modular design facilitates distribution of the required hydrogen removal capacity through reactor containment.

The catalysts used in PARs are proprietary AECL formulations developed for application in radioactive environments. Two catalyst formulations, Type 89-24 and Type 99-11, are available. The catalysts have high activity for hydrogen oxidation, are not deactivated by water vapour or steam, operate over a wide range of temperatures (13 - 750 °C) and are unaffected by exposure to high radiation. The catalysts are wet-proofed using a proprietary procedure. Water is repelled, but hydrogen and oxygen are able to diffuse to the active sites for the recombination reaction to occur.

PAR performance is characterized by two parameters: hydrogen removal rate (capacity) and self-start threshold.

Hydrogen removal rate (capacity)

Hydrogen removal rate (capacity) is defined as the amount

of hydrogen that one PAR unit removes per unit of time (usually expressed in kg/h or g/s with reference to temperature and pressure at a specified concentration of the limiting constituent). The AECL PAR capacity was studied as a function of temperature (286-378 K), pressure (90-400 kPa(abs)) and hydrogen concentration (0.5-6.0 vol. %). For oxygen-limited gas mixtures, the capacity is a function of oxygen concentration. PAR capacity increases with increasing pressure and limiting reactant concentration, and decreases slightly with increasing temperature.

Capacity is insensitive to the presence of diluents such as steam, CO2, or N2 as long as an above-the stoichiometric amount of oxygen required for recombination is available.

Self-start threshold

Self-start threshold is the minimum hydrogen concentration required to develop a self-sustained convective flow through the recombiner at a given (ambient) temperature. The self-start hydrogen concentration decreases with an increase in the ambient temperature. A PAR containing new (or regenerated) catalyst will self-start at 2% hydrogen by volume in a water vapour saturated atmosphere at 20ºC within 30 minutes.

PAR catalysts are susceptible to degradation, as are all noble metal catalysts. This can be understood as the result of phenomena that remove active sites from the catalyst surface -for instance, the occupation of active catalyst sites by adsorbed molecules other than O2 and H2.

Airborn volatile organic compounds (VOCs) might be present in nuclear containment air. They may originate from chemicals (paints, solvents, lubricants, glues, etc.) used during reactor maintenance outages. VOCs can also be released from painted surfaces and insulation, especially with heating during a reactor restart.

VOCs can adsorb on the surface of any noble metal catalyst taking up some of the available active sites. This will lead to a temporary deactivation/degradation of the catalyst, thereby affecting PAR self-start. The amount of adsorbed VOCs will decrease with increasing ambient temperature. Adsorbed VOCs can be removed with heat generated by the exothermic reaction between hydrogen and oxygen on the catalyst surface or heating the catalyst in air in an oven. With the application of heat, eventually all VOCs will desorb from the catalyst and the original catalyst activity and performance will be restored.

AECL’s PAR containing new catalyst plates will self-start at ≤ 2% hydrogen, ≤ 20°C, 1 bar and 100% RH [1]. However, after exposure to nuclear containment air, the active sites of the PAR


catalyst may become occupied by VOCs, temporarily affecting the PAR’s ability to self-start. The condition of the catalyst will depend on the concentration of VOCs in the containment air, duration the catalyst has been exposed in containment and the containment temperature. Self-start after exposure to VOCs might require higher than 2% hydrogen concentration and/or higher than 20°C to rapidly self-start. If the catalyst is exposed to hydrogen concentration for a longer period of time, the recombiner will self-start at a lower hydrogen concentration and/or a lower ambient temperature. For a given catalyst condition (degradation level) the hydrogen concentration required for PAR self-start will decrease exponentially with increasing temperature [2]. Once started the PAR operates at the design capacity. Therefore, the PAR capability to self-start (readiness for service) is the critical characteristic to monitor.

AECL has demonstrated that a degraded catalyst plate can be regenerated to its initial activity by self-starting (in the presence of hydrogen) or by heating in air. Furthermore, it was demonstrated that the heat generated by one new (or regenerated) catalyst plate can regenerate the adjacent catalyst plates in a PAR on exposure to 2% hydrogen. In turn, the heat from the newly regenerated plates would regenerate their adjacent plates creating a “domino effect” and ultimately regenerating all catalyst plates in the PAR [2]. Thus, periodic regeneration of one or more starter plates would ensure the uninterrupted PAR availability for service.

3. AECL PAR Testing Facilities

The Large Scale Vented Combustion Test Facility (LSVCTF, Figure 2), located in Whiteshell Laboratories in Manitoba, is a 10 m long, 4 m wide and 3 m high rectangular enclosure with an internal volume of 120 m3. The facility is designed to be versatile so that many geometrical configurations can be achieved. The facility can be subdivided into two or three compartments using partitions, which have openings to allow internal venting. The facility incorporates extensive capabilities for instrumentation, data acquisition, gas sampling and analysis. Other features of the facility include operation at temperatures exceeding 100°C for extended time intervals and remote operation to ensure safety of the personnel. Test conditions in the facility can be controlled and measured accurately. Instrumentation and facility modifications can be performed quickly due to easy access to the interior of the test chamber.

The Containment Test Facility (CTF) sphere (Figure 3) has an internal volume of 6.6 m3, is rated for pressures up to 10 MPa, and can be trace-heated. The facility has systems for the controlled addition of hydrogen, oxygen, nitrogen and air. The sphere can be steam trace heated and cooled to a limited degree. It is leak-tight and thus allows experiments at elevated pressures, low oxygen, and/or the presence of selected gases. The sphere is ideal for long-term (several days) experiments where it is desired to maintain conditions for the test duration. Test conditions in the CTF sphere can be controlled and measured accurately.

4. AECL PAR Qualification

The AECL PAR was subjected to cumulative stressors that simulated the operational conditions the recombiner is expected to be exposed to during its lifetime. Qualification also included subjecting the PAR to potential post-accident conditions. Baseline functional tests were performed to determine the PAR performance prior to applying the stressors. Subsequent

Figure 2 Large-Scale Vented Combustion Test Facility

Figure 3 Containment Test Facility


Int. Conf. Future of HWRs Paper 41 Ottawa, Ontario, Canada, Oct. 02-05, 2011

Table 1 Summary of AECL PAR Qualification Qualification Aspect Operability

Pressure 1-4 bar(abs)

Temperature • 13-108°C (capacity measurements)

• Up to 750°C (functionality)

Hydrogen concentration >0.5% by volume

Relative humidity Up to 100%

Radiation 370-480 kGy gamma; small-scale activity tests after exposure to 2000 kGy gamma

Post-accident H2 transient Yes (24 h of postulated post-LOCA H2 transient in a CANDU reactor)

Seismic acceleration 9.5 g (horizontal) and 6.3 g (vertical)

Thermal aging 40 years at 50°C

Fuel aerosols and vapours Yes (simulated PWR core fusion)

Hydrogen burns Yes (ignition tests at 7.5-8% H2 by volume)

Cable/kerosene fires Yes

Sprays

• Before hydrogen release Yes

• After hydrogen release Yes

• Water Yes

• Boric acid, borax, potassium hydroxide Yes (16 g/kgwater boric acid, 7.5 g/kgwater borax, 0.185 g/kgwater KOH)

• Tri-sodium phosphate (TSP), lithium hydroxide

Yes (120 mg/kgwater TSP, 50-100 mg/kgwater LiOH)

• Sodium hydroxide Yes (0.6 wt%)

Low oxygen concentration Yes (1-2% O2 by volume)

Post-accident chemicals (iodine, methyl iodide, hydrazine, chlorine, hydrochloric acid)

Yes (5.0 mg/m3 iodine, 5.0 mg/m3 CH3I, 100 mg/L N2H4, 40 mg/m3, Cl2, and 10 g/m3 HCl)

After long-term exposures to plant operating conditions

Yes (up to 42 months)


intermediate and final functional tests were carried out to demonstrate the PAR performance after exposure to the cumulative stressors.

Stressors applied cumulatively to the PAR included thermal and radiation aging, long-term exposure to hydrogen and seismic testing. Additional tests using the same PAR housing and catalyst plates included functional tests to determine the effect of dousing spray chemicals, the effect of high pressure on capacity, and the effect of low oxygen on self-start. The effect of

fuel aerosols on PAR capacity was tested using a reduced-size PAR unit in the H2PAR facility in France [1].

Poisoning tests were performed to examine the separate effects of post-accident chemicals on PAR catalyst samples and the full scale PAR. The chemicals include iodine, methyl iodide, hydrazine, chlorine, hydrochloric acid, formaldehyde, benzene, cable/kerosene fires, carbon dioxide and carbon monoxide. The recombination activities (recombination rates) of the exposed samples were compared to the activities of new catalyst [1].

The recombiner was evaluated under CANDU operating conditions to study the effect of VOCs present in the containment air on the catalyst by installing trial PARs in CANDU reactors.

Functional testing, including thermal aging and tests with sprays, was conducted in the LSVCTF and CTF at AECL-WL. Poisoning tests were carried out at AECL-CRL. Radiation aging, seismic qualification and tests including exposure to fuel aerosols were performed by independent laboratories.

A summary of AECL PAR qualification is given in Table 1.

5. AECL PAR In-Service Inspection

The AECL recombiner requires no special maintenance. However, periodic testing of the catalyst is required to ensure the PAR availability for service, i.e. its capability to self-start at the required station-specific conditions of temperature and hydrogen concentration. To perform on-site periodic testing, AECL has developed the whole plate tester (WPT) – see Figure 4.

The WPT is comprised of a temperature controlled enclosure (oven chamber) where a PAR catalyst plate is inserted. A mixture of 2% hydrogen (by volume) in air is admitted into the oven chamber and over the catalyst plate at a controlled flow rate. Six infrared sensors monitor the temperature increase of the catalyst plate as a function of time. “PASS” or “FAIL” is indicated relative to the station-specific requirement for PAR self-start. A “PASS” denotes the plate will meet the requirement. However, it does not give an indication of the actual degradation of the catalyst. Thus, the plate must be regenerated before re-installation. A “FAIL” indicates that the plate has degraded beyond the station-specific requirement. Therefore, the inspection schedule may need to be modified to ensure uninterrupted PAR availability for service.

AECL recommends performing the following activities during every maintenance outage:

· Visually inspect a few plates per PAR

· Test three starter plates per PAR in the WPT

　· Regenerate (or replace with regenerated/new catalyst plates) the starter plates in each PAR

If the required self-start temperature is equal to or exceeds 100°C, the VOCs are not of great concern, as it has been determined through years of research that the AECL PAR will self-start at 2% hydrogen by volume or less regardless of the catalyst degradation level.

6. AECL PAR Commercial Experience

The AECL PAR has been supplied to CANDU reactors in Canada and PWR and VVER reactors in France, Finland, Ukraine and South Korea. Two models (PAR1 and PAR2) of the AECL recombiner are currently qualified and installed in nuclear power reactors. A third (PAR3) design with a larger capacity is currently being qualified.

7. Conclusion

The AECL PAR is a device which employs a catalyst to facilitate

Figure 4 Whole Plate Tester (WPT)


the reaction between hydrogen and oxygen producing water and heat. It is a passive system which self-starts/self-feeds and does not require power or operator action. It has undergone extensive qualification testing at AECL’s hydrogen test facilities and international facilities. The PAR requires in-service testing using the WPT and periodic regeneration due to the susceptibility of noble metal catalyst to degradation by VOCs. Since 2003, AECL has supplied PARs globally.

8.References

[1] J.V. Loesel Sitar and K. Marcinkowska, “Consolidation Report on the Qualification Testing of the Proprietary AECL Hydrogen Recombiner”, CANDU Owner’s Group Report, COG-00 217, 2003 December.

[2] K. Marcinkowska, “Evaluation of AECL Passive Autocatalytic Recombiner (PAR) for Point Lepreau, Gentilly-2, Pickering A and Bruce A Generating Stations”, CANDU Owner’s Group Report, COG-08-2133, 2010 October.

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8.References


The world of nuclear power is constantly evolving, and in this regard it is hard to ignore the big new trend in the world centering on small modular reactors (SMRs). While China is certainly not yet the leader in this field, there are many notable developments regarding SMRs in China. Just like in other parts of the world, SMRs in China represent an exciting new sector for nuclear power.

History of SMR Development in China

China has been working on small reactor designs since it tested and launched its nuclear submarines in the 1970s. China has developed several small-scale reactors including Qinshan Phase I, the CNP-300, which was China’s first commercial PWR and falls into the small reactor category (i.e., less than 300 MWe in capacity). Although China has focused mostly on large-scale PWRs as its technology of choice, China also began developing SMRs for different applications back in the 1980s. China developed, built, and operated a Nuclear Heating Reactor (NHR) with a power capacity of 5 MWe, NHR-5 for district heating supply and seawater desalination. A High Temperature Gas-Cooled Reactor (HTR) with a power capacity of 10 MWe, the HTR-10, was later built in Beijing. A team led by Tsinghua University and Huaneng Group is now expanding the HTR-10 design to a modular design with a power capacity of 200 MWe. Construction works for this HTR-PM demonstration project at Shidaowan, Shangdong Province, started in December 2012.

Recently, CNNC also announced its own small modular design, called the ACP-100. This is a 100- 150 MWe PWR designed for electricity, heat, and/or desalination. A plant utilizing this design will have a flexible configuration, scalable from one to eight modules. CNNC already signed an agreement in 2011 with the Zhangzhou municipal government in Fujian Province, which is planning to host the first ACP-100 demonstration plant.

Meanwhile, China has also become a calling point for many international designers and developers of SMRs and advanced reactor designs. Companies that have been reportedly in

negotiations with the Chinese nuclear industry include Babcock & Wilcox (B&W) – designer of the mPower reactor, as well as NuScale Power, and Hyperion (now 4Gen).

Key Drivers for China’s SMR Development

Although China has worked on small reactors for several decades, until very recently the country has had no strategic plan to develop and deploy these technologies. Therefore, China’s small reactor design program has been limited to small scale R&D without major advances.

In the 1990s, China obtained pebble-bed HTR technologies from Germany through Chinese engineers sent there to study nuclear engineering. After their studies, these engineers came back and became a major working force at Tsinghua’s Institute of Nuclear Energy Technology (INET) to conduct the HTR-10 project. Since China’s policy shift to strongly promote nuclear energy in the mid-2000s, the nuclear industry gradually became more interested in SMR designs partially due to the global emphasis on SMRs, which remains strong even after Fukushima.

China’s nuclear industry now also has financial support from the government and sufficient investment from power companies to develop demonstration units for SMR technologies. In addition, China has realized that there is a huge gap with other major nuclear power countries in terms of technology innovation, and it is working hard to close this gap. In the near future, China aims to transform from a technology importer to an exporter.

Although Chinese nuclear officials have often mentioned that small reactor applications could be a solution to help remote areas without grid infrastructure and coastal areas lacking fresh water, domestic applications are unlikely to be a major driving force. Instead, technology innovation and goals to export serve as the primary drivers for SMR development in China.

Organizations Involved

Several organizations are involved in SMR work in China,


By Yun Zhou and Jonathan Hinze, The Ux Consulting Company, LLC


including academic organizations, technology companies, nuclear utilities, and other investors.

Since Chinese small reactor programs are still at the R&D stage, there have been only two major institutes involved: INET at Tsinghua University and the Nuclear Power Institute of China (NPIC) under CNNC. INET, as a pure academic institute, is China’s pioneer in working on small reactor R&D programs. Its engineers and researchers designed NHR-5, NHR-200, HTR-10, and HTR-PM for different applications. In addition, it also works on supercritical light water reactor technologies for submarines. NPIC has provided engineering design work for the ACP-100 reactor.

As the first power company that invested in small reactor concepts, China Huaneng Group formed a joint investment, Huaneng Shandong Shidaowan Nuclear Power Company (HSSNPC) along with China Nuclear Engineering Group Corporation and Tsinghua Holdings Group to construct the first HTR-PM demonstration plant in the Shandong province (China Huaneng Group has 47.5% share; CNECC has a 32.5% stake; and Tsinghua University’s INET 20%).

In addition, China Guodian Group formed a joint investment, Zhangzhou Energy Company, with CNNC to develop the first ACP-100 demonstration plant in Zhangzhou, Fujian (CNNC has 80% share; China Guodian has 20% share).

China Power Investment Corporation (CPIC), which is one of the three power companies that can own and operate nuclear power plants in China, is also interested in small reactor designs and is currently conducting research on small reactor project siting and already signed a collaborative agreement with Zhuzhou municipal government in Hunan Province.

China Guangdong Nuclear Power Corporation (CGNPC) seems to be behind on the small reactor design and development competition; however, CGNPC is making some progress in this area. China Nuclear Power Technology Research Institute (CNPRI), the R&D branch of CGNPC, formed a team which is responsible for small reactor R&D in 2012 and hosted a small reactor forum in Xi’An in September 2012. In addition, CGNPC also has held talks with NuScale from the U.S.

SNPTC, the state-owned enterprise that is in charge of AP1000 technology transfer is also aware of the competition. It has held talks with B&W in the U.S. to seek potential opportunities on small reactor technology transfer.

Current and Future Projects

Currently, the HTR-PM and ACP-100 are the two most promising designs to move forward to the demonstration stage.

After several years of development and small-scale testing of a prototype in Beijing, a demonstration 210 MWe high-temperature, gas-cooled pebble-bed reactor called the HTR-PM was approved by the Chinese government in November 2005 for construction at Shidaowan, near Rongcheng in Weihai City, Shandong Province. The Shidaowan demonstration plant is slated to pave the way for an 18-unit (3,780 MWe) power plant. However, the first step in the HTR-PM project consists of construction of two commercial-scale 210 MWe units, although it is considered a demonstration plant. Although the project obtained a construction permit in 2009, it only began construction in December 2012 due to differing views within China’s nuclear industry that questioned the safety performance of pebble-bed core designs amid China’s post-Fukushima reviews. At the end of 2012, the project finally obtained the permit to proceed and poured first concrete.

It has been estimated that construction time for the first demonstration project will be approximately 50 months after first concrete. Currently, the project has pre-ordered 90% (in costs) of its components, and many of these are in the midst of manufacturing. Large key components, such as the reactor pressure vessel (RPV), steam generators, and turbine-generator systems have been ordered. Except for the RPV and steam generators (SGs), all components can be derived from standard nuclear-grade manufacturing. It appears that Shanghai Electric Co. will produce the RPV, Harbin will be in charge of the SGs, and Fangda Carbon New Material Technology Co. will be in charge of the reactor vessel internals. Therefore, there is little concern that China will be able to produce the necessary major components for the HTR-PM. Meanwhile, the main Helium ventilator and control rod drive mechanism (CRDM) are still in R&D. Instrumentation and control (I&C) systems and electrical equipment remain weak points, where foreign suppliers may be enlisted to complete the supply chain.

HTR-PM Source: Tsinghua INET


The HTR-PM team has already completed comprehensive testing of key technologies for fuel kernel production. A fuel production line is under construction with capacity of producing 300,000 fuel elements per year at Northern Fuel Fabrication Plant in Inner Mongolia. China also has a contract with SGL Group in Germany for supply of the initial 500,000 machined graphite spheres for the HTR-PM demonstration project. However, validation of large scale fabrication of the pebble fuel with high quality has yet to be proven. This may still be a challenge for the HTR-PM team.

Besides its technical challenges, the economics of HTR-PM are still questionable compared to large-scale PWRs. Strategies are proposed to lower its cost, including simplified reactor auxiliary, I&C, and electrical systems as well as modular construction.

ACP-100

With the international trend moving forward on SMR studies, CNNC’s NPIC started focusing on developing a small integrated modular PWR with passive safety features in 2010. CNNC views ACP-100 as a multi-purpose energy resource. It can be applied for both electricity and process-heat generation as well as water desalination, and it could be easily adaptable to remote areas that have limited energy options or industrial infrastructure.

News reports claim that ACP-100’s engineering design work was to be completed by the end of 2012, when the preliminary safety assessment report was delivered. CNNC has plans to obtain the construction permit by the end of 2013.

A plant utilizing this design will have a flexible configuration, with between one and eight modules. The first demonstration project in Zhangzhou is slated to start construction at the end of 2013 with an aggressive construction schedule. It is set to provide the city with electricity, heat, and water desalination.

The design uses passive safety features already included in Generation III designs and has an underground siting option. The ACP-100 design has an output power level of 100 MWe. According to CNNC, the ACP-100 estimated construction time is 30 months and a design life of 60 years. The fuel cycle length for this PWR is expected to be 24 months.

Economics is definitely a challenge for small reactor designs due to the economies of scale rule. China has also acknowledged this issue. According to CNNC, it estimated that the first demonstration project will cost approximately RMB 25,000/kWe (~$4,000/kWe). With the multiple-module option, the cost might

be reduced to RMB 20,000/kWe (~$3,200/kWe) in the future.

Conclusions

It seems quite clear that China’s nuclear industry is quickly following the recent international trend to develop small reactor technologies. Each nuclear power company in China is developing its own strategic plan. The HTR-PM and ACP-100 will be the first batch of Chinese SMRs to be built and demonstrated. Other SMR designs might eventually be developed and deployed in the future. However, the domestic market is still uncertain for small reactors due to the large scale deployment and feasible economics of larger 1,000 MWe nuclear power plants in China. As a result, China may be targeting the international market rather than domestic applications for its small reactors in the next decades. Nonetheless, the domestic market remains important in connection with efforts aimed at demonstrating the safety and economics of these technologies. Thus, the new SMR sector in China is certainly one to watch going forward.

Ux Consulting issued a new special report on the global SMR Market Outlook in early 2013.

For more information, go to www.uxc.com or contact Jonathan Hinze at

Ux Consulting issued a new special report on the global SMR Market Outlook in early 2013. For more information, go to www.uxc.com or contact Jonathan Hinze at [email protected]

www.uxc.com

www.uxc.com



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NEWSHighlights of the Month

Company News


NPP News

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HighlightsLiaoning NPP Officially Enters into the Grid-Connect and Debug Phase

At 3:09 p.m. on February 17, Liaoning Hongyanhe NPP Unit 1 realized its first successful grid-connect, which marks that our first NPP in North-East China officially entered into the grid-connect and debug phase. It also signifies that the NPP can generate more economic and cleaner nuclear energy for Liaoning people.

Hongyanhe NPP is located in Wafangdian, Dalian Hongyanhe town, Liaoning Province. It is 110 km from Dalian City, and 270 kilometers from Shenyang City. It is not only the first nuclear power plant but also the largest energy investment project in Northeast China. It began construction in August 2007. Four one-million-kilowatt nuclear power units were built during the first-phase project, with an investment of 50 billion RMB. The second phase project started in May 2010 with two one-million-kilowatt nuclear power units being constructed at a cost of 25 billion RMB. Thus Hongyanhe NPP has become the largest nuclear project in the world with the most units in construction. The NPP will finish its construction in 2016, when annual energy output will reach 45 billion kWh.

During the construction process, Liaoning Hongyanhe Nuclear Power Co., Ltd. always adhere to the principle of "safety and quality first". The project quality and all project nodes should accept the supervision from national nuclear safety authorities, and a second phase will not continue without the previous stage receiving approval. The NPP’s construction lasted more than

5 years, and went through different phases to finally realize its grid-connection. Those phases included civil work, equipment installation, systems commissioning, nuclear fuel loading, units reaching critical phase and turbine rolling.

The first four units of Hongyanhe NPP will be finished in 2015 and enter operation then. The annual energy output will reach 30 billion kWh, which is higher than the Dalian 2012 total electricity consumption, 28.7 billion kWh, accounting for 16% of the total consumption in Liaoning province in 2012.

The grid-connection of the Hongyanhe NPP not only optimizes Liaoning’s electricity supply structure but also speeds up the process of realizing the targets of energy saving and emission reduction. It will help to improve the environment and air quality. Compared with the same scale of thermal power plant, the first four units of Hongyanhe NPP will realize an annual reduction of standard coal consumption of 10 million tons, carbon dioxide emission reduction of 24 million tons and sulfur dioxide emission reductionof 230,000 tons, which equals building 66,000 hectares.

Source：http://www.china-nea.cn/

Chinese Nuclear Industry Seeking Saying on Uranium through Multiple ChannelsIn an interview hosted by Shanghai Security News, several nuclear professionals said, the current international uranium market is a buyer’s market, so Chinese nuclear enterprises should capitalize on this opportunity of seeking to have a say on the uranium price.

A senior professional analyzed that, “the spot price for international uranium has fallen back to 71 USD/pound, although we cannot expect the price to drop as low as in the 1990s when it reached less than 10 USD/pound for natural uranium (uranouranic oxide), the price is still falling now.”

The international uranium price had kept increasing since 2003, almost reaching $140 USD in 2007, before beginning to fall.

At the Tenth International Nuclear Power Industry Exhibition, several experts mentioned that the fluctuation of the international uranium price is a signal for China to reconsider its strategy for domestic nuclear development and uranium resources.

These experts said that the long-term nuclear power development plan was approved by the State Council in 2007. The plan defines that our installed nuclear power capacity will

Hongyanhe NPP Unit 1 Source: Liaoning Daily

http://www.china-nea.cn

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reach 40 million kilowatts by 2020, with 18 million kilowatts in construction. They said to safeguard the healthy development of nuclear industry, we should abide by the principle of increasing income and decreasing expenditure, so that we can establish a stable natural uranium resource system.

Fu Manchang, secretary-general of the Chinese Nuclear Society said “Recently, our nuclear industry has developed rapidly, but compared to other countries, our nuclear development remains at a low level.”

Statistics show that the installed nuclear power capacity for the units in operation is about 9 million kW, only 1.3% of China’s total power capacity. The percentage in other countries is as high as 16%, with even higher figures in France, Japan and the US.

“Apparently, the nuclear markets in France and Japan almost reached saturation, and the demand for uranium resources is very stable now. While, the domestic demand of uranium in China is very limited, so it is a buyer’s market”, Said Yu Zusheng, a senior expert from the committee of State Nuclear Power Technology Co., Ltd. He also said that China has an opportunity to seek the saying on the international uranium price.

Currently, each million kilowatts will cost 130 to 150 tons of natural uranium (uranouranic oxide), said one expert. So if the installed nuclear power capacity can reach 40 million kilowatts by 2020, the annual domestic demand of uranium will increase to between 5200 and 6000 tons.

At the end of last year, CNNC announced that a breakthrough was made in the geological exploration of natural uranium. The largest uranium deposit was discovered in Erdos, Inner Mongolia.

CNNC said that more and more uranium resources were discovered each year, which could not only meet the demand of the domestic nuclear market but set a solid base for the mid and long-term development of Uranium.

We therefore have the opportunity to have a say on the international uranium price. And it is said that a price negotiation system among national nuclear prices is underway.

“However, as uranium is a very special resource, the price is not only determined by market supply and demand, other factors also influence it. So we must prepare our own uranium resource reserve,” said one expert.

“What we should learn from other countries is that we should explore the overseas market promptly,” said Fu Manchang.

Yu Zusheng said that the economic benefit will reach 10 million RMB per day per million kilowatts. So the earlier we put the units into operation, the earlier the benefit will be realized.

“It will result in a great loss if we do not have sufficient uranium reserve” said one expert. So we should implement different strategies to guarantee a sufficient reserve.


Haiyang NPPs Unit1 Internal Components DeliveredRecently, the ships loaded with Haiyang Unit 1 reactor internal arrived at Haiyang Nuclear dock.

The internal was loaded in Portsmouth, US, on 9th, December 2012 and arrived in Shanghai Port on 6th, and on 10th they were shipped to the Haiyang NPP site.

The internal is one of the most important key pieces of equipment for nuclear island. It consists of upper and lower internal parts. It offers a support for the reactor core and provides directions for the control rod drive package. Also, it forms a passageway for the reactor coolant.

The Haiyang unit 1 internal was made by Westinghouse’s Newington plant. The successful delivery of the component laid a solid base for the placement of the CV cover head and the installation of unit 1.


Ying-jeou Ma: Nuclear Security First Taiwan media reported that Ying-jeou Ma, the leader of Taiwan’s government, said that local government insisted on applying the highest nuclear security level for Longmen NPP (or the Fourth NPP). It could only start operation after it reached the safety level.

When Ying-jeou Ma met with Andre-Claude Lacoste, former director of the French Nuclear Safety Agency, he said that the Taiwan government will apply a more integrated and strict test on the pre-operation. The relevant department will supervise the process, and they welcome fair estimates and inspections from international institutions. This NPP will not operate without receiving approval from Taiwan’s government after ensuring it



59 News

has reached the safety level.

Ying-jeou Ma stated that his government insists on applying the highest standard of nuclear safety. If this level cannot be reached there should be no development in the nuclear industry. A full inspection on the first, second and third NPPs have been made recently after the Fukushima accident. The protection system against seism, tsunami and the whole operation process had been checked carefully.

Source: http://realtime.xmuenergy.com/

China Nuclear Power Development Summit 2013 will be Held in HangzhouChina Nuclear Power Development Summit 2013 will be held in Hangzhou on 28th May, 2013. It is launched by Zhejiang Nuclear Society, Sichuan Nuclear society and Heilongjian Nuclear Society.

Based on Zhejiang nuclear projects, the summit’s topics will cover analysis of the domestic nuclear industry, nuclear equipment manufacture and certification, nuclear safety upgrade, new NPPs and the prospective nuclear technologies. Also topics such as opportunities and challenges, the set-up of platforms for exchange, cooperation and innovation will be discussed. This summit will help to enhance technical exchanges and project cooperation. Also it will help enterprises and government to enter into overseas markets to realize a “win-win”.

The summit receives great support from Harbin Electric Corporation, Dongfang Electric Corporation, Shanghai Electric Group and China Nuclear Power City. It will be prepared by Galleon (Shanghai) Consulting Co., Ltd.


CGNPC and WANO Paris Center Held 2nd Annual CongressRecently, China Guangdong Nuclear Power Corporation (CGNPC) and the World Association of Nuclear Operators (WANO) Paris Center held the 2nd annual congress at Daya Bay base. For the past year, CGNPC established close relationships with WANO’s top leaders. Topics also covered how to strengthen further communication and cooperation in the future.

The meeting acknowledged the achievement that Daya Bay base had made in terms of the WANO index, and the

contribution that CGNPC had made as a member of WANO Paris Center. The parties exchanged their opinions on how to keep a smooth operation of CGNPC by capitalizing on the platform WANO offered. They would work together to improve the safety condition of the global NPP and CGNPC committed to deepen its cooperation with WANO in the future.

WANO Paris Center ’s director Ignacio Araluce and his colleagues attended this meeting together with members from CGNPC and WANO.

Source: http://news.bjx.com.cn/

China Will Accelerate the Construction of 30 New NPPsThe “Uranium Monitor and Sustainable Development International Conference” was held in Beijing this month. Investigations showed China will soon become the second largest emitter of carbon dioxide in the world. He Ping, Environment Department manager of UNDA (the United Nations Development Program) thought that would result in a greater pressure on China in the prospective discussion on global climate change.

It is said that nuclear power accounted for 16% of China’s total power generation, which decreased carbon dioxide emissions by 600 million tons per year, equaling 8% of the global greenhouse gas emission.

In fact, news of “China is the largest carbon dioxide emitter” was reported several times. A report written by a Netherlands environment estimate institution said that the total greenhouse gas emission in China had exceeded US by about 400 million tons in 2006. But the Chinese foreign department denied this report, and expressed that China was actively reducing global greenhouse gas emission.

For the past several years, China had made great progress in energy saving and emission reduction, and modified its energy structure, including nuclear development.

He Ping said, more and more manufacturing bases were transferred to China between 2001 and 2005, and that Chinese heavy industry developed fast, especially the industries of steel, chemical and hydraulic engineering.

He pointed out that to promote sustainable development, we should also accelerate nuclear and other clean energy development beside increasing industry restructure and a

http://realtime.xmuenergy.com


http://news.bjx.com.cn

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sustainable energy budget. Wang Zhongtang, deputy director of the Nuclear Safety Management Department, State Environmental Protection Administration agreed with He Ping.

Wang Zhongtang said that nuclear power was a clean, safe and

economic energy, which would be a necessary choice for the

prospective development of China. It would not only guarantee

an optimized energy structure but will ease the pressure China

is facing to reduce its greenhouse gas emission.

For the long-term nuclear development program, China

stipulated that by 2020, 40-million kilowatt units would be

constructed, with a power output of 260 billion to 280 billion

kWh, accounting for 4% to 6% of China’s total power generation

capacity.

Zhaiqi, deputy general-secretary of CBCSD (China Business

Council for Sustainable Development), said China attached

great importance to the green effect of nuclear power. Compared

with France and US, Chinese nuclear development was in its

early phase, but 30 new NPPs will be constructed in the next 2

decades in China.

Source: http://www.cnnc.com.cn/

ACME Project Passed the Hydraulic Testing for RPVOn 6th February 2013, ACME passed the hydraulic test for its reactor pressure vessel (RPV). To assemble the RPV, there were several processes to follow, such as electric heating rod and sealing element installation, and internal component assembly and upper head cover. The test went on smoothly and steadily.

Source: http://www.snptrd.com/

The Review Conference on the Duty-Free Import of Third Generation Equipment A review meeting on the import of third generation equipment being duty-free was held on 21st and 22nd February in Beijing. It was co-organized by the National Finance Ministry, the National Development and Reform Committee and the Ministry of Industry and Information Technology. Experts from associations, research academies and manufacturing enterprises examined the imported equipment duty-free list, which mainly applied to Sanmen NPP Phase 1, Haiyang NPP Phase 1, Taishan

NPP Phase 1 and Tianwan Units 3 & 4. They collected new information on equipment which can be produced locally and which cannot, and reached a consensus which will work as a reference for the policy making department.

Xu Yuming and Long Maoxiong, vice general secretaries of China Nuclear Energy Association attended the meeting. And Xu Yuming presented the panels opinions on the meeting.

Source: http://www.china-nea.cn/

Suzhou Thermal Academy Prepared Training Courses for “RCC-M PWR Machinery Design and Manufacturing Rules” To help people better understand RCC-M standards and promote the localization process of domestic nuclear equipment, the China Nuclear Energy Association will hold the second phase of training courses on “RCC-M PWR machinery design and manufacturing rules”. The dates of the courses will be from 23rd to 27th April 2013. They will be prepared by Suzhou Thermal Academy.


XXCIG’s Gas Cylinders Emerge in the Nuclear IndustryThe SGZ system high-pressure nitrogen tank for Hainan Changjiang Nuclear Power Project has been officially delivered in February. This tank was made by Xinxing Engergy Equipment Co., Ltd which is owned by Xinxing Cathay International Group (XXCIG for short).

Hainan Changjiang NPP is the first project in Hainan province. And the SGZ system high-pressure nitrogen tank is a system component used for this project. The tank stores vaporized liquid nitrogen and works as a buffer. The stored nitrogen will be delivered to medium-pressure nitrogen users after decompression by a medium-pressure nitrogen decompression

Company News

http://www.cnnc.com.cn

http://www.snptrd.com



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stop.

It is the first time XXCIG’s gas cylinders have entered the nuclear industry. XXCIG’s researchers delivered their qualified design mission on time, which shows XXCIG’s whole research capability was highly developed - this will be valuable experience for future nuclear projects.


Jiuli Received Manufacturing License for NPP Core EquipmentOn 18th, February, Jiuli Company announced that it has received a notification from NNSA (National Nuclear Safety Association), which acknowledged that Jiuli had the capability to manufacture qualified civil nuclear safety equipment. NNSA approved the application of extending Jiuli’s manufacture scope which refers to the manufacture of 1E nickel-base alloy heat exchange tube.

Jiuli stated the license made it the second company for nickel-base alloy heat exchange U-tube in the domestic manufacture industry. This product is the key material and main part of nuclear steam generator for nuclear island core equipment. The license will enhance Jiuli’s competiveness.

Since its establishment, Jiuli has engaged in production, sale and research on the industrial stainless steel tube/pipe, which is mainly used in the petroleum, chemical, natural gas and electricity (including nuclear) industries. For now, they focus on two products, which are seamless & stainless pipe/tube, and stainless welded pipe/tube. Besides the industries mentioned above, their customers also include the industries of shipbuilding, papermaking and other machine manufacturing.


Hongyanhe Unit 1 Finished the Excitation Parameter TestOn 13th February, the Liaoning Electrics and Science Academy finished the excitation parameter test on Hongyanhe unit 1. The test lasted for 3 days.　

Hongyanhe phase 1 was the first project approved during the 11th Five Year Plan, with all four million-kilowatt units for the project receiving approval at the same time. As the first NPP in northeast China, the unit started construction on 18th, August,

2007. It should realize grid-connection in early 2013, and will be in operation in April.

Technicians of Liaoning Electrics and the Science Academy started preliminary work immediately after entering the debugging site. They formed a very specific debugging plan with the debugging technicians. At 11:00 pm, 11th February, they finished no-load test and general step-test; at 5:30 pm, 13th February, they finished 5% of the step-test. The success of the test would lay a solid base for the smooth process of unit 1. CGNPC leaders spoke highly of the technicians who gave up their spring festival to work.


The First China-Made AP1000 Ellipsoidal HeadRecently, China National Erzhong Group completed the precision finishing on the AP1000 ellipsoidal head which was manufactured by Shanghai Electric Nuclear Power Equipment Co., Ltd. This is the first integrated manufacture of a 3rd generation AP1000 ellipsoidal head. Its successful delivery reflects a breakthrough that Erzhong Company had made in forging pieces for nuclear steam generator.　　

The ellipsoidal head is an important component of the AP1000 steam generator. Its processing technique is very complicated. However, Erzhong Company optimized the process steps and set up quality control and guarantee systems.

Source: http://www.cnnc.com.cn/

Third Generation of NPP Nuclear Pump Realized LocalizationAP1000 is the safest and most advanced nuclear technology designed by Westinghouse to reduce nuclear leakage to a minimum level. There are only two nuclear pumps for the million-kilowatt units of nuclear island. Recently, Dalian Deep Blue Pump Company (DBP) finished the design of a domestic afterheat discharge pump which has passed national verification and reached the international advanced technical level. Two more pump designs passed the national verifications, and they are a non-nuclear water-feeding pump for nuclear island and a condensate pump for conventional island.

The normal afterheat discharge pump is one of the most important pieces of equipment for the heat discharge system, which releases the heat generated by the reactor coolant system





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during an NPP’s shut-down period. AP1000 has a very high requirement of antiseismic level and technical qualification. Until now, all the nuclear pumps for the four AP1000 NPP units in construction have been imported, but DBP’s innovation will change this. Experts from the Chinese Academy of Engineering believe that the DBP nuclear pump design is qualified and can meet the requirement of NPPs.

Since DBP received its 3E pump design and manufacture license in 2005, DBP maintained its research and development of new products and materials in the petro-chemical, coal-chemical and nuclear industries. In recent years, three 2E pumps and five 3E pump samples passed the national verification. The successful research of the five 3E pumps resulted in the localization of nuclear pumps, which occupied 80% of the 3E nuclear pump market in the domestic nuclear market.


14th Reloading Outage Phase for National Nuclear Opera t ion and Management Company On 20th February, No.1 Plant of the National Nuclear Operation and Management Company disconnected the grid from the East China Grid Company for its 300,000 kilowatt unit. It finished the 14th fuel recycle on schedule and has now officially begun the 14th reloading outage phase (R14).

This is the 5th year outage for the unit, which will last for 42 days. A full-scale overhaul will be executed on the steam turbine generator. The overhaul will cover the main pump “A” bearing box, centrifuge upper charging pump “A”, safety injection pump “A” and other equipment in nuclear island. The R14 outage plan will totally cover 3210 items, including 26 technical reforms, 60 variation projects, 55 status redress reports, 80 in-service inspections, 219 routine tests and 300 pieces of corrective maintenance.


China Has the Capability to Produce Nuclear FuelOn 22nd February, the uranium enrichment centrifuge produced by CNNC (China National Nuclear Corporation) realized its industrial application, which means China has the ability to manufacture nuclear fuel and masters the uranium enrichment technology. That is significant for the country’s sustainable nuclear development.　

Uranium enrichment centrifuge technology is a key technology for nuclear fuel manufacture, and an important benchmark for a country’s nuclear technology development level. High vacuum, high revolving speed, corrosive, high Mach number and anti-repair are features of a centrifuge. Its theories and techniques cover multiple disciplines, such as mechanics, electrics, material sciences and computer applications, which result in complicated techniques for centrifuge manufacture. There are about 10 countries in the world engaging in the research of this equipment and only Urenco JV in Western Europe and Rosatom in Russia have realized its industrial production.　

Researchers at CNNC have made several breakthroughs in key technologies and realized the industrial application of the centrifuge. Several techniques have reached the international advanced level. CNNC has formed an integrated system in terms uranium enrichment research, covering centrifuge research and production, project design, construction and operation, which will meet the domestic nuclear development requirements.


No. 1 Simulator Put into Operation in SDNPCIn order to undertake the full preparatory work for simulator software installation, SAT and operators training, SDNPC (Shangdong Nuclear Power Company) held a meeting on 25th February. Yu Bing, vice general manager and CPC party chief, and Wang Youzhi, vice general manager, attended the meeting.

During the period of the simulator installation, test and training, Westinghouse introduced the relevant knowledge and requirement for site support, and in the meeting all attendees restudied the requirements and defined all missions for each department.

Mr. Yu emphasized that the operation of No.1 simulator will guarantee operators receive successful training and a license, which will be a milestone of Haiyang NPP phase 1 project.

Source: http://www.sdnpc.com/

Changjiang Nuclear Plant Emergency Plan Received ApprovalThe National Nuclear Emergency Responce Office held a panel review meeting on Hainan Changjiang Nuclear Plant Off-Site Emergency Plan. Five experts attended the meeting and approved the plan as it conforms to national nuclear emergency




http://www.sdnpc.com

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laws and regulations.

Hainan Nuclear Emergency Respond Office said they’d improve the nuclear emergency responce ability and guided relevant units to carry out emergency response activities.



China and France Might Dominate the British Nuclear MarketThe recent British nuclear development program will be valued at hundreds of millions of pounds, however, Centrica Company, the only British nuclear company, has officially stated to it will retreat from the four NPP construction projects. Now, EDF (Electricite de France) is looking for new partners. Chinese state owned company, CGNPC is engaging in the cooperation discussion with EDF, which means the prospective nuclear supply for the UK market will be controlled by French and Chinese governments.

GMB was against Centrica’s retreat. They believe that the nationalization of the British nuclear market is the only way to keep it from the domination of France and China. Centrica, as the only British nuclear enterprise, possesses the capital and professionals for the construction of the four NPPs. Furthermore, EDF promises to give Centrica 20% of the shares of the four NPPs. However, the Fukushima accident resulted in a modification of British nuclear regulations which will cause an increase of the construction cost. Because of that, Centrica decided to quit from the construction plan.

Sam Laidlaw, Chief Executive of Centrica, said “Since our initial investment in the program, the requirement of further investment keeps growing, and the construction schedule extended. Based on the considerations of a long investment period and capital turnover rate, we think it will not be an ideal program for Centrica and our shareholders.” Two of the four NPPs are located in Somerset and the other two in Suffolk.

Although Centrica gives up its 20% share in the four NPPs, it still has 20% of eight current British NPPs, which will shut down during the next two decades.


Dilemma for French Nuclear According to a report from Tianxia Caijing ("Global Finance") of China National Radio, nuclear power, aviation and railways have always been regarded as the three pillars of the Sino-French economic cooperation, but it seems that France is falling into a dilemma. On the one hand, China will remain the largest global market for nuclear power and France will not give up this opportunity. On the other hand, France fears being replaced in the future by Chinese nuclear power companies, which constantly reinforce technologies. Wei Jianguo, Secretary General of CCIEE (China Center for International Economic Exchanges) shared his comments on the subject.

Wei Jianguo is Deputy Director and current Secretary General of CCIEE and a member of the CPPCC National Committee. His research covers international trade, foreign investment and China-Africa Cooperation.

For the Sino-French cooperation in the field of nuclear power, some thought that China depended on French companies, and others believed that Chinese companies would replace their French counterparts. China or France - which has stronger voice?

According to Wei Jianguo, in terms of vehicles as well as other products, the Chinese market is admired and appreciated abroad. French nuclear technology is relatively advanced for a given time, but if France does not implement or develop in practice, these technologies will eventually become obsolete. Thus, in the future, France should further cooperate with China to seek more opportunities taking advantage of the Chinese booming nuclear market.

French nuclear magnates want to get their hands on the Chinese market, but at the same time, they are afraid. Faced with this dilemma, how will France weigh the pros and cons? In this regard, Wei Jianguo said that France would finally choose to enter this market. It is still a useful method to develop a new market with advanced technology. If France does not transfer its technologies as soon as possible, it will lose the Chinese market as they become outdated.

For the prospective international nuclear cooperation, what should Chinese enterprises pay attention to meet with the requirement proposed by French peers?

Wei Jianguo believes that China has a perfect mastery. We cannot only cooperate with France, but also with the United States and Japan, even with Russia. Chinese enterprises should fully control the market, and make better decisions. Then, we must admit that France has advanced technology, so we can cooperate with France. We hope that we transfer more technologies as soon as possible, which will benefit the Chinese companies.

Source：http://finance.huanqiu.com/



http://finance.huanqiu.com

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Chinese goods and services in Argentine exports.

Both agreements were signed in Buenos Aires by utility Nucleoeléctrica Argentina SA and China National Nuclear Corporation (CNNC) in the presence of Argentine federal planning minister Julio de Vido, Chinese ambassador Yin Hengmin and CZEC general manager Mao Xiaoming (CZEC is a subsidiary of CNNC).

Under the first agreement, Nucleoeléctrica and CNNC will cooperate on issues related to reactor pressure tubes, including engineering, fabrication, operation and maintenance. It will also cover the manufacture and storage of nuclear fuel, licensing, life extension and technological advances. This agreement is aimed at both operating and future nuclear power plant projects.

The second agreement calls for the transfer of Chinese technology to Argentina. Under the accord, Argentina could act as a technology platform, supplying third countries with nuclear technology incorporating Chinese goods and services.

In addition, the CNNC delegation presented technical and financial aspects of its CAP-1000 reactor, which is one of several designs being considered for Argentina's fourth nuclear power reactor.

The signing of the two agreements follows a July 2012 nuclear cooperation accord between Argentina and China involving studies for a fourth nuclear power plant, financed by China, and in transfer of fuel fabrication and other technology.

Argentina has two operating power reactors, one at Atucha and the other at Embalse. A second unit at Atucha is nearing completion. Work began on this in 1981 but was suspended due to lack of funds in the 1990s before resuming in 2006. All three units are pressurized heavy-water reactors (PHWRs). Embalse is a 600 MWe Candu-6, while the Atucha units are a Siemens design unique to Argentina.

Government plans call for the construction of a fourth unit and a feasibility study has already been conducted. In July 2007, Nucleoeléctrica signed an agreement with Atomic Energy of Canada Ltd (AECL) to establish contract and project terms for construction of a 740 MWe gross Enhanced Candu 6 reactor, as well as completing Atucha 2. A further 740 MWe Enhanced Candu 6 unit was proposed. However, the government has also been talking with reactor vendors from France, Russia, Japan, South Korea, China and the USA, suggesting that the choice of reactor design may not be certain. A final decision on Atucha 3 is pending completion of Atucha 2.

In September 2007, AECL s igned a memorandum of understanding with Nucleoeléctrica and CNNC to conduct a joint study for cooperation in the design, manufacture, construction

The Signing of I & C Agreement will Boost Chinese Nuclear Power LocalizationWestinghouse Electric Group will cooperate with SNPAS (State Nuclear Power Automation System Engineering Company) to supply I & C (Instrumentation and Control) systems for AP1000 NPPs.

SNPAS and Westinghouse signed the I & C agreement in Beijing, which clearly defined the basic clauses and terms, as well as duties and work scopes for both parties. It also mentioned the plan of the prospective cooperation for other projects.

According to the cooperation model they defined in the agreement, SNPAS will work as a general contractor for AP1000 projects and Westinghouse as a sub-contractor. David Howell, senior vice president of Westinghouse Nuclear Automation, said that the agreement will allow Westinghouse to capitalize on the most optimized local resources to supply the most advanced global technology for NPPs. Qiu Shaoyang, general manager of SNPAS spoke highly of the cooperation.

There are four AP1000 PWR in construction located in Sanmen and Haiyang. Sanmen Unit 1 will realize the grid-connection and start to operate next year. The other three units will generate power in 2016. China will continue to construct AP1000 units, and it will also develop a local advanced reactor. China signed the technology transfer agreement in 2007, which defined a plan for the construction of NPPs in Sanmen and Haiyang.

SNPAS is a joint venture set up by SNPTC (State Nuclear Power Technology Corporat ion) and SAIC (Shanghai Automation Instrumentation Co., Ltd). It supplies I & C systems and equipment for Sanmen NPP and Haiyang NPP. It is now engaging in the development of I & C systems for advanced large-size PWRs.

The requirement of localization for nuclear projects is increasing. And more local suppliers and contractors are involved in domestic NPP projects. Even before the construction of the NPPs, Westinghouse and other contractors had already signed cooperation agreements with local suppliers. Foreign contractors now attach more importance to keeping stable partnerships with local suppliers.

Source：http://realtime.xmuenergy.com/

China and Argentina Will Expand the Nuclear Cooperation China and Argentina have extended their cooperation in the field of nuclear energy with the recent signing of two agreements covering operations and technology, as well as the use of


65 News

and operation of Candu nuclear power reactors on future projects in Argentina, Canada and China. In addition, CNNC and Nucleoeléctrica agreed to strengthen cooperation in sharing and exchanging their Candu 6 reactor operational and maintenance experience.


CGNPC President Meets with Morgan Stanley Chairman On 21st, February, He Yu, CGNPC President, met with James Gorman, Morgan Stanley Chairman, in Shenzhen. Mr. Gorman said that CGNPC is a first-rate nuclear enterprise in China,

and as one of the leading investment banks, Morgan Stanley is willing to offer CGNPC their service. They also exchanged opinions on the economic development trend in China, the US and Europe.

Leaders from Morgan Stanley Asian, China, Asian investment department and CGNPC attended the meeting.

Source: http://www.cgnpc.com.cn/

Sino-Russian Cooperation Enhanced in Third-World NPP Construction On 25th February in Beijing, Wang Qishan (Vice-Premier of China’s State Council and Chinese Chairman of the Sino-Russian Energy Cooperation Committee) met with Arkady Dvorkovich (Vice-Prime Minister of Russia and the Russian Chairman of Sino-Russian Energy Cooperation Committee.

Wang Qishan said energy cooperation between two countries plays an important role in the bilateral partnerships. The Sino-Russian Negotiation System was established 5 years ago, and great achievements have been made. This meeting will further enhance cooperation between the two countries.

Wang Qishan said a consensus on expanding crude oil trade has been reached with Russia, which means greater progress had been achieved in energy cooperation. They will also accelerate negotiations on the Sino-Russian Tianjin refinery plant project. Both governments greatly support enterprises in negotiations for the eastern gas pipeline, which will supply 38 billion m³ of gas to China each year. The eastern line of the liquefied natural gas project and the western line of the gas supply project are also encouraged by the two governments. A broader cooperation is expected in the future, such as NPP, space reactor, floating reactor, fast reactor and constructing NPPs in third-world countries. The governments encourage their enterprises to maintain long-term cooperation in industries of electricity, coal, aluminum, energy efficiency and renewable energy.

Dvorkovich said the Russian government was very happy to witness the progress that being made in the two countries. He mentioned that the natural gas project is very important for both countries and wished the two governments will promote the cooperation process in the eastern gas pipeline and liquefied natural gas projects. The cooperation in petroleum, electricity, coal and new energy reflect strategic partnerships between the two countries.


Li Ganjie Meets with Turkish Energy and Natural Resource Ministry RepresentativesThe website of the Ministry of Environmental Protection released a news on Li Ganjie, the vice minister of China Environmental Protection Ministry, there are currently 15 nuclear units in commercial operation and 30 units in construction in China. They all keep safety records.

Recently, Mr. Li met with Mr. Arkin, deputy of Turkish Energy and Natural Resource Ministry representatives. They exchanged opinions on nuclear development and safety cooperation. Li extended a welcome to Turkish representatives.

Li said that the Fukushima accident greatly affected the global nuclear industry. However, it did not change the requirement for nuclear power. He said nuclear safety plays a very important role in nuclear development and that the Chinese government had implemented a series of policies to enhance nuclear safety.

He said that the development of a country is closely related to its energy development and China was glad to further its cooperation with Turkey to promote bilateral nuclear development.　

Arkin defined the Turkish energy development condition. He said

CGNPC President Meets with Morgan Stanley Chairman Source:www.cgnpc.com


http://www.cgnpc.com.cn


www.cgnpc.com

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that the fast development of the Turkish economy has led to a great demand for energy. Nuclear development is very important - it can solve the problems of energy supply. He hoped a further cooperation between the two countries could promote nuclear development in Turkey.

Source: http://www.dzwww.com/

Sino-Dutch Discuss Preparatory Work of Dutch Nuclear Security SummitOn 20th February, Ma Zhaoxu, ministry assistant of the China Foreign Affairs Ministry met with Mr. DeClercq, Dutch ambassador and coordinator of the Dutch Nuclear Security Summit which will be held in 2014. They exchanged their opinions on the preparatory work of the summit.

Source: http://www.smnpc.com.cn/

NPP News

Source: http://www.cnpe.cc/

Welding Starts on the Main Pipe of Haiyang NPP Unit 1 On 2nd February, three pipe sections of the Haiyang Unit 1 B loop circulate were lifted to the pre-set position in the nuclear island, creating a favorable condition for the main pipe welding.

AP1000’ main pipe consists of two heat pipes and four cooling pipes, which is one of the most important 1E nuclear equipment, combing reactor pressure vessels steam generators and reactor coolant pump (RCP). The coolant pump system is formed by two loop circuit, and each circuit includes one heat pipe section and two cooling pipe section. The coolant for the nuclear reactor is drove by four RCPs. It flows through inner coolant core and got heated. Then it goes through the PRV and discharged from the pipe. The coolant was sent to steam generator from the RCL heat pipe, and got cooled from the RCP drive, and back to pressure vessel. Thus a cycle is finished.

The construction of the main pipe is one of the most important projects on the nuclear island, and directly affects the subsequent construction. To ensure everything goes well in 2013, the main system construction team and other departments united as one and worked hard to guarantee the smooth process of the project.

Source: http://www.cnec5.com/

China to Develop More Coastal NPPs As early as in the 1980s, China began selecting sites for inland NPPs, and several sites were chosen. However, 41 units in operation are located in or near coastal areas. The Fukushima accident, as well as a report from Wangjiang local government, resulted in the opposition of local people. The three proposed new inland NPPs might fail to gain approval from the 12th Five Year Plan. Although the investigation showed that the sites for the three inland NPPs are favorable for construction and more capital would be invested in Pengze NPP project, it only represents local government’s confidence of the inland NPPs and nuclear enterprises. It does not reflect a practical significance.

There are 21 coastal units engaging in preliminary work, which together produce 22.24 million kW. 12.42 million kW of units in operation and 27.05 million kW of units are in construction, all the three add up to 61.71 million kW, which is 8 million kW less than the previous estimation of 70 million kW. Several major

Completion of Construction and Concrete Pouring of the First Volute in Fuqing NPPOn 5th February, the concreting for the volute of 3PX pump room in B district of Fuqing NPP was finished.

The construction of the volute is one of the most difficult parts of civil nuclear work. It is combined with highly intensive steer bars, the bonding process is very complex and the space for construction is severely limited. Furthermore, it requires a high degree of accuracy for the installation of the embedded parts. The concrete is made with fiber and ganister sand, which make concreting more difficult.

The construction team formed a new strategy based on previous experiences. They combined the D district and F1 district to finish the concreting. The highest concreting of Fuqing NPP reached 6.363m. One month and half were saved from the project with enhanced site supervision which guaranteed the quality of the project.

This successful concreting was closely related to the cooperation between each company involved in this project. It was finished before the Chinese Spring Festival which helps the realization of 2013 targets.

http://www.dzwww.com

http://www.smnpc.com.cn

http://www.cnpe.cc

http://www.cnec5.com

67 News

domestic nuclear enterprises are now developing coastal nuclear projects. Although most of them have not received the “road ticket” from NDRC (A "road ticket" from NDRC, the National Development and Reform Commission, means preliminary work could officially start), but investigation shows the qualified conditions have already been prepared. It will take less than two years to get the final approval for construction，which means if a “road ticket” can be received in 2014, the projects can start to be constructed by the end of 2015, and an installation can be finished before 2020 - that would help to reach the previous target of 70 million kW.

The three inland NPP projects have already finished the bidding for their main equipment. If no constructions are approved, the successful bidding will be delayed or canceled. However, NDRC might give the “road ticket” to coastal projects to replace the inland ones to meet the target of 70 million kW. The equipment for those NPPs has not yet started bidding, so new orders will be delivered to relevant enterprises in the future.


Haiyang NPP Unit 2 Finish TSP Installation On 7th February, Haiyang NPP Unit 2 finished the installation of 10 tube support plates (TSP), which were used for the “A steam generator”. TSP installation is very complex and requires high accuracy. It is one the most important parts for the steam generator.

The installation started on 15th January, and lasted for 24 days. The completion of installation embodied that a great process had been made for unit 2 “A steam generator”. And it offers a strong guarantee for the project.

JPMO supervisors witnessed the success of the installation during the spring festival.


Hongyanhe NPP Unit 2 Stars Cold-State ExperimentOn 20th February, Hongyanhe Unit 2 received its license for cold-state commissioning.

The cold-state function test is the first integrated debugging check for the system test, which will implement an examination on the installation quality of its main loop. After the Fukushima accident, NNSA (National State Safety Administration) enhanced

the safety supervision on NPP units and added a cold-state function test as a control method.


Heyuan Earthquake Has No Effect on Daya Bay NPPOn 22nd February, CGNPC announced that the earthquake in Heyuan city, Guangdong province had no effect on Daya Bay’s 6 units. It said the seismic systems of Daya Bay NPP, Lingao NPP phase 1 and phase 2 remained normal and the alarms were not triggered by the earthquake.

According to China Seismic Network, a 4.8 magnitude earthquake hit Dongyuan county at 11:34, on 22nd February 2013. The earthquake’s depth was 11 km with an epicenter 145 km from Daya Bay base.

CGNPC said the anti-seismic level for Daya Bay, Lingao NPP phase 1 and phase 2 is as high as lever-8, which guarantees the NPP safety.


Completion of Ningde NPP Unit 2 CRDM Pressure Hull Installation and WeldingOn 22nd February, the CRDM pressure hull installation and welding was completed on Ningde NPP Unit 2.

CRDM is a very important equipment to drive RCCA (Rod Cluster Control Assembly) and to control the reactor. It asks for a high quality installation, welding and construction. To guarantee the construction quality and a smooth process, technicians use their construction experience, restructure the operation pattern and optimize the allocation of human resources which lead to the successful completion of the pressure hulls installation and welding.

Source: http://www.cni23.com/

Reactor Vessel Installed at Yangjiang 2 The reactor pressure vessel (RPV) has been lowered into place at unit 2 of the Yangjiang nuclear power plant, under construction in China's Guangdong province. The reactor is set to start operating next year.

Plant constructor China Nuclear Engineering and Construction Corporation (CNECC) said that Yangjiang 2's RPV was installed





http://www.cni23.com

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on 18 February. The target is to complete the installation of all the remaining heavy equipment - including the three steam generators - at the 1080 MWe CPR-1000 unit by 15 March. The steam generators arrived at the site last month.

Yangjiang 2 is one of four reactors being built at the site by China Guangdong Nuclear Power Company (CGNPC). Construction of unit 1 started in December 2008, with work on unit 2 beginning in 2009, unit 3 in 2010 and unit 4 in late 2012. The first unit is scheduled to begin generating power later this year with the remainder following to 2017. Two further units are planned for Yangjiang but their schedules have been subject to review.

The Yangjiang plant will be operated by the Daya Bay Nuclear Power Operations and Management Company - a joint venture between CGNPC and Hong Kong's China Light and Power. The company already manages the Daya Bay, Ling Ao and Ling Ao Phase II nuclear power plants.

Source: http://www.cni23.com/

Hongyanhe NPP Unit 1 Complete Power Exchange Test On 17th February, Hongyanhe NPP unit 1 passed the power exchange test, which verified the stability of the power unit. This is a very important test after the grid-connection of Hongyanhe unit one, and is one of the most risky tests in the commissioning process.


Haiyang Unit 2 RPV Complete DVI Tube-Assembly Welding

On 25th February, Haiyang NPP unit 2 RPV (Reactor Pressure Vessel) finished DVI tubes-assembly welding. DVI was manufactured by Shanghai Electric Nuclear Power Equipment Co., Ltd.

The DVI (Direct Vessel Injection Nozzle) tube is a key component of AP1000 RPV. Once an accident occurs (such as LOCA), the core makeup tank, accumulator and RWST will immediately inject water into the reactor through the DVI tubes to cool the reactor core. It is very complicated to weld the tube-assemblies which consist of 4 inlet tubes, 2 outlet tubes and 2 DVI tubes. The tubes are easily deformed. After welding the DVI tubes, the upper and lower shells of the RPV will fit, and the welding work of 4 inlet tubes and 2 outlet tubes will start.

Supervisors from Shanghai Electric Nuclear Power Equipment Co., Ltd. will follow up the welding work and focus on anti-deformation of the tubes in the welding process.

Source: http://www.sdnpc.com/

Workers manoeuvre the giant component into place Source:CNI23

Welding on RPV DVI Tube-Assembly Source:SDNPC




69 目录

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AECL 非能动自动催化复合器

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OKBM 公司公共关系部总监 Alexander L. Berenzon 先生专访

Polimaster 公司国际部副总监 Alexander Gordeev 先生专访

SPC Doza 公司销售分销部总监 Alexey Nourlybaev 先生专访

Crouzet 公司销售工程师 Sonia Goual 女士专访



70专访

DPS: 您能不能介绍一下您的背景信息？

Alexander L. Berenzon: 我叫 Alexander Berenzon。

我是俄国联邦“Afrikantov OKBM”公司的部门总监，负责公关和展览活动。

我已经从事核电事业大约 12 年了，主要负责信息和分析工作。我曾作为

一名信息研究和分析专员在 OKBM 的科技信息部工作数年。现在我统筹公

关和展览活动部门的工作进程；参加宣传和展览活动、策划活动、联络媒

体，并与股东和大众定期交流。

DPS: 能否介绍一下 OKBM 在核电工业领域的历史背景？

Alexander L. Berenzon: “Afrikantov OKB Mechanical Engineering” (JSC “Afrikantov OKBM”) 是一家股份制企业，

创立于 1945 年，最初是为了解决苏维埃首个原子能项目。公司的第一

任领导是 Igor Afrikantov，他是一位卓越的原子能和电力工业新设备

的设计师和发明家。令我们自豪的是现在他的名字就代表着公司。Igor

Afrikantov 确实是现有公司结构的创立者，包括强大的设计部、实验型

生产设备部、研究和试验综合部。在过去的几十年里，OKBM 直接参与的

核电项目中，约建造了 500 个核反应堆和蒸汽发电机组，数百台不同的核

用设备，电力工业设备和船舰设备。他们总共的使用寿命达 10000 多堆

年，相当于世界上所有服役电站反应堆的使用寿命。尤其突出的是 OKBM

在上个世纪四五十年代研发了 25 种气体扩散机（其中有九台先后投入生

产）。苏维埃第一家浓缩铀厂商就是使用了这些机器。此外，OKBM 还参

与了生产军用核材料和核素的九个铀石墨堆和七个重水堆的项目工程。自

二十世纪五十年代，OKBM 就为俄国舰船开发并先后生产了几代核动力蒸

汽发电机组。众所周知，俄国是世界上唯一一个拥有核动力破冰舰队的国

家，而 Afrikantov OKBM 又是为核动力破冰船和运营船只开发反应堆机组

的研发者，这始于为第一艘破冰船“Lenin” (1959 年投入使用 ) 开发反

应堆。快堆是我们公司历史上的又一页光辉，也是俄罗斯核电工业的骄

傲。二十世纪六七十年代，OKBM 开发并参与建造哈萨克斯坦 BN-350 快堆

和 Beloyarsk 核电站（俄罗斯斯维尔德洛夫斯克地区）的 BN-600 快堆。

BN-600 反应堆是 OKBM 的工程师数十年前开发的，已经持续运营 30多年，

这无疑证明了 OKBM 的发展思路的正确性。

DPS: OKBM 为核电工业提供哪些服务？

Alexander L. Berenzon:目前股份公司“Afrikantov

OKBM ” 是俄罗斯国家原子能公司 Rosatom 旗下“Atomenergomash” 机

械制造部的一部分。OKBM 是俄罗斯核工业领域的一流公司，集科研、生

产和设计于一体。除了开发出国家核工业关键技术的优秀设计团队，OKBM

还有自己的研发和生产基地。这使它能够为大范围的用电领域（船舰和

核电站）建造各种反应堆机组和配套设备。OKBM 是 Beloyarsk 电站第四

个核电机组（机组正在建造中，容量是 880 百万千万）的 BN-800 快钠冷

反应堆机组和俄罗斯在建的浮动核电站“罗蒙诺索夫”号的小堆型机组

KLT-40S 的总设计师和全套供应商。而且，JSC “Afrikantov OKBM” 自

主研发并向市场提供了各种运营和拟建核电站所需的各种设备，包括水泵，

OKBM 公司公共关系部总监

Alexander L. Berenzon 采访

“罗蒙诺索夫”号浮动核电站

BN-600 反应堆大厅

邮箱：[email protected] 电话 : +7 (831) 246-98-27


71 专访

通风设备，热交换器，辅助设备和核载料设备。OKBM 的业务也涉及燃料

和能源领域，为从事化学、炼油、天然气、造船和其它工业的企业制造工

业用非标准设备。

DPS: OKBM 参与了哪些核电项目？

Alexander L. Berenzon: 依照联邦任务计划，JSC

“Afrikantov OKBM” 开发设计了新一代 1200MW 容量的 BN-1200 钠冷快

堆。这个反应堆将和同容量的 VVER 压水反应堆在技术和经济参数上展开

竞争。2020 年以后 BN-1200 反应堆将陆续开工建设。OKBM 为新一代双倍

吃水核动力破冰船设计 RITM-200 创新反应堆机组，并开发设计中小型反

应堆（6-600MW），包括浮动核电站的部分堆型，它用于无核能源的发展

中国家及偏于地区的分散供电和昂贵燃料供应。现在 OKBM 参与研发的一

个国际合作的创新反应堆设计是俄罗斯和美国的 GT-MHR 汽轮机 - 模块氦

冷反应堆项目，它是带有氦冷却剂和燃气轮机能量转化装置的高温气冷堆。

这个项目有很大的发展前景，因为它可以用工业级核电和热能生产氢气燃

料。

DPS: 贵公司的研发费用占年度预算的多少比例？你们的研发策略是什么？

Alexander L. Berenzon: 2011 年我们公司的研发费

用占公司总收益的 31.7%，约 1.22 亿美元。“Afrikantov OKBM”的长期

发展战略之一是计划 2020 年之前把这个参数提高近两倍半 - 达到 3.23 亿

美元（详情请查阅我们的年度报告）。

DPS: OKBM 是什么时候进入中国核市场的？

Alexander L. Berenzon:OKBM 和中国的合作始于近

60 年前。上个世纪 50 年代，OKBM 参与了中国研究中心重水研究反应堆的

开发。我们的中国区同事对这种堆型进行了广泛的研究。我们庞大的设计

师和技术专家团队共同参与了反应堆装配任务。这项工作的所有参与者因

为成功完成了建造反应堆任务而获得了中国政府颁发的奖项。

自上个世纪 90 年代，OKBM 就已经参与了中国实验快堆 65 MW 容量的钠冷

反应快堆的大量合作开发工作。中国专家和 Rosatom 旗下的企业密切合作

从事反应堆的建设，包括 JSC“Afrikantov OKBM”， JSC “SPbAEP”，

SSC RF IPPE, JSC “TVEL”, JSC “ZiO-Podolsk”等企业。JSC “Af-

rikantov OKBM”公司是反应堆机组的总设计者，协调各项工作，提供

设计、生产、设备供应、技术咨询和操作人员培训等服务。2011 年，有

“Afrikantov OKBM”公司的俄国专家参与的中国实验快堆在中国原子能

科学研究院启动，这是开发快堆和中国核能的重要里程碑。展中俄未来的

合作将主要集中在中国政府建造新的核电站的计划。目前两国正在商讨在

中国建设一座装有两台 BN-800 型快堆的核电站。我希望这个核电站项目

在互利共赢的基础上进行。

DPS: OKBM 在中国遇到的主要阻碍或者技术挑战是什么？

Alexander L. Berenzon: 中国实验快堆的设计开发

是建立在中国制定的技术要求的基础之上的。我必须承认，中方订立了非

常严格的基本要求，甚至比俄罗斯核工业可以接受的辐射安全、放射性排

放和事故要求还要严格。但是，俄罗斯企业（包括OKBM）在反应堆的开发、

建设和钠冷快堆的操作中的长期的积极的经验使俄罗斯专家能够满足中国

实验快堆设计中所有来自中方的要求。

DPS: 贵公司是否与中国企业有合作？您是如何看待中国企业的经营方式？

Alexander L. Berenzon: 我们的中国伙伴在世界核

电市场上非常活跃，尽管日本的福岛核电事故后，中国（和其他国家一样）

的核工业有了短暂的停歇，但是现在中国核能开发紧锣密鼓，建设新的核

电站计划也栉鳞次比，中国在世界核电市场上的地位日益巩固。现在我们

的合作，正如我上面提到的，是关于正在商讨中的在中国建造 BN-800 型

快堆的双机组电站的计划以及浮动核电站建设领域的潜在合作。

DPS: OKBM 在中国的未来发展策略是什么？

Alexander L. Berenzon: 我们在中国的发展

策略取决于中方对俄罗斯快堆在中国的进一步部署的决定。“OKBM

Afrikantov” 公司只是新核电站建设的庞大而复杂进程中的一个环节（公

司负责反应堆机组和其他设备的设计和成套供应），我们在国际核电市场

上的战略是由我们的母公司 - 俄罗斯国家原子能公司 Rosatom 和它的机

械制造部“Atomenergomash”制定的。中俄正在部署建造田湾核电站 3，

4 号机组，如果 OKBM 赢得此次竞标，我们计划向该电站供应我们公司制

造的设备，包括水泵、热交换器等。至于我们对 OKBM 和 Rosatom 公司将

来在中国的核电市场上的设想，我想继续深化两国互利互惠的合作是非常

必要的。中俄在工业发展上有巨大的合作潜力和机会，是世界核技术市场

上的重要角色。

Afrikantov OKBM 办公楼蓝图

72专访

DPS: 您可以介绍一下您的背景吗？您是什么时候加入 Polimaster 公司的？

Alexander Gordeev: 我是一名工程师，同时也负责市

场推广工作。我毕业于白俄罗斯州立大学，主修无线物理学和电子学。在

这所学校，我不仅取得了硕士学位还取得了博士学位。我还获得科罗拉多

大学的工商管理硕士学位。我是 2000 年加入 Polimaster 公司的，负责

北美、拉丁美洲、亚洲、中东等除欧洲和独联体以外的所有地区的市场

营销和技术支持工作。2004 年我们在美国弗吉尼亚州的阿林顿市成立了

Polimaster 公司。起初我负责公司管理，之后我们又在立陶宛的首都维

尔纽斯建立了Polimaster仪器UAB公司，负责欧洲市场的营销及产品制造。

在过去的三年中，我作为市场营销总监负责管理集团所有公司的市场营销

部。我们的公司主要分布在四个国家，负责本区域的生产和营销。位于美

国的公司，负责北美及拉丁美洲市场；位于白俄罗斯明斯克的公司，负责

前苏联、中东和亚洲市场；位于日本的公司，负责日本及周边市场，立陶

宛公司负责所有欧盟地区的销售、制造和技术支持。

DPS: Alexander Antonovsky 在 20 年前成立了 Polimaster 公司，他成立公司的目的是什么？是否是因为受到切尔诺贝利事故的影响？

Alexander Gordeev: 明斯克曾经是前苏联辐射测量

和 CBRN 便携式探测仪器的主要研发地。那里有测量仪、放射探测、监控

仪等设备的大型设计和制造工厂、政府科研机构等，这些设备应用于核

电、航空等多个领域，还可用来应对突发状况。因此这里聚集了许多经验

丰富的专家和工程师。切尔诺贝利核电事故发生后，市面上很难找到能

够探测高度放射量的放射量测定器。于是明斯克的工程师们肩负起高度

放射量的测定器设计工作，这些仪器不仅能够准确测量放射剂量率、环境

计量，还可以在极度恶劣的环境中运作。他们同时还为普通百姓设计了民

用放射量测定仪。1992 年苏维埃政府解体，大型科研机构关闭后很多工

程师失去了工作，因此他们开始谋划其它发展途径。1992 年，Alexander

Antonovsky 决定成立 Polimaster 公司以继续从事放射量测定仪和放射探

测设备的设计和制造。

Polimaster 公司国际部副总监

Alexander Gordeev 先生专访

DPS: 你们生产的设备类型超过 140 种，那么就辐射测量来讲，你们设计制造了哪些仪器？

Alexander Gordeev: 我们有多条生产线，每个生产线

都有多个产品模型。我们致力于为每个需要接触电离辐射或负责辐射量监

控的人提供我们的产品。我们生产的设备分为几种。第一种是个人电子剂

量计，用于计量测量、个人剂量、剂量率及事故临界点报警等。这是一种

个人安全防护型电子放射剂量计。第二种是个人放射量探测仪，该仪器

的放射测量敏感度更高，用于电离辐射的搜寻定位。这款设备能够快速探

测外围环境的电离辐射度并及时做出警示。第三种是放射性核素识别仪，

通过收集分析光谱告知用户引发警报的放射因素及放射元素的种类。我们

还有集电离辐射探测、化学生物探测、违禁物品探测于一体的综合设备。

我们生产的产品应用行业广泛，包括核电安全领域、环境保护及所有会涉

及到电离辐射测量的领域都可以用我们公司生产的产品。

DPS: 你们的年产量是多少？

Alexander Gordeev: 每年的产量数额不尽相同，平均

年产量为 2 万件，产品类型种类繁多，小到袖珍计量仪，大到大型门式辐

射检测器。

校准站

邮箱：[email protected] 电话 : +7 (831) 246-98-27


73 专访

校准站 -准直器

DPS: 现在贵公司的日本市场需求是否还在增长？

Alexander Gordeev: 目前来讲市场需求已经趋于稳

定。许多制造商进入日本市场为其提供各式设备，但是质量参差不齐。日

本工程师更倾向于购买有质量保证的专业设备，因此我们的市场销量依然

很大，但是不像事故刚发生时那样快速增长了，设备的需求方向也变的多

样化了，如对于食物和土壤污染探测设备的需求等。

DPS: 你们最早做辐射计量仪设备，现在又推出了电子腕表伽马射线计量仪，你们的产品能够推陈出新的动力是什么？是如何研发出 140 多种设备的？你们是如何能够满足不同的市场需求并保持市场竞争力的？

Alexander Gordeev: 主要有两大因素推动我们设计如

此多的设备类型。一是市场的需求。我们生产的很多产品是根据客户的要

求设计的，如能够在极度恶劣的环境下运行的计量仪设备，及铀矿、应激

反应所需的设备等。另外一个因素是我们一直致力于走在市场前沿。正如

你之前提到的腕表，我们设计这种腕表计量仪是因为当时市场上没有第二

家公司能够将计量仪设备缩小安装在腕表上了，我们是独一无二的。正是

这两个因素推动我们推陈出新，如去年我们设计研发了食物污染检测仪，

这款产品是针对福岛事故而设计的，有一定的市场需求。

DPS: 你们是什么时候进驻中国市场的？

Alexander Gordeev: 公司刚刚成立的时候与中国有过

几次合作，但是正式的合作是在 2000 年，我们与别拉斯（中国）贸易服

务有限公司建立合作关系。他们作为我们在中国的经销商开始向中国市场

校准站 -仪器检测

DPS: 1992 年你们只有 15 个员工，而现在你们在白俄罗斯、立陶宛、日本、美国均设立公司，员工人数高达 200 人。对公司的快速扩大，您有何看法？

Alexander Gordeev: 公司得以迅速壮大主要是由于市

场对我们产品的需求的增加，世界局势变动及某些历史事件推动我们公司

快速成长。苏维埃政府解体后，各国政府开始控制非法放射物走私活动，

主要针对的是前苏联的走私活动。因此国际原子能机构、美国国务院、美

国能源部等部门投资了很多项目用于设备的研发、测试，这些设备将用于

前苏联、独联体国家边境地区的辐射物品测量及违禁品探测。

Polimaster 公司的专业团队有幸参与到这些项目中，我们的设备达到国

际安全要求，并且我们的辐射探测、测量设备成为行业同类设备的标杆。

2001 年 9·11 事件使得世界开始关注恐怖分子活动和核辐射威胁。许多

国家政府开始投资科研机构进行辐射物品的探测设备研发，以期预防类似

恐怖事件的发生。

DPS: 你们在日本设立了公司并且是日本瓦红核电服务机构的代表，福岛事故后，日本有没有对你们的产品提出更高的要求，产品需求量有没有增加？

Alexander Gordeev: 是的，福岛事件对我们确实产生

了一定的影响。我们 6 个月的库存产品在一个礼拜之内售罄。日本的需求

量非常大，实际上只要是与辐射测量相关的设备他们都会购买，如辐射量

测量仪、辐射探测器、识别设备等，市面出现了供不应求的局势。那种情

形让我联想到了切尔诺贝利事故，区别在于那时候我们没有探测识别设备、

没有相关的专业知识、没有专家，也没有人组织培训来指导人们如何应对

这种事故。为了满足日本客户的需求，我们增加了生产量，并在日本东京

建立办事处和服务中心。

74专访

出售我们的产品。

DPS: 谁是你们的第一个客户，是核电站运营企业吗？

Alexander Gordeev: 这是 13 年前的事情了，已经记

不清楚了。但当时我们的主要设备都供应给了国家环保署。我们的部分产

品受到海关和边境部门的肯定，随后我们慢慢进入到中国核电市场。

DPS: 刚进入中国市场的时候有没有遇到阻碍？

Alexander Gordeev: 我们最初遇到的障碍就是沟通问

题。因为存在语言障碍，我们很难制定出进入中国市场的规划，包括客户

群定位、了解客户需求、如何进行产品推广等。但是我们有信心克服这些

困难，并且我们已经开始学习汉语了。

DPS: 现在你们在中国最大客户是核电站运营企业还是研究机构？

Alexander Gordeev: 我们在中国有几家分销商，产品

覆盖四个市场领域—环境保护、医疗、公共安全、核电。

DPS: 你们在中国有三个分销商，分别是别拉斯（中国）贸易服务有限公司、北京华恒鑫达科技发展有限公司和卡迪诺科技贸易（北京）有限公司，他们的市场方向有什么不同？你们采取了什么样的合作方式？

Alexander Gordeev: 实际上现在还有一个分销商在代

理我们的产品 - 北京日之阳有限公司。他们代理的是同样的产品，只是客

户群不同。每个分销商都有自己的客户资源，彼此之间不存在竞争关系。

如卡迪诺公司主要负责核电市场的产品供应，他们不仅销售产品还向客户

提供技术支持。未来我们会与这些分销商共同参与中国项目，当然也包括

核电项目。

DPS: 你们为什么不自己销售产品而选择代理商呢？

Alexander Gordeev: 我们的原定计划是有规划的进入

中国市场，同时这样可以降低市场风险。我们选择的合作公司都是有一定

客户资源的，这样就可以避免语言不同和文化差异造成的阻碍。我们计划

未来在中国建立一家技术服务公司。

DPS: 你们有专门应用于铀矿和核燃料市场的专业计量仪。你们是否与中核北方核燃料有限公司

（202 厂）或中核建中核燃料元件有限公司（812厂）有合作？

Alexander Gordeev: 我们目前没有与这两家单位合作。

在矿业领域，我们目前的主要客户是加拿大 Cameco 公司，我们负责向他

们提供两种产品：一是 PM1604 个人剂量计，这种产品可以在严峻的铀矿

环境中应用，另一种是 PM1610 仪器。

DPS: 你们与核电站运营商有合作吗，如大亚湾核电运营管理有限公司？

Alexander Gordeev: 我们的设备完全满足了核电站运

营商的要求，为那些与辐射源直接接触的员工起到防护作用。虽然中国运

营商有购买我们的设备，但是我们与他们没有直接合作关系，事实上我们

与中核集团、中广核集团合作，他们购买我们的产品后再分配到各个企业

单位。

DPS: 福岛事故发生后，中国市场有没有对你们的计量仪、伽马探测仪等设备提出新的规范要求？

Alexander Gordeev: 福岛事故对中国市场产生了很大

影响。很多非核电领域的人开始关注辐射防护。他们的工作和辐射无关，

只是单纯为了保护自己和家人不受辐射影响。我们认识到这是一个全新的

市场，因此我们开始设计民用辐射测量设备。

矿用计量仪 PM1604 探测器 PM1904

75 专访

我们研发设计了几个新的产品，其中一个是为 IPhone 手机设计的辐射探

测仪—Polismart，任何使用 IPhone 的用户都可以购买 Polismart，将其

连接到手机上就会显示辐射覆盖的地图，还可以与朋友共享。日本福岛事

故后，应市场需求我们设计了一款可以探测食物和土壤放射性核素的污染

探测仪。与以往探测仪的笨重、昂贵不同，这个仪器小巧轻便，适用于普

通家庭。虽然体积缩小了，但是其采用的还是大型探测仪的技术规格。

DPS: 中广核或中核集团有没有对贵公司的产品提出新的要求？

Alexander Gordeev: 我们有根据他们的要求改进计量

仪。我们在现有的产品中加入了新的技术，有些是根据中国市场需求研发

的，如可以快速显示探测读数的无线个人计量仪。

PM1406 食品污染探测器

DPS: 中国的大部分铀是从哈萨克斯坦进口。你们是否为中国海关提供相关设备以帮助其进行边境管理？

Alexander Gordeev: 是的。我们有很多产品可以应用

于边境管理。如大型门式检测器及其它海关或边境管理用探测设备等。

DPS: 中国现在正在大量建设核电站，因此再过 20 年中国将成为世界最大的核电国。Polimaster有没有拓展中国市场的战略规划？中国市场对 Polimaster 的影响是什么？

Alexander Gordeev: 近几年中国核电市场快速发展壮

大，我们对此非常关注。我们制定了几种方案以期在中国市场占有一席之

地。我们有参与中核集团、中广核集团的项目。我们按照中国客户的要求

设计产品，以期更好的为中国核电市场服务。

中国设备的本土化发展势头强劲。因此我们认为该类设备“中国制造”势

必成为必然，我们正在就这一问题做出努力和尝试。我们从多个角度采取

了多个解决方案，如在中国本土寻找合作伙伴进行本地制造，或者在中国

成立自己的公司进行市场营销，同时为中国市场提供技术服务。未来有多

种可能性，我们会采取多元化的战略计划进驻中国市场。

DPS: 对于其它同样希望走入中国市场的企业，你有什么建议吗？

Alexander Gordeev: 根据市场调整战略规划，要有针

对性。寻找有实力的本土合作伙伴，学习汉语。

76专访

DPS: 贵公司是辐射监测设备和放射生态应用设备的主要供应商之一，您能多谈谈您其他的业务吗？

Alexey Nourlybaev: 目前 Doza 是一家占有较大市场份

额的大公司，拥有员工超过 200 人。我们最近刚刚建成单独的生产厂房，

这大大地促进了 Doza公司不断发展壮大。我们主要集中于以下几块市场：

便携式辐射监测和光谱测定、辐射监测系统、医疗和实验室设备、校准装

置。Doza 公司生产的多样化丰富了公司的收益模式，因此它能在供求变

化无常的市场上保持相当的独立性。我们的业务几乎涉及到辐射监控的各

个方面，我们坚持不断探索，以向客户提供完整的解决方案为目标。

另外，Doza 发行自己的科技杂志“ANRY”，它在俄罗斯的辐射监测领域

很受欢迎。我们也安排进修课程，邀请优秀的科学家做演说。“监测和安全”

是我们成立的一家私立教育机构，它获得了所有所需的办学执照，还向学

生颁发政府承认的证书。

DPS: 您能简单介绍一下您的个人情况吗？您是什么时候加入 Doza 的？您的职位什么 ?

Alexey Nourlybaev: 我于 2003 年毕业于莫斯科工程物

理研究所（国家研究核大学）。这所大学是俄罗斯优秀的核设施人才的主

要发源地。我自己尝试了不同领域的工作 - 信息安全，视频监控系统等。

2009 年我最终加入 Doza，成为服务与支持部负责人。现在我是销售和分

销部总监，工作重心转移到为公司制定和实现战略目标上来。

DPS: 能否介绍一下 Doza 的历史背景？它是如何创立的？

Alexey Nourlybaev: SPC Doza 公司是由俄罗斯主要度

量衡研究所的几名职员创立的，这几名职员具有商业头脑，善于抓住机

遇，1991 年俄国革命之后，他们就创立了此公司。Kubeysin Nurlybaev

是我的父亲，他萌生了创办公司的最初想法，成为 Doza 公司的第一任负

责人。Doza在俄语中是“dose”的意思，它形象的说明了公司的经营方向。

Doza 公司几乎从零做起，最初供应辐射监控设备。我认为公司的成功源

于创立者艰苦卓绝的奋斗。

SPC Doza 公司销售分销部总监

Alexey Nourlybaev 采访

先进的辐射监控设备

X射线医药计量测量仪

邮箱：[email protected] 手机：+7 985 6446996

77 专访

DPS: Doza 保持产品竞争优势的策略是什么呢？

Alexey Nourlybaev: 创新特色，高品质和合理的价格

使 Doza 成为俄罗斯最具竞争力的设备制造商之一。创立者们的度量衡学

背景使 Doza 公司的产品有独一无二的测量精度，而这又恰是俄国专家非

常重视的一方面。我们的专家作为几个国内外技术委员会的成员参与标准

和需求开发。辐射监测这一块要求严格，强制遵循标准，Doza 的设备必

须通过每一项测试才可以向外供应。我认为成为一流的制造商而不仅仅是

供应商是非常重要的。但是很多公司选择从制造设备变为转售设备，这公

司本身和业务范围都是死胡同。

DPS: Doza 产品研发的策略是什么？产品研发费用占年度预算的多少？

Alexey Nourlybaev: 是 Doza 的主要部门之一。我不能

透漏精确的数字，但是我们的研发费用几乎没有上限，唯一的限制是投放

到市场上的专家的数量。Doza 有强大的研究团队，但仍然在国内外物色

人才。例如我们从欧洲核子研究委员会“挖”来高级技能科学家。Doza

也雇佣来自俄罗斯重点技术高校的学生。

DPS: Doza 是给国际原子能机构，美国军方和俄罗斯供应辐射监测设备的主要供应商之一，它是什么时候进入中国市场的？

Alexey Nourlybaev: 早在 2010 年我们已经给田湾核电

站供应设备，同时也提供诸如 UMF-2000 分光仪和便携式放射量测定器等

不同种类的实验室设备。中国在过去的几年里核技术有了惊人增长，所以

现在也是推销我们最先进的产品的好时机。便携式放射量测定市场上的装

置几近饱和，我们发现了其它产品的市场潜力：辐射监测系统。在供应和

设置大范围辐射监测系统上我们有丰富的经验，包括设计阶段，我们都可

以提出完整的解决方案。

DPS: Doza 在中国有哪些项目？

Alexey Nourlybaev: 几个月前，Doza 参加了在北京举

办的 2012 中国国际核工业展览会，展会上，我们评估了潜在客户对我们

装备的兴趣。展会山人们针对我们的装置的不同特点进行了详细的询问。

他们精通技术，看起来是真的对我们的设备感兴趣。我把这些人当作我们

在中国市场的主要“催化剂”之一。现在的主要任务就是让他们得到所有

他们想了解的关于 Doza 设备的所有信息。

谈论在中国的大项目还言之尚早，从小额订单供应上赢得客户的信任才是

DOZA 激光切割机

新型制造设备

ANRI 杂志

78专访

当务之急。然而，日本福岛核事故之后，我们有大量的便携式放射量测定

器从中国转运往日本。

DPS: Doza 在中国遇到了什么主要阻碍或技术挑战？它是如何克服的？

Alexey Nourlybaev: Doza 目前在中国还不是很有名。

我们有比 MGP 公司和堪培拉公司便宜的设备，也有更好地产品特色。由于

我们在这个市场上刚刚立足，因此我们要努力向中国客户证明我们的设备

也是世界顶级产品。

此外，尽管我们的产品完全符合国际电工委员会的标准，但是中国客户往

往有别的检测标准。找出方方面面的标准认证是很困难的，但是我们寄希

望于中国伙伴的帮助。

DPS: Doza 是否有一个中国团队服务中国的客户？这个团队有多少人？若没有，你们是如何回应中国客户的需求的？

Alexey Nourlybaev: 我们有一个合作伙伴 - 上海智丹

国际贸易有限公司，它在销售我们生产的辐射监测系统方面有积极的经验。

我们也培训上海智丹的工程师支持我们的设备，包括举行设备操作物理基

础的演讲等。他们还有俄语翻译，这在帮助我们与非英语国家客户进行有

效地沟通上起到了很大的作用。

DPS: Doza已经获得了MKS-15D “Snegir”剂量率仪的专利，您是否有什么策略在中国推广这种产品？

Alexey Nourlybaev: 我认为这种产品不需要任何特殊

的推广策略。Snegir 是 β 和 γ 射线剂量仪。它价格相当低，有便捷的

β和γ开关，所以它可以与其他这类装置相抗衡。

我真正想要推广的是我们的优势产品 - 辐射监测装置：放射性气溶胶监测

仪 UDA-1AB，碘监测仪 UDI-1B, 惰性气体监测仪 UDG-1B，H-3/C-14 检测

仪 UDGB-01，蒸汽发生器泄漏监测仪 UDGP-01 和其他监测仪。我们尽量使

我们的英文网站更加便捷，使每一种装置的基本和详细信息更加容易获得。

同时我们也在 2012 中国国际核工业展览会分发了大量宣传册。我们欢迎

任何意见和要求，我希望通过我们的努力，Doza 的辐射监测设备能在中

国市场上得到飞速发展。

先进的辐射监控设备

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79 专访

DPS: 可以介绍一下您的个人背景吗？你什么时候加入 Crouzet 公司的？您的职位是什么？

Sonia Goual: 我在大学主修的是商务管理和市场营销。2006

年，我加入 Crouzet（高诺斯）的德国分公司，时任商务开发部经理，负

责市场营销。我负责推广我们公司的安全级产品，并开拓欧洲市场。我现

在的职务是国际销售工程师，负责全球的市场推广业务。

DPS: 能否介绍一下 Crouzet 公司在核电行业的发展历程？

Sonia Goual: Crouzet 是 CST 公司（Custom Sensors &

Technologies）的品牌之一。CST 是各类传感技术 , 控制和动力等领域的

专家。CST 拥有全球超过 4400 名的员工并在 2012 年创下 6.04 亿美元的

销售额。CST 为关键系统提供高质量的产品部件，致力于满足最严苛的客

户需求。

Crouzet 公司自上世纪 80 年代就已经进入核电市场。法玛通公司（现在

更名为阿海珐）制定 Crouzet 为压水堆核电站的出口供应商，主要参与的

中国项目有大亚湾核电站和岭澳核电站。Crouzet 在核电领域的发展与中

韩两国紧密相连，与中国的紧密合作始于 1988 年，与韩国始于 90 年代。

我们的常规产品及定制产品均能有效对抗 LOCA 事故（我们的所有 K1、K2

和 K3 电气设备均符合法国 RCC-E 的规定，RCC-E 是法国压水堆核电站核

岛电气设备设计和建造规则）。我们的产品都是安全性部件，用于阀门、

制动器等产品。我们的产品用于探测行程终端、移动和位置。

DPS: 贵公司与制动器和阀门制造商有合作关系吗？

Sonia Goual: 我们与先进制造商有合作关系。例如 Velan 调

节阀门、用于 EPR 反应堆的 Rotork 制动器，还有 Bernard 控制器等。我

们的产品还可以应用于非安全级设备，如 REEL 起重机、通风设备和卷筒

型起重机等。

我们有自己的国际销售团队，因此我们可以和客户保持密切沟通。我负责

的国家有中国、印度、欧洲、美国和南韩。最初的项目设计由一个专家小

组负责，该小组均是来自 RCC-E 董事会或标准制定专家组的专业工程师，

我们负责项目的协调工作。因此每个项目都是由一个专家小组根据客户要

求专门设计的。这一机构组织形式得到了法国、中国、美国核电站的大力

支持。我们的先进技术得到了法中电力协会及法国核工业协会的认可，我

们也有幸成为它们的一员。

DPS: 您刚才提到您的教育背景是商务管理而不是工程学，这在核电行业来讲比较少见。您认为从学术背景来看您有哪些优势？

Sonia Goual: 核电行业专家云集。我也接受了核电专业知识

培训。不过我的销售市场背景在协调方面起到了很大的辅助作用。我可以

敏锐的收集产品、新标准等信息、发现机会，与我的专业团队共同开发新

的项目。

DPS: 您的办公地点在哪里？

Sonia Goual: 事实上，为了了解项目进度，我经常出国拜访

客户。同时，我们的客户及电力公共事业单位也会定期来访法国，我们在

这里有一个专业的核电工程小组。我们与位于其它国家的本公司同事定期

召开销售及技术交流会，以在设计、应用及标准制定等方面进行交流。

Crouzet 公司

销售工程师及核电部主管

Sonia Goual 女士专访

邮箱 : [email protected] 手机 : +33 (0)6 89 10 31 43

Paul Papelier, Sonia Goual 及 Michel Dorey（标准及审批部经理）


80专访

DPS: 贵公司在核电市场的研发工作队对其它行业的市场有什么影响？

Sonia Goual: 我们的核心产品是全密封开关元件。该产品最

先应用于航天设备（如反推力装置），我们按照核电标准进行了重新设计。

这表明只要严格按照 MTBF 这样的安全准则运作，不同的市场也可以产生

协同效应。因此可以说核电研发增强了我们防爆设备 (ATEX-Ex) 领域的专

业技能。

DPS: 除中法两国外，贵公司还与哪些国家有合作？

Sonia Goual: 我们在印度有分公司，出售非安全级产品，如

核电站非密闭领域的电位计。我们在韩国也有贸易，与韩国蔚珍核电站

(UL1&2) 有合作，法国阿海珐公司也参与了该项目。我们也有参与芬兰

OL3 项目。

DPS: 贵单位的自动控制部件在全球的排名如何？您的产品都应用于核电站的那些领域？

Sonia Goual: Crouzet 的微型开关在法国排名第一，全球排

名第 3。我们的产品主要应用于反应堆堆芯，及 Atex（防爆）环境下的

K1、K2、K3 等领域。

DPS: 您的产品都用到了哪些材料？

Sonia Goual: 我们的限位开关是用全密封微型开关做成的，

应用了快速作用机制原理，有高强度的防冲击、抗震、耐极温等特点。该

密封微型开关内部填充了惰性气体，这在一定程度上保护了接触开关。该

部件不仅可以应用于低电平电路，还可以用于大电流电路。我们在部件制

造过程中秉承一丝不苟的原理，严格监控制造流程，保持产品高洁净制造

环境。我们的产品甚至在极度恶劣的环境中都可以应用。Crouzet 的全密

封微型开关在航天、海事及核电领域得到了很好的应用。

DPS: 您是如何保持竞争优势的？

Sonia Goual: 我们的策略就是在质量、可靠性及专业技能方

面做到最优。我们的优势表现在我们能够为客户提供准确的技术解答及创

新方案。我们每年将总收益的 7% 作为研发费用，我们能够在创新技术的

基础上进行设计，如将接近传感器和远程电路结合起来。

DPS: 法国电力集团公司 EDF 是否每年都会对Crouzet 进行审计？

Sonia Goual: 我们是 EDF 指定的供应商，我们的产品也在 EDF

的供货单上，并且 EDF 每年都会对我们进行审计。我们的其它客户也是如

此，如 OEM 和其它电力公用事业单位等。

DPS: 你是怎么看待国际竞争的？

Sonia Goual: 上世纪 80、90 年代，我们的市场仅限于法国。

如今，我们注意到其他国家的竞争者慢慢强大起来，其中中国最引人注目。

然而，对于新兴开关企业来说，技术和标准造成的阻碍使其难以与西方企

业抗衡。企业的竞争力度主要集中于核电站 CPR1000/ERP 和 AP1000 技术

及产品的资格认证。

DPS: 你们有 AP1000 的 IEEE 认证吗？？

Sonia Goual: 我们现在的产品已经获得了 RCC-E 认证。我们

的经营模式是根据客户要求提供技术解决方案。如果有需要，我们会向

AP1000 规范靠拢，并获取 IEEE 认证。

DPS: 现在 50% 的中国核电市场用的是AP1000 技术。对此贵公司是否重新调整了战略规划？

Sonia Goual: 现在的核电市场已经从 CPR1000 转向了

AP1000。对此，我们决定研发 AP1000 技术，同时我们与美国西屋电气公

司也有联系。

Paul Papelier, 设计质量控制部 /RCC-E 标准制定委员会委员

K1 限位开关

81 专访

DPS: 你们是否取得了 HAF 604 认证？

Sonia Goual: 我们的产品不在 HAF 604 认证规定范围之内。

不过我们也一直在关注申请范围的变动情况，如果将来我们的产品被划入

申请范围，那么我们也会积极做好申请准备。

DPS: 你提到你们之前有和阿海珐合作参与中国大亚湾及岭澳项目。那么，你们是不是只是和中广核有合作，而且合作的项目仅限于台山 EPR项目呢？

Sonia Goual: 实际上，我们的产品除了用于台山核电站的通

风设备和阀门控制设备外，在其它中国核电站项目中也有应用，如福清、

方家山、红沿河、宁德、昌江、防城港、阳江、秦山、田湾核电站。

DPS: 我看到您的合作伙伴中有提到中核集团。

Sonia Goual: 是的，我们与中核集团保持了很好的联系，尤

其是在核电领域。

DPS: 你们是什么时候与中广核工程有限公司这样的核电站决策者建立关系的？是否是在大亚湾项目和岭澳项目建立的联系，最近有没有拓展新的合作伙伴？

Sonia Goual: 自 2006 年到 2007 年中国核电市场重新崛起，

我们就与中国核电企业建立了合作关系。我们不仅与中国核电公用事业单

位有直接往来，还与他们的工程公司建立了联系。

DPS: 您之前提到你们为当地阀门制造商提供部件，那么与当地供货商相比，你们的销售成绩如何？

Sonia Goual: 以中国本地制造商和国外制造商相比较来看，

我们的销售额比例是 1:1。

DPS: 进军中国市场是否遇到阻碍或技术挑战？Crouzet 公司是如何克服的？

Sonia Goual: 目前来讲最大的阻碍就是语言。由于我们所有

的文件都是用法语撰写的，所以中国人很难看懂我们的认证报告。现在我

们的中国团队已将这些文件翻译成英语和汉语。

DPS: 你们在中国是否建有工厂？

Sonia Goual: 2009 年我们在广东惠州建了一座工厂，现有员

工 250 人。这个工厂建立的目的是更好的为亚洲客户服务。最初我们是为

了追随我们的几个大客户，他们想在中国发展自己的供应链。如今我们将

法国公司的组织机制复制过来，包括质量体系 (ISO 9001) 和客户辅助中

心（CAC）。

DPS: 这个工厂是否有一定程度的自主权？

Sonia Goual: 作为 Crouzet 的附属公司，自成立以来就有很

大的自主权。我们的目标是这个工厂未来可以独立运转。

DPS: 你们在广东的这个工厂是否可以直接为中国客户服务？

Sonia Goual: 目前来讲，所有的核电产品都是在法国工厂制造。

我们尚未开通针对中国客户定制的服务体系。不过如果有机会，我们将会

把我们的核电技术转移到我们的中国工厂来满足中国客户的要求。从全球

角度来讲，我们想在各国都成立一个本土团队，便于从商业和制造两方面

并行管理本土市场。我们的团队遍布南韩、新加坡、印度等国家，且我们

的法国专家及时给与帮助。这样一种机构管理模式能够帮助我们与客户保

持密切沟通，充分了解他们的需求。

DPS: 你们是否在研究其它类型的反应堆，如高温反应堆、快堆等？

Sonia Goual: 目前我们正在接触 PWR 和 VVER 反应堆。

DPS: 日本福岛事件对外国核电企业的影响就是促使他们购买更有质量保证的专业技术。您有没有察觉这一改变，或者更关注的是部件的价格趋势？

Sonia Goual: 在核电领域，我们从未受价格变动的束缚。我

们的市场领域内，价格变动往往是比较敏感的，如自动化产品，但是质量

是关键因素。由于福岛事件，客户提出的很多问题都与质量安全相关。我

们很乐意解答这些问题，因为我们可以证明我们的产品质量是安全可靠的。

DPS: 贵公司如何保持法国乃至全球第一的位置？

Sonia Goual: Courzet 公司成立于 1921 年，在核电领域有 40

年的运作经验，是 CST 的品牌公司。CST 公司资本运转良好，是一个可以

终身合作的伙伴。

法国工厂

82 HAF 政策

第一章总则

第一条为了加强对民用核安全设备设计、制造、安

装和无损检验活动的监督管理，根据《民用核安全设

备监督管理条例》，制定本规定。

第二条从事民用核安全设备设计、制造、安装和无

损检验活动的单位，应当遵守本规定。

运离民用核设施现场进行民用核安全设备维修活动

的，应当遵守民用核安全设备制造活动的有关规定。

第三条民用核安全设备目录由国务院核安全监管部

门商国务院有关部门分批制定并发布。

第四条从事民用核安全设备设计、制造、安装和无

损检验活动的单位，应当取得民用核安全设备设计、

制造、安装和无损检验许可证，并按照许可证规定的

种类、范围和条件从事民用核安全设备设计、制造、

安装和无损检验活动。

第五条民用核设施营运单位，应当对民用核安全设

备设计、制造、安装和无损检验活动进行质量管理和

过程控制，做好监造和验收工作；对在役的民用核安

全设备进行检查、试验、检验和维修，并对民用核安

全设备的使用和运行安全承担全面责任。

第六条国务院核安全监管部门对民用核安全设备设

计、制造、安装和无损检验活动实施监督管理。

第二章许可

第七条申请领取民用核安全设备设计、制造或者安

装许可证的单位，应当按照拟从事的活动种类、设备

类别和核安全级别向国务院核安全监管部门提出申

请。

申请领取民用核安全设备无损检验许可证的单位，应

当按照无损检验方法向国务院核安全监管部门提出申

请。无损检验方法包括射线检验（RT）、超声检验

（UT）、磁粉检验（MT）、涡流检验（ET）、渗透

检验（PT）、泄漏检验（LT）、目视检验（VT）等。

第八条申请领取民用核安全设备设计、制造、安装

或者无损检验许可证的单位，应当具备下列条：

（一）具有法人资格；

（二）有与拟从事活动相关或者相近的工作业绩，并

且满 5 年以上；

（三）有与拟从事活动相适应的、经考核合格的专业

技术人员，其中从事民用核安全设备焊接和无损检验

活动的专业技术人员应当取得相应的资格证书；

（四）有与拟从事活动相适应的工作场所、设施和装

备；

（五）有健全的管理制度和完善的质量保证体系，以

及符合核安全监督管理规定的质量保证大纲。

对申请领取不同设备类别和核安全级别的民用核安全

设备设计、制造、安装或者无损检验许可证的单位的

具体技术要求，由国务院核安全监管部门规定。

申请领取民用核安全设备制造或者安装许可证的单

位，应当根据其申请的设备类别、核安全级别、活动

范围、制造和安装工艺、材料牌号、结构型式等制作

具有代表性的模拟件。

模拟件制作的具体要求由国务院核安全监管部门规

定。

同时申请领取民用核安全设备设计和制造许可证的单

位，应当在模拟件制作过程中，完成相应的鉴定试验。

民用核安全设备制造安装和无损检验监督管理规定（HAF601）

83 HAF 政策

第九条申请领取民用核安全设备设计、制造、安装

或者无损检验许可证的单位，应当提交申请书和符合

第八条规定条件的证明文件。

申请领取民用核安全设备制造或者安装许可证的单

位，还应当提交模拟件制作方案和质量计划等材料。

同时申请领取民用核安全设备设计和制造许可证的单

位，还应当提交鉴定试验大纲和必要的相关文件。

第十条国务院核安全监管部门对提交的申请文件进

行形式审查，符合条件的，应当予以受理。

第十一条国务院核安全监管部门在审查过程中，应

当组织专家进行技术评审，并征求国务院核行业主管

部门和其他有关部门的意见。技术评审方式包括文件

审查、审评对话和现场检查等。

对需要进行模拟件制作活动的，技术评审还应当包括

对模拟件制作活动方案、质量计划等材料的审查，以

及制作过程中的现场监督见证等。

国务院核安全监管部门应当自受理之日起 45 个工作

日内完成审查，对符合条件的，颁发许可证，予以公

告；对不符合条件的，书面通知申请单位并说明理由。

依据第一款、第二款规定组织进行技术评审的时间，

不计算在第三款规定的期限内。

第十二条取得民用核安全设备设计、制造、安装或

者无损检验许可证的单位，可以从事相同活动种类、

相同设备类别、相同设备品种及范围内的较低核安全

级别的相关活动，但许可证特别注明的除外。

第十三条民用核安全设备设计、制造、安装和无损

检验许可证应当包括下列主要内容：

（一）单位名称、住所和法定代表人；

（二）准予从事的活动种类和范围；

（三）有效期限；

（四）发证机关、发证日期和证书编号。

第十四条禁止无许可证或者不按照许可证规定的活

动种类和范围从事民用核安全设设计、制造、安装和

无损检验活动。

禁止委托未取得相应许可证的单位进行民用核安全设

备设计、制造、安装和无损检验活动。

禁止伪造、变造、转让许可证。

第十五条民用核安全设备设计、制造、安装和无损

检验许可证有效期限为 5 年。

第十六条民用核安全设备设计、制造、安装和无损

检验单位有下列情形之一的，应当于许可证有效期届

满 6个月前，向国务院核安全监管部门提出延续申请，

并提交延续申请书和延续申请文件：

（一）持证期间有相应的民用核安全设备设计、制造、

安装或者无损检验活动业绩，并拟在许可证有效期届

满后继续从事相关活动的；

（二）正在从事民用核安全设备设计、制造、安装或

者无损检验活动，且在许可证有效期届满时尚不能结

束的。

持证期间无民用核安全设备设计、制造、安装和无损

检验活动业绩的，应当按照本章规定的程序重新申请

领取许可证。

第十七条对民用核安全设备设计、制造、安装和无

损检验单位提出的许可证延续申请，国务院核安全监

管部门应当在许可证有效期届满前作出是否准予延续

的决定；逾期未作决定的，视为准予延续。

第十八条民用核安全设备设计、制造、安装和无损

检验单位变更单位名称、住所或者法定代表人的，应

当自变更登记之日起 20 日内，向国务院核安全监管

部门申请办理许可证变更手续，并提交变更申请、工

商注册登记文件、变更说明和相关变更证明材料。

国务院核安全监管部门应当对申请变更的情况进行核

实。情况属实的，换发许可证。变更后的许可证有效

期适用原许可证的有效期。

84 HAF 政策

第十九条民用核安全设备设计、制造、安装和无损

检验单位变更许可证规定的活动种类或者范围的，应

当向国务院核安全监管部门重新提出申请。

第三章质量管理与控制

第二十条民用核安全设备设计、制造、安装和无损

检验单位，应当提高核安全意识，建立并有效实施质

量保证体系，确保民用核安全设备的质量和可靠性，

并接受民用核设施营运单位的检查。

第二十一条民用核安全设备设计、制造、安装和无

损检验单位应当根据其质量保证大纲和民用核设施营

运单位的要求，在民用核安全设备设计、制造、安装

和无损检验活动开始前，编制项目质量保证分大纲。

项目质量保证分大纲应当适用、完整、接口关系明确，

并经民用核设施营运单位审查认可。

民用核安全设备制造和安装单位应当根据具体活动编

制相应的质量计划，并经民用核设施营运单位审查认

可。

民用核安全设备设计、制造、安装和无损检验单位应

当按照项目质量保证分大纲的要求，对所有过程进行

控制，并对发现的问题进行处理和纠正。

第二十二条民用核安全设备设计单位在设计活动开

始前，应当组织相关设计人员对民用核设施营运单位

提出的设计要求进行消化、分析，充分掌握设计输入

要求，并予以明确；确定设计接口控制措施、设计验

证方式和内容以及设计变更控制措施。

设计单位在设计的各个阶段，应当按照确定的设计验

证方式对其设计进行设计验证。设计验证人员应当具

有一定的设计经验、校核能力以及相对独立性。

设计单位在设计活动中，对设计变更应当采取与原设

计相当的控制措施。

在设计工作完成后，设计单位应当为该设计的使用单

位提供必要的设计服务。

第二十三条民用核安全设备制造、安装单位在活动

开始前，应当组织相关人员对设计提出的技术要求进

行消化、分析，编制制造、安装过程执行文件，并严

格执行。

制造、安装单位应当根据确定的特种工艺，完成必要

的工艺试验和工艺评定。

制造、安装单位应当严格执行经民用核设施营运单位

审查认可的质量计划。

制造、安装单位应当对民用核安全设备的制造、安装

质量进行检验。未经检验或者经检验不合格的，不得

交付验收。

第二十四条民用核安全设备无损检验单位应当对所

承担的具体检验项目，结合检验对象的结构型式、材

料特性等，编制无损检验规程，并严格执行。

无损检验单位应当客观、准确地出具无损检验结果报

告。

无损检验工作应当由民用核安全设备无损检验Ⅱ级或

者Ⅱ级以上无损检验人员为主操作。

无损检验结果报告应当由Ⅱ级或者Ⅱ级以上无损检验

人员编制、审核，并履行相关审批手续。

第二十五条民用核安全设备设计、制造、安装和无

损检验单位，不得将国务院核安全监管部门确定的关

键工艺环节分包给其他单位。

关键工艺清单由国务院核安全监管部门制定。

第二十六条民用核设施营运单位对民用核安全设备

的安全运行负全面责任。在民用核安全设备设计、制

造、安装和无损检验活动开始前，民用核设施营运单

位应当对民用核安全设备设计、制造、安装和无损检

验单位编制的项目质量保证分大纲进行审查认可。

在民用核安全设备设计、制造、安装和无损检验活动

中，民用核设施营运单位应当采取驻厂监造或者见证

等方式对过程进行监督，并做好验收工作。有下列情

形之一的，不得验收通过：

85 HAF 政策

（一）不能按照质量保证要求证明质量受控的；

（二）出现重大质量问题未处理完毕的。

第二十七条民用核安全设备制造、安装、无损检验

单位和民用核设施营运单位，应当聘用取得民用核安

全设备焊工、焊接操作工和无损检验人员资格证书的

人员进行民用核安全设备焊接和无损检验活动。

民用核安全设备焊工、焊接操作工和无损检验人员，

应当严格按照操作规程进行民用核安全设备焊接和无

损检验活动。

第四章报告与备案

第二十八条民用核安全设备设计单位，应当在设计

活动开始 30 日前，将下列文件报国务院核安全监管

部门备案：

（一）项目设计质量保证分大纲和程序清单；

（二）设计内容和设计进度计划；

（三）设计遵循的标准和规范目录清单，设计中使用

的计算机软件清单；

（四）设计验证活动清单。

第二十九条民用核安全设备制造、安装单位，应当

在制造、安装活动开始 30 日前，将下列文件报国务

院核安全监管部门备案：

（一）项目制造、安装质量保证分大纲和大纲程序清

单；

（二）制造、安装技术规格书；

（三）分包项目清单；

（四）制造、安装质量计划。

第三十条民用核安全设备无损检验单位，应当在无

损检验活动开始 15 日前，将下列文件报国务院核安

全监管部门备案：

（一）项目无损检验质量保证分大纲和大纲程序清单；

（二）无损检验活动内容和进度计划；

（三）无损检验遵循的标准、规范、目录清单和验收

准则。

第三十一条民用核安全设备设计单位，应当在每季

度开始 7 个工作日内，向国务院核安全监管部门提交

上一季度活动情况报告，主要内容包括：

（一）已完成的设计活动清单，以及下一季度计划开

始和拟完成的设计活动清单；

（二）设计变更清单；

（三）设计验证完成清单。

第三十二条民用核安全设备制造、安装单位，应当

在每季度开始 7 个工作日内，向国务院核安全监管部

门提交上一季度活动情况报告，主要内容包括：

（一）已完成的制造、安装活动清单，以及下一季度

计划开始和拟完成的活动清单；

（二）已完成的制造、安装质量计划清单；

（三）制造、安装活动不符合项统计表。

第三十三条民用核安全设备无损检验单位，应当在

完成无损检验 10 个工作日内，向国务院核安全监管

部门报告无损检验内容和检验结果。

第三十四条民用核安全设备设计、制造、安装和无

损检验单位，应当按照下列规定向国务院核安全监管

部门报告：

（一）开展涉及核安全的重要会议、论证等活动的，

提前 7 个工作日报告；

（二）出现重大质量问题的，在 24 小时内报告；

（三）因影响民用核安全设备质量和核安全而导致民

用核设施营运单位发出停工指令的，在 3 个工作日内

通报。

86 HAF 政策

第三十五条民用核安全设备设计、制造、安装和无

损检验单位，应当对所从事的民用核安全设备设计、

制造、安装和无损检验活动进行年度评估，并于每年

4 月 1 日前向国务院核安全监管部门提交上一年度的

评估报告。

评估报告应当包括下列内容：

（一）本单位工作场所、设施、装备和人员等变动情况；

（二）质量保证体系实施情况；

（三）重大质量问题处理情况；

（四）民用核设施营运单位提出的整改要求落实情况；

（五）国务院核安全监管部门及其派出机构提出的整

改要求落实情况。

第五章监督检查

第三十六条国务院核安全监管部门及其派出机构有

权对民用核安全设备设计、制造、安装和无损检验活

动进行监督检查。

被检查单位应当对国务院核安全监管部门及其派出机

构进行的监督检查给予配合，如实反映情况，提供必

要的资料，不得拒绝和阻碍。对于监督检查中提出的

整改要求，被检查单位应当认真落实。

第三十七条民用核安全设备监督检查的依据是：

（一）《民用核安全设备监督管理条例》以及其他核

安全监督管理规定；

（二）民用核安全设备设计、制造、安装或者无损检

验许可证的条件和范围；

（三）民用核安全设备国家标准、行业标准和经国务

院核安全监管部门认可的标准；

（四）经国务院核安全监管部门审查认可的质量保证

大纲及大纲程序。

第三十八条民用核安全设备监督检查人员应当具备

下列条件：

（一）具有大专以上文化程度或者同等学力；

（二）在民用核安全设备方面具有五年以上工程实践

或者三年以上核安全管理经验，掌握有关的专业知识，

具备良好的沟通能力，能独立做出正确的判断；

（三）熟知相关法律、行政法规和核安全监督管理规

定；

（四）作风正派，办事公正，工作认真，态度端正。

第三十九条民用核安全设备监督检查的内容包括：

（一）许可证条件遵守情况；

（二）相关人员的资格；

（三）质量保证大纲的实施情况；

（四）采用的技术标准及有关技术文件的符合性；

（五）民用核安全设备设计、制造、安装或者无损检

验活动重要过程的实施

情况；

（六）重大质量问题的调查和处理，以及整改要求的

落实情况；

（七）民用核安全设备设计、制造、安装或者无损检

验活动的验收和鉴定；

（八）营运单位的监造情况；

（九）其他必要的监督内容。

第四十条国务院核安全监管部门及其派出机构，接

到民用核安全设备设计、制造、安装和无损检验单位

依据本规定报送的文件后，应当制定相应的监督计划

并书面通知报送单位。民用核安全设备设计、制造、

安装和无损检验单位应当根据监督计划的要求，做好

接受监督检查的准备。

民用核安全设备设计、制造、安装和无损检验单位，

87 HAF 政策

应当根据相关活动的实际进度，在监督计划确定的活

动实施 10 个工作日前，书面通知国务院核安全监管

部门及其派出机构。

第四十一条民用核安全设备监督检查分为例行检查

和非例行检查。非例行检查可以不预先通知。

监督检查分为综合性检查、专项检查和检查点检查，

主要通过现场检查、文件检查、记录确认或者对话等

方式进行：

（一）综合性检查：包括质量保证检查和技术检查，

质量保证检查主要检查质量保证大纲是否得到有效实

施。技术检查主要抽查民用核安全设备的设计、制造、

安装和无损检验过程是否符合标准、规范和相关技术

文件的要求。

（二）专项检查：指当发生问题或者认为可能有问题

时，由国务院核安全监管部门及其派出机构对被检查

单位进行的专项任务检查。主要包括对某一技术方面

或者质量保证大纲某一要素的实施情况所进行的检

查，以及核实提出的整改要求落实情况。

（三）检查点检查：指对检查点进行的现场实施情况

检查。

必要时，国务院核安全监管部门及其派出机构可以进

行独立验证，验证方式包括计算复核和检验验证。

国务院核安全监管部门及其派出机构，在对民用核安

全设备设计、制造、安装和无损检验单位进行综合性

检查或者检查点检查时，应当对民用核设施营运单位

监造人员的能力和监造实施情况进行检查。

第四十二条国务院核安全监管部门及其派出机构实

施监督检查时，应当对每次检查的内容、发现的问题

以及处理情况做出记录，并由监督检查人员和被检查

单位的有关负责人签字确认。确有必要时，应当保留

客观证据。

被检查单位的有关负责人拒绝签字的，监督检查人员

应当将有关情况记录在案。

国务院核安全监管部门及其派出机构应当将每次监督

检查的情况以及相应的管理要求形成监督检查报告，

并发送被检查单位以及相关单位。

被检查单位应当针对监督检查中提出的问题，采取相

应的整改措施，并将整改报告上报国务院核安全监管

部门及其派出机构。国务院核安全监管部门及其派出

机构应当对整改报告进行审查，并在后续的监督检查

中对被整改要求的落实情况进行跟踪验证。

第四十三条民用核安全设备监督检查人员在进行监

督检查时，有权采取下列措施：

（一）向被检查单位的法定代表人和其他有关人员调

查、了解情况；

（二）进入被检查单位进行现场调查或者核查；

（三）查阅、复制相关文件、记录以及其他有关资料；

（四）要求被检查单位提交有关情况说明或者后续处

理报告。

民用核安全设备监督检查人员在监督检查时，对于违

反核安全监督管理规定、许可证条件和范围以及民用

核安全设备标准而导致核安全隐患或者出现质量问题

的行为，应当立即予以制止，并立即上报国务院核安

全监管部门及其派出机构。

国务院核安全监管部门及其派出机构对有证据表明可

能存在重大质量问题的民用核安全设备或者其主要部

件，有权予以暂时封存。民用核安全设备或者其主要

部件被暂时封存的，应当完成后续处理，并由国务院

核安全监管部门及其派出机构验证符合要求后，方可

启封。

在进行监督检查时，民用核安全设备监督检查人员不

得少于两人，并出示证件。监督检查人员应当为被检

查单位保守技术秘密和业务秘密；不得滥用职权侵犯

企业的合法权益，或者利用职务上的便利索取、收受

财物；不得从事或者参与民用核安全设备经营活动。

第四十四条国务院核安全监管部门及其派出机构对

88 HAF 政策

民用核安全设备设计、制造、安装和无损检验活动实

施的监督检查不减轻也不转移被检查单位对所从事的

相关活动应当承担的责任。

第六章法律责任

第四十五条民用核安全设备设计、制造、安装和无

损检验单位有下列行为之一的，由国务院核安全监管

部门限期改正；逾期不改正的，处 1 万元以上 3 万

元以下的罚款：

（一）在民用核安全设备无损检验活动开始前，未按

规定将有关文件报国务院核安全监管部门备案的；

（二）未按规定向国务院核安全监管部门报告上一季

度民用核安全设备设计、制造、安装或者无损检验情

况的；

（三）在民用核安全设备无损检验活动完成后，未向

国务院核安全监管部门报告无损检验内容和检验结果

的；

（四）开展涉及核安全的重要会议、论证等活动，出

现重大质量问题，或者因影响民用核安全设备质量和

核安全而导致民用核设施营运单位发出停工指令，未

向国务院核安全监管部门报告的。

第四十六条民用核安全设备设计、制造、安装和无

损检验单位以及民用核设施营运单位，有其他违反本

规定行为的，依据《民用核安全设备监督管理条例》

及其他相关法律法规进行处罚。

第七章附则

第四十七条申请领取民用核安全设备制造或者安装

许可证的单位，拟自行对其制造或者安装的民用核安

全设备进行无损检验活动的，不需要单独申请领取无

损检验许可证。

第四十八条本规定中有关术语的含义如下：

（一）模拟件：指国务院核安全监管部门在审查民用

核安全设备制造、安装许可证申请时，要求有关申请

单位针对申请的目标产品，按照 1：1 或者适当比例

制作的与目标产品在材料、结构型式、性能特点等方

面相同或者相近的制品。该制品必须经历与目标产品

或者样机一致的制作工序以及检验、鉴定试验过程等。

（二）鉴定试验：指在设计过程中，为了保证设计满

足预先设定的设计性能指标而对模拟件（或者样机）

实施的实物验证试验。鉴定试验包括功能试验、抗震

试验和环境试验（包括老化试验和设计基准事故工况

试验）等。

（三）检查点：指国务院核安全监管部门及其派出机

构，根据民用核安全设备设计、制造、安装和无损检

验单位报送文件，所选择的需检查的某一工作过程或

者工作节点。根据检查方式的不同，检查点一般分记

录确认点（ R 点）、现场见证点（W 点）、停工待

检点（H 点）等三类。

第四十九条本规定自 2008 年 1 月 1 日起施行。

1992 年 3 月 4 日国家核安全局、机械电子工业部、

能源部发布的《民用核承压设备安全监督管理规定

（HAF601）》同时废止。

附件一：民用核安全设备许可证申请书、申请活动范

围表和申请文件的格式

及内容（一式二份，同时提交电子版文件）

附件二：民用核安全设备许可证格式与内容

附件三：民用核安全设备许可证延续申请书、申请活

动范围表和申请文件的格式及内容（一式二份，同时

提交电子版文件）

庆祝 L-3 MAPPS电力系统及仿真技术领导力

40 周年

2013 年 2 月 12 日，L-3 公司在蒙特利尔市宣布庆祝公司电

力系统及仿真商业成立 40 周年。为迎接这划时代的事件，L-3 为

员工和客户发行了以“L-3 公司 40 年在电力系统及仿真市场非凡

领导力”为标题的，112 页的限量版书籍。书中记录了 40 年来公

司的改革创新之路及与客户稳定良好的关系，它们造就了公司市

场领导者的头衔。

“从 1973 年在加拿大创业开始到如今的领导地位，L-3 公司

在电力系统及仿真方面的成功已经得到客户和最终用户的认可。

现在，客户期待 L-3 可以突破技术界限，研发更先进的技术来满

足客户要求。”L-3 MAPPS 电力系统及仿真市场销售副总裁，

Michael Chatlani 说：“我们今天的成功要归功于我们的员工。

正是因为他们的辛勤工作、努力创新，才使得我们研发的高保真

仿真机大大提升全球核电站的安全性能。”

L-3 MAPPS 凭借多年被世界认可的，具有稳健性、简易操作

和互用性优势的先进仿真技术形成了一套属于自己的软件工具—

Orchid® 软件工具。此外，在过去的 40 年里，L-3 MAPPS 还为客

户提供先进的全范围仿真机，课堂模拟机，任务培训机，工程设

计模拟机，数字系统控制安装，先进模型升级技术和 rehosts 等

多种设备满足客户的需求。它为工厂创建各种样式的仿真机，这

些仿真机在北美，欧洲和中国等世界范围国家和地区安装使用。

L-3 MAPPS 是 L-3 海洋和电力系统（L-3M&PS）的一个分支，

它在船舶自动化领域有 30 余年的先进技术经验和 40 余年向全球

范围领先公共事业单位提供高保真度电力仿真机的经验。另外，

公司在为加拿大重水堆铀公司提供工厂计算机系统方面有 40 多年

的专业知识。同时，L-3MAPPS 向太空领域提供目标控制和仿真机

解决方案。想了解更多关于 L-3 MAPPS 的信息，请访问公司网站：


L-3 M&PS 由 25 家运营公司组成。它在为美国海军，联合国

海军和全球商业客户提供船舶自动化和控制、航海、通信、动力

定位、电力供应和调节方面堪称世界领导者。同时，L-3 M&PS 生

产的高保真度仿真机，用于增强操作员的熟练操作程度，提高全

球船舶操作者和主要公共事业单位的安全操作和运行。在超过 19

个国家的 85 个地方，L-3 M&PS 在高科技、优质服务和综合协调

方面都有能力和可靠的工业业绩成为最有粘着力的全球性合作伙

伴。想了解更多关于 L-3 M&PS 的信息，请访问公司网站：www.

L-3com.com/MPS

L-3 总部设在美国纽约市，在全球拥有近 51000 个员工 , 它

是 C3ISR 系统（指挥、控制、通信、智能、监视和侦察）、航空

现代化及维修、国家安全保护措施的主要承包商。L-3 还提供一

系列的电力控制系统，用于军队和商业平台。2012 年的本公司的

销售额达 131 亿美元。想了解更多 L-3 信息，请访问公司网站：

www.L-3com.com

1995 年美国私人证券诉讼改革法案的安全港声明

除了此处包含的历史信息外，本新闻稿中列出的事项均属于前瞻性陈述。该

声明是预测性的，包括诸如“期望”、“预期”、“打算”、“计划”、“相信”、

“估计”、“意志”、 “可以”及类似表达均属前瞻性陈述。上述前瞻性陈述涉及

一些风险和不确定性，可能导致结果与实际性报告有一定的分歧和不同，其中公司

的安全港合规性声明的前瞻性陈述中的风险和不确定性包含在公司最新的文件中，

包括最近与美国证券交易委员会（SEC）提交的 10-K 和 10-Q。前瞻性陈述仅在做出

之日起取得，本公司无义务更新这些前瞻性陈述。

# # #

Orchid 是 L-3 Communications MAPPS 公司的商标。其它产品的商标不属该

公司所有。


www.L-3com.com/MPS

www.L-3com.com/MPS

www.L-3com.com

90 会议展会

北京天津西安

贵州

上海

广东深圳

3 月2013 第十五届中国国际工控自动化及仪器仪表（济南）展览会

时间：2013/03/15-2013/03/17

地址：济南国际会展中心

联系人：青岛金诺国际会展公司

联系方式：0532-80771360

网址：http://www.jn-smtm.com/

2013 年第十六届西安装备制造业博览会

时间：2013/03/14-2013/03/17

地址：西安曲江国际会展中心

联系人：张璐

联系方式：029-88153918

网址: www.cn-hpf.com

2013 第十四届深圳国际机械自动化展览会

时间：2013/03/28/-2013/03/31

地址：深圳会展中心

联系人：徐先生

联系方式：0755-83458749

网址：http://www.simmexpo.com/portal.php

2013 第三届云南国际装备制造业博览会

时间：2013/03/28-2013/03/30

地址：昆明国际会展中心

会议展会

联系人：徐姣

联系方式：18213980454

网址：www.ynzbh.com

2013 第十四届东北（长春）国际工程机械、建筑机械、矿山机械及工程车辆展览会

时间：2013/03/21/2013/03/24

地址：长春国际会展中心

联系人：王雪

联系方式：0431-86766871

网址：http://www.wdexpo.com.cn/news.asp?pageclass=10101&id=258

2013 年厦门电力设备暨智能电网建设展会

时间：2013/03/21-2013/03/23

地址：厦门国际会展中心

联系人：江虹

联系方式：0592-5078295

河南

济南

长春

云南厦门

北京天津

西安上海

深圳

长春

河南

济南

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http://www.simmexpo.com/portal.php

www.ynzbh.com

http://www.wdexpo.com.cn/news.asp?pageclass=10101&id=258

91 会议展会

网址：http://www.pesgexpo.com/index.html

2013 第十三届中国金属冶金展

时间：2013/03/28-2013/03/30

地址：重庆国际博览中心

联系人：陈游江

联系方式：023-67745022

网址：http://www.cmpi.cn/page.asp?moduleid=7

2013 第十三届中国锻造锻件钣金及金属成形展览会

时间：2013/03/28-2013/03/30

地址：重庆国际博览中心

联系人：祝航

联系方式：13883620171

网址：http://www.cmpi.cn/page.asp?moduleid

2013 第 15 届中国郑州焊接与切割展览会

时间：2013/03/28-2013/03/31

地址：郑州国际会展中心

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这是在美国召开的关于小型模块化反应堆的高层会议。会议聚集了来自美国和其他国家的龙头企业和专家，他们在研发小

型模块化反应堆方面有显著成就。

3个案例分析及发展更新现状：

• 美国巴布科克 & 维尔克斯公司

• 美国西屋公司

• 美国 NuScale Power 公司

发言人名单：

• 美国阿莫林密苏里公司，总裁兼首席执行官， Warner Baxter

• 美国密苏里电气合作协会，首席执行官，Barry Hart

• 美国巴布科克 &维尔克斯公司，总裁，Christofer Mowry

• 美国巴布科克 &维尔克斯公司，副总裁兼项目总监，J. Darren Gale

• 美国巴布科克 &维尔克斯公司，技术开发部副总裁，Jeff Halfinger

• 鲍易斯州立大学，经济发展部主席，Geoffrey Black

• 加拿大核安全委员会，高级项目主管，Marcel deVos

• 国际战略研究中心，防扩散项目部主任，Sharon Squassoni

• EXCEL服务公司，总裁兼首席执行官，Donald Hoffman

• FirstEnergy 核运行公司，法律事务部主任，Greg Halnon

• 燃料循环周刊出版社，发行人，Andrea Jennetta

• 国际原子能机构，水反应堆技术开发部，Mark J. Harper

• 美国 NuScale Power 公司，首席商业运行官，Mike McGough

• ( 美国 )橡树岭国家实验室，著名研发人员，Randy Beatty

• 顺德伦国际律师事务所，合作伙伴，Mark Herlach

• 美国田纳西河流域管理局，小型模块反应堆技术高级经理，Daniel Stout

• 美国核管理委员会，小型反应堆审批二部，部长，Anna Bradford

• 美国能源部，副助理部长，Edward McGinnis

• 美国能源部，副助理部长，John Kelly

• 美国能源部，先进反应堆实验室，Craig Welling

• Ux 咨询服务公司，国际高级副总裁，Jonathan Hinze

• 西屋电气公司，首席技术官，Kate Jackson

想了解更多确切信息，请登陆网站：www.platts.com/smallmodularreactors

普氏能源第四届年度会议小型模块化反应堆研讨会：控制成本、应对技术和监管挑战—发展新核能行业

时间：2013 年 5 月 29 日 -30 日地址：华盛顿特区文华东方酒店

94 科技文章

科技文章


中国小型模块化反应堆——一个令人激动的新领域

95 科技文章

在论述上述试验之前，将先行叙述此 AECL PAR 以及 AECL PAR 试验设施

的特征和性能。

2、AECL PAR 特征和性能

AECL PAR 的设计是扁平的矩形催化剂板沿竖直方向置于开口的盒子（外

壳）中，并附有连接的盖子。氧气和氢气在催化剂表面发生反应，产生水蒸

气和热量。无需外部动力和操作员动作，产生于催化剂表面的热量以及 PAR

的几何形状将促使复合器内发生自然对流现象。带有未反应氢气的潮湿热空

气通过 PAR 出口全部排出。

PAR 的紧凑设计使其无论是单独安装还是成组安装均简单易行，模块化

的设计也便于在反应堆安全壳内对所需的氢气移除能力进行分配。

PAR 内的催化剂采用 AECL 为放射性环境中的应用而开发的专利配方。

有 89-24 和 99-11 型两种催化剂配方可用。该催化剂对于氢气氧化具有很高

的活性，不会因水蒸气或蒸汽的作用而失效，可在很大的温度范围内（13 -

750 ° C）起效，并且不会受到高辐射的影响。该催化剂经过专利工序处理

而具有防潮性能。该催化剂同样防水，但氢气和氧气能够扩散到活性部位，


L.B. Gardner1和 K. Marcinkowska1

1加拿大安大略省乔克河加拿大原子能有限公司

摘要

加拿大原子能有限公司（AECL）的非能动自动催化复合器（PAR）是一

种非能动装置，用于事故发生后减少核反应堆安全壳内的氢气。该复合器采

用 AECL 专利催化剂，该催化剂能够促进氢气和氧气发生放热反应以产生水

蒸气。由于反应产生的热量以及复合器的几何形状，复合器中发生对流现象：

周围的富氢气体进入复合器入口，热而潮湿的贫氢气体从出口流出。

加拿大原子能有限公司的非能动自动催化复合器已通过了大量针对加拿

大重水铀反应堆（CANDU）和轻水反应堆（LWR）的资格试验，迄今为止已出

口法国、芬兰、乌克兰和韩国，目前正在加拿大的多间核电厂得到有效利用。

1、前言

加拿大原子能有限公司（AECL）的非能动自动催化复合器（PAR）设计

用于事故发生后反应堆安全壳内出现氢气的情况。该复合器通过催化反应将

氢气和氧气转化为水蒸气并释放出热量。由于反应产生的热量以及复合器的

几何形状，复合器内发生自然对流现象，因而无需用泵或风扇将新生的氢气

抽送或吹送至催化剂表面（见表 1）。

AECL PAR 经过了大量针对加拿大重水铀反应堆（CANDU）和轻水反应堆

（LWR）的设计基准事故（DBA）和严重事故（SA）情景的资格试验。该类资

格试验是在白贝实验室（AECL-WL）的大规模泄放燃烧试验设施（LSVCTF）

和安全壳试验设施（CTF）上、乔克河实验室（AECL-CRL）中以及国际性试

验设施（法国的 H2PAR 和 REKO-1，德国的 THAI）上进行的。

受挥发性有机化合物（VOC）的作用，PAR 催化剂可能容易发生退化或

中毒现象。由于核反应堆安全壳内存在低浓度的挥发性有机化合物，因此周

期性的 PAR 催化器再生可能必不可少。AECL 的整板测试仪（WPT）用于在使

用过程中检查催化剂板，以确定其是否需要再生。

除了已有的合格设计，AECL目前正在进行针对更大规模设计的资格试验。

迄今为止，AECL 已向法国、芬兰、乌克兰和韩国供应 PAR，而且此 PAR 目前

正在加拿大的多间核电厂得到有效利用。

本文旨在论述AECL PAR的资格试验，以及目的在于确保此PAR随时可用、

同时对此 PAR 的商业成就进行更新的在使用期间进行的现场试验。

图 1 PAR 运行原理

96 科技文章

令复合反应发生。

PAR的性能通过两个参数来表示：氢气移除速率（能力）和自启动临界值。

2.1、氢气移除速率（能力）

氢气移除速率（能力）定义为一个 PAR 单元在单位时间内移除的氢气量

（通常用 kg/h 或 g/s 表示，并与规定的限制成分浓度下的温度和压力有关）。

AECL PAR 的能力是作为温度（286-378K）、压力（90-400kPa（abs））和氢

气浓度（0.5-6.0 体积百分比）的函数进行研究的。对氧气含量有限的气体

混合物来说，该能力是氧气浓度的函数。PAR 的能力随着压力和限制反应物

浓度的增加而提高，随着温度的升高而略有降低。

在提供复合反应所需的高于化学计算量的氧气量的情况下，该能力对稀

释剂（例如蒸汽、CO2 或 N2）并不敏感。

2.2、自启动临界值

自启动临界值是指在给定（环境）温度下复合器内产生自持式对流所需

的最低氢气浓度。此自启动氢气浓度随着环境温度的上升而下降。在氢气体

积比为2%、水蒸气饱和的空气环境中、温度为20ºC的条件下，一个采用新（或

再生）催化剂的 PAR 将在 30 分钟内自启动。

与所有惰性金属催化剂相同，PAR 催化剂易于退化。这一点可以理解为

活性部位从催化剂表面被去除这种现象的结果——例如，催化剂活性部位被

除 O2 和 H2 之外的被吸附的分子所占据。

核安全壳空气中可能存在空气传播的挥发性有机物（VOC）。这些挥发

性有机物可能产生自反应堆维修停运期间所使用的化学制品（涂料、溶剂、

润滑油、粘合剂等）。VOC 也可能由喷漆表面释放或者在绝缘处理中释放，

特别是反应堆重启时的加热过程。

VOC能够吸附在任何惰性金属催化剂表面，占据一部分可用的活性部位。

这将导致催化剂暂时性的钝化 / 退化，从而影响到 PAR 的自启动。被吸附的

VOC 量将随着环境温度的上升而减少。在催化剂表面发生的氢气氧气放热反

应所释放的热量可以去除吸附的 VOC，也可用烤炉对置于空气中的催化剂进

行加热达到去除 VOC 的目的。

通过加热，最终可去除吸附在催化剂表面的所有 VOC，从而恢复催化剂

原有的活性和性能。

置有新催化剂板的 AECL PAR 将在氢气≤ 2%、温度≤ 20° C、压力为

1 巴、相对湿度为 100% 的条件下自启动 [1]。但在暴露于核安全壳空气中之

后，PAR 催化剂的活性部位可能会被 VOC 占据，从而暂时性地影响到 PAR 的

自启动能力。催化剂的状况将取决于安全壳空气中的 VOC 浓度、催化剂暴露

于安全壳中的持续时间以及安全壳温度。PAR 催化剂暴露于 VOC 中之后，PAR

可能需要氢气浓度大于2%以及/或者温度高于20°C的条件以快速自启动。

如果催化剂在氢气浓度中暴露的时间较长，复合器将在较低的氢气浓度以及

/或者较低的环境温度下自启动。对于给定的催化剂状况（退化等级）来说，

PAR自启动所需的氢气浓度将随温度的上升而呈指数下降[2]。PAR一旦启动，

即以设计能力运行。因此，PAR 的自启动性能（随时待用）是需要监视的关

键特性。

AECL已经证明，退化的催化剂板可以通过自启动（在氢气存在的情况下）

或在空气中加热恢复其初活性。此外 AECL 还证明，暴露于 2% 氢气条件下，

一个新（或再生）催化剂板所产生的热量可以使 PAR 中临近的催化剂板再生。

接着，得到再生的催化剂板所产生的热量又将使其临近催化剂板再生，从而

产生“多米诺效应”，最终使得该 PAR 内的所有催化剂板再生 [2]。因此，

定期对一个或多个启动催化剂板进行再生处理将保证 PAR 持续不间断的可用

性。

3、AECL PAR 试验设施

位于加拿大马尼托巴白贝实验室的大规模泄放燃烧试验设施（LSVCTF，

见图 2）是一个长 10m、宽 4m、高 3m 的矩形围场，内部空间为 120m3。该设

施的设计使其具有通用性，可实现多种几何形状的配置。该设施可采用隔墙

分为两个或三个隔间，这些隔间均配有用于内部排气的开口。该设施在仪表

配备、数据采集、气体采样和分析等方面具有丰富的功能。该设施的其他特

性包括：可在高于 100° C 的温度条件下运行很长的时间间隔、支持远程操

图 2 大规模泄放燃烧试验设施

图 3 安全壳试验设施

97 科技文章

表 1 AECL PAR 资格汇总

资格方面可操作性

压力 1-4 巴（绝对）

• 13-108°C（能力测量）温度

• 直至 750°C（功能）

氢气浓度体积比>0.5%

相对湿度直至 100%

辐射 370-480kGy伽马；暴露于 2000kGy 伽马下之后

进行的小规模活性试验

事故后 H2 瞬变是（假设发生冷却剂损失事故，事故后 CANDU反应堆内 24 小时的 H2 瞬变）

地震加速度 9.5 g（水平方向）、6.3 g（竖直方向）

热老化 50°C 下 40 年

燃料气溶胶和水蒸气是（模拟压水反应堆（PWR）堆芯聚变）

氢燃烧是（H2 体积比为 7.5-8%的条件下进行的引燃试

验）电缆/煤油火是喷雾

• 在氢气释放之前

是

• 在氢气释放之后

是

• 水

是

• 硼酸、硼砂、氢氧化钾

是（16g/kg 水硼酸、7.5g/kg 水硼砂、0.185g/kg 水

KOH） • 磷酸三钠（TSP）、氢氧化锂

是（120mg/kg 水 TSP、50-100mg/kg 水 LiOH）

• 氢氧化钠是（重量百分比为 0.6%）低氧浓度是（O2 体积比为 1-2%）事故后的化学物质（碘、碘甲烷、联氨、氯、

盐酸）是（5.0mg/m3 碘、5.0mg/m3 CH3I、100mg/L N2H4、

40mg/m3 Cl2、10g/m3 HCl）

长期暴露于工厂运行条件下之后是（高达 42 个月）

98 科技文章

作以保障人员安全。该设施内的试验条件可以精确地控制和测量。由于可以

很便利地进入试验室内部，所以可快速进行仪表配备和设施更改。

安全壳试验设施（CTF）球体（见图 3）的内部空间为 6.6m3，额定压力

达 10MPa，并且具有伴热功能。该设施具有控制氢气、氧气、氮气和空气添

加的多个系统。该球体可在一定限度内实现蒸汽伴随加热或冷却。该球体具

有防漏性能，因此可在高压、低氧和 / 或选定气体存在的条件下进行试验。

对于需要在试验期内保持试验条件的长时间（数天）试验，该球体是十分理

想的试验场所。CTF 球体内的试验条件可以实现精确的控制和测量。

4、AECL PAR 资格

AECL PAR 经过了多项累加的压力因素的考验，该类压力因素模拟了复

合器在其生命周期内预期将经受的运行条件。进行的资格试验还包括将 PAR

置于发生事故后的可能条件下的试验。在施加压力因素之前先进行了基线功

能试验，以确定 PAR 的性能。施加了多项累加的压力因素之后进行了中间功

能试验和最终功能试验，以证明 PAR 在经受压力因素之后的性能。

对 PAR 累积施加的压力因素包括热老化、辐射老化、长期暴露于氢气中

以及抗震测试。对同一 PAR 外壳和催化剂板还进行了功能试验，以确定喷淋

化学品的作用、高压对 PAR 能力的影响以及低氧对 PAR 自启动的影响。在法

国的 H2PAR 设施上，采用较小尺寸的 PAR 单元针对燃料气溶胶对 PAR 能力的

影响进行了测试 [1]。

所进行的中毒试验目的在于测试事故后的化学物质分别对 PAR 催化剂样

品和全尺寸 PAR 产生的影响。此类化学品包括碘、碘甲烷、联氨、氯、盐酸、

甲醛、苯、电缆/煤油火、二氧化碳和一氧化碳。受试样品的复合活性（复合率）

与新催化剂的活性进行了对比 [1]。

对复合器的评估是在 CANDU 运行条件下进行的。通过将受试 PAR 安装在

CANDU 反应堆内，研究催化剂表面的存在于安全壳空气内的 VOC 的影响。

包括热老化和喷雾试验在内的功能试验是在白贝实验室（AECL-WL）的

大规模泄放燃烧试验设施（LSVCTF）和安全壳试验设施（CTF）上进行的。

中毒试验是在乔克河实验室（AECL-CRL）进行的。辐射老化、抗震合格性以

及包括暴露于燃料气雾剂的试验在内的多项试验是在多个独立实验室进行

的。

5、AECL PAR 使用期间的检验

AECL PAR 无需特别维护。然而，为确保 PAR 的可用性，即在要求的特

定电站条件（温度和氢气浓度）下 PAR 的自启动性能，有必要对催化剂进行

定期测试。AECL 为定期现场测试开发了整板测试仪（WPT）——见图 4。

WPT 由受温度控制的外壳（炉室）组成，供 PAR 催化剂板插入。含有 2%

氢气（体积比）的空气混合物以受控流率进入炉室，到达催化剂板上方。六

个红外线传感器用于监测催化剂板温升随温度的变化。“通过”或“失败”

的指示与电站对PAR自启动的特定要求相关。“通过”表示催化剂板符合要求。

但是，WPT 并不指示催化剂实际发生的退化现象。因此，催化剂板在再次安

装前必须进行再生处理。“失败”表示催化剂板已经退化到不符合电站特定

要求的状况。因此可能需要修改检验时间表以保证 PAR持续不间断的可用性。

AECL 建议在每次维修停运期间进行下列活动：

• 目视检查每一 PAR 的一部分催化剂板

• 在 WPT 中测试每一 PAR 的三个启动催化剂板

• 对每一 PAR 的启动催化剂板进行再生处理（或以再生 / 新催化剂

板替换）

如果所要求的自启动温度等于或高于 100° C，则无需特别关注 VOC，

因为多年的研究已证明：无论催化剂退化等级如何，AECL PAR 均可在氢气体

积比等于或小于 2% 的情况下自启动。

6、AECL PAR 商业经验

AECL 已将其 PAR 供应至加拿大的 CANDU 反应堆和法国、芬兰、乌克兰

及韩国的压水反应堆（PWR）和水 - 水高能反应堆（VVER）。AECL PAR 的两

个型号（PAR1 和 PAR2）现已通过资格试验并安装在核动力应堆上。第三个

型号（PAR3）的设计能力更强，目前正在进行资格试验。

7、结论

AECL PAR 采用催化剂促进氢气和氧气之间发生产生水和热量的反应。

该 PAR装置是一个能够自启动 /自给的非能动系统，无需动力或操作员动作。

该 PAR 装置在 AECL 的氢气试验设施和国际性试验设施上经过了大量的合格

试验。由于惰性金属催化剂对 VOC 引起的退化的敏感性，该 PAR 装置在使用

期间需要采用 WPT 进行测试，并需要定期进行再生处理。AECL 自 2003 年开

始在全球范围内供应 PAR 装置。

8、参考资料

[1] J.V. Loesel Sitar 和 K. Marcinkowska，“AECL 专利氢气复合

器资格试验联合报告”，CANDU 业主集团报告，COG-00-217，2003 年 12 月。

[2] K. Marcinkowska，“AECL 非能动自动催化复合器（PAR）用于

Point Lepreau 发电站、Gentilly-2 发电站、Pickering A 发电站和 Bruce

A 发电站的评估”，CANDU 业主集团报告，COG-08-2133，2010 年 10 月。

图 4 整板测试仪（WPT）

99 科技文章

中国小型模块化反应堆 - 一

个令人激动的新领域作者： Yun Zhou and Jonathan Hinze, Ux 咨询

有限公司

世界核能是不断变化发展的。鉴于这一点，忽略以小型模块化核反应堆

为核心的核能发展趋势是很困难的。在小型模块化核反应堆领域中国尚且称

不上的领头军，但是中国在该领域也取得了很多显著业绩。像世界其他地方

一样，中国出现小型模块化核反应堆是核能行业一个令人激动的新型领域。

小型模块化核反应堆在中国的发展历程

20 世纪 70 年代，中国测试并发射了核潜艇，之后就开始从事小型模块

化核反应堆的设计。中国已经研发了几个小型反应堆，包括秦山核电一期的

CNP300 压水堆。CNP300 是中国第一个用于商业运行的压水堆，它属于小型

反应堆的范畴（发电量少于 300 兆瓦）。尽管中国选择集中精力研发大型

反应堆，但是中国早在 80 年代就着手开发小型反应堆以适应不同的应用。

中国开发、建造并运行了功率为 5 兆瓦的供热反应堆，用于区域供暖和海水

脱盐。之后，北京建造了 10 兆瓦的高温气冷堆 HTR-10。日前，清华大学和

华能集团组联合团队正将 10 兆瓦的高温气冷堆扩大为 200 兆瓦的模块化设

计。高温气冷堆示范工程已于 2012 年 12 月在山东石岛湾开始施工。

最近，中核集团公布了ACP100小型反应堆的设计。ACP100应用在电力、

供热或者脱盐方面，功率在 100-150 兆瓦。应用 ACP100 的核电站将可以配

备数量灵活的模型配置，数量从 1 到 8 不等。2011 年，中核集团和福建省漳

州市政府签订了一份在漳州市主办 ACP100 示范装置的协议。

与此同时，在小型反应堆和先进反应堆设计方面，中国也成为国际设计

者和研发者追逐的焦点。据报道，很多公司和中核集团洽谈合作，包括 B&W

公司（mPower 反应堆的设计者），NuScale Power 公司和 Hyperion 公司（现

在是四代技术）。

中国小型模块化反应堆发展的关键驱动力

尽管中国从事小型反应堆研发数十年，但是截止目前，中国在发展和部

署这些技术没有一个战略性计划，因此小型反应堆的设计仅限于利用之前的

技术进行小规模研究和开发。

上世纪 90 年代中国工程师被派往德国学习核电工程，由此获得球床高

温气冷堆技术。回国后这些工程师成为清华大学核能与新能源技术研究院指

导10兆瓦高温气冷堆的主力军。2000年开始，中国政府要求加强核能发展，

核能行业才逐渐关注小型模块反应堆的设计，部分原因还要归于全球对小型

模块反应堆的重视。尽管日本发生了福岛事件，这种发展趋势依然强劲。

目前，中国核工业集团得到政府和一些电力公司的金融支持，有足够的

资金为小型模块反应堆技术研发示范装置。此外，中方意识到在技术创新方

面与其他专业化核电国家有很大的差距，但中方正努力缩小这种差距。中国

致力于在不久的将来从技术进口国发展成为技术出口国。

尽管中国核电官方人员宣称小型反应堆可以解决偏远地区没有电网基础

设施和沿海缺少淡水的情况，但是在国内应用很难成为小型堆发展主要驱

动力。相反，技术创新和出口技术成为发展小型模块反应堆的主动力。

积极参与小型堆研发的组织机构

包括学术性组织机构、技术公司、核电公用事业单位和其他投资者在内

的等许多机构都参与了中国小型模块化反应堆的工作。

虽然中国小型反应堆项目还处于研发阶段，但是已经有两家重要的机构

参与其中，分别是清华大学核能与新能源技术研究院和核动力研究院。清华

大学核能与新能源技术研究院是单纯性的学术研究，是研究和开发小型反应

堆项目的先锋。该院的工程师和研发人员为不同的应用需求设计了 NHR-5、

NHR-200、 HTR-10、和 HTR-PM。同时，该院还从事于核潜艇的超临界轻水

反应堆的技术研究。核动力研究院提供了 ACP100 反应堆的工程设计。

作为第一个对小型反应堆理念进行投资的电力公司，华能集团联合中国

核工业建设集团公司和清华大学共同成立了华能石岛湾核电公司，该公司在

山东省建立高温气冷堆示范工程（华能拥有 47.5% 的市场份额，中国核工业

建设集团公司有 32.5% 的所有权，清华占有 20%）

另外，中国国电集团也成立了联合投资公司，由漳州能源公司和中核集

团组成。中核在福建漳州市开发了第一个 ACP100 反应堆示范工程（中核股

份为 80%，中国国电股份为 20%）

中国电力投资公司是中国拥有和运作核电厂的三大电力公司之一，它

同样对小型反应堆的设计感兴趣。当前，该公司正在现场指导研发小型反应

堆项目，并且和湖南省株洲市签订了合作协议。

中广核看似在小型反应堆设计方面失去竞争力，然而，近期中广核在

这个领域取得了一些进步。中广核的旗下研究院，即中国核电技术研究院，

于 2012 年成立了专门负责小型反应堆研究与开发的团队，2012 年 9 月在西

安举行了小型反应堆研讨会。并且，中广核与美国NuScale公司进行了会谈。

负责 AP1000 技术转移的国营企业—国家核电也意识到了竞争。国核与

B&W 公司在美国进行会谈，寻求小型反应堆技术转移的潜在可能性。

目前与将来的项目

目前，高温气冷堆示范电站和 ACP100 是两个最有希望推进到示范阶段

的设计项目。

100 科技文章

经过多年对北京原型模型的研发及小规模测试， 2005 年 11 月中国政

府批准了 210 兆瓦的高温气冷球形堆，这个标准示范工程在山东省威海市荣

成石岛湾开建。石岛湾示范工程为建设一个配备 18 机组（3780 兆瓦）的电

站项目创造了良好条件。尽管石岛湾被认为是示范核电站，然而在高温气冷

堆项目建设的开工之初，就包含了两个相当于 210 兆瓦商用机组。尽管这个

项目在 2009 年就获得开工权，但是 2012 年才正式开工建设，原因在于，受

日本福岛事件的影响，核能行业质疑球床堆的核心设计所具有的安全性能。

因此，2012 年底，这个项目最终获得开工权，正式浇筑第一注混凝土。

预估，第一个示范项目的施工时间大概在浇筑第一注混凝土后的 50 个

月。目前，这个项目已经预定了占总费用 90% 的部件，大多已在制造阶段。

像反应堆压力容器，蒸汽发生器，汽轮发电机系统等大型关键部件已经预定。

除了压力容器和蒸汽发生器，所有的部件都可以从核级制造商那里买到。据

悉，上海电气将制造压力容器，哈尔滨电气制造蒸汽发生器，方大碳素新材

料科技公司负责压力容器的内部构件。因此，中国本身可以为高温气冷堆示

范工程生产出必要的主要元件，这点无需担心。同时，氦通风扇和控制驱

动机构依然还在研究开发中，仪器控制系统和电力设备依然是国内弱项，可

能要依赖国外供应商，才能彻底完成这个项目的供应链。

示范项目小组已经完成了对燃料芯核的关键技术的综合试验。位于中国

内蒙古的燃料生产线正在建设中，这个北方燃料工厂每年可以生产 300000

个燃料组件，中国还与德国 SGL 集团签订了初期为高温气冷堆示范工程提供

500000 个加工石墨球的合同。然而，尚未证实大规模制造高品质球状燃料的

确切消息。对于高温气冷堆示范项目小组来说，这仍是一个挑战。

与大规模压水堆相比，除了技术问题，经济条件也是大问题。解决的办

法就是降低花费，包括简化反应堆辅助设备，仪器仪表和控制系统及部件结

构等。

ACP-100

随着小型模块反应堆的研究日趋国际化，2010 年中核集团下的核动力

研究院将目光转向发展具有非能动安全特性的小型集成模块化压水反应堆。

中核将 ACP100 作为动力资源的多功能途径。ACP100 同时适用于电力、工业

用热、脱盐处理。并且适用于缺乏能源的偏远地区和工业基础设施。

据报道，初期安全预估报告递交时预估 ACP100 的工程设计在 2012 年底

完成。中核计划在 2013 年年底获得开工权。

应用 ACP100 的核电站将可以配备数量灵活的模型配置，数量从 1 到 8

不等。预计 2013年底在漳州开工的第一个示范工程有施工周期将十分紧凑，

它旨在为漳州市提供电力，热能和淡水。

这项设计的非能动安全性能在第三地反应堆设计中有所应用，该项目已

秘密着手进行选址工作。ACP100 的输出功率是 100 兆瓦。中核称 ACP100 的

施工期为 30 个月，设计寿命为 60 年。压水反应堆的燃料循环周期预期为 24

个月。

由于经济规模的限制，设计小型反应堆依然面临巨大挑战。中国已经

意识到这个问题。中核称第一个示范项目预计花费将近 RMB 25,000/kWe

（~$4,000/kWe）。随着多模块选项的研发，将来的花费可能减少到 RMB

20,000/kWe (~$3,200/kWe)。

结论

很明显，在发展小型反应堆技术上，中国核工业紧跟现代国际发展的趋

势。每个中国核电公司都有自己的战略发展计划。高温气冷堆项目和 ACP100

将成为中国首批建造和示范的小型模块反应堆。其它小型模块反应堆设计最

终可能在将来进行部署。然而，百万千瓦级核电的大规模建设及其带来的

经济利润使得国内发展小型堆的市场前景渺茫。也许在未来的几十年里，中

国可能将目标转向国际市场而不是国内。尽管如此，由于需要在国内展示

这些技术的安全性和经济性，因此国内市场同样重要。因此，新型小型模块

反应堆在中国的发展前景还是被看好的。

高温气冷堆项目

来源：清华大学核能与新能源技术研究院

Ux 咨询公司于 2013 年早期在全球 SMR

Market Outlook 上发表了一篇专题报道，了解详

细信息请登录 www.uxc.com 或联系 Jonathan

Hinze 邮箱：[email protected]

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红沿河核电站一期 4 台机组预计 2015 年全部建成发电。4 台机组年发

电量将达 300 亿千瓦时，高于大连市 2012 年全社会用电量 287 亿千瓦时的

水平，约占辽宁省 2012 年全社会用电量的 16%。

红沿河核电站并网发电后，不仅优化了辽宁省电力供应结构，而且将促

进实现节能减排目标、进一步改善周边区域空气质量。与同等规模的火电相

比，红沿河核电站一期 4 台机组相当于每年减少标煤消耗约 1000 万吨，减

排二氧化碳 2400 万吨，减排二氧化硫 23 万吨，减排氮氧化物 15 万吨，相

当于造林 6.6 万公顷。

来源：http://www.china-nea.cn/

中国核电产业多渠道谋求铀矿话语权

“目前国际铀矿市场是买方市场，因此我国核电企业应利用这一有利时

机，提前谋求铀矿价格话语权。”多位核电专家在接受上海证券报采访时表示。

而据记者了解，目前我国核电企业集体谈判价格的机制正在形成。

全球铀矿仍是买方市场。目前，“国际铀矿现货价格已回落至 71 美元

/ 磅，虽然这一价格不太可能下跌至上世纪 90 年代天然铀（八氧化三铀）每

磅不足 10 美元的水平，但却仍有下跌空间。”一位资深专家分析说。

据了解，自 2003 年以来，国际铀矿价格快速攀升，2007 年一度曾接近

140 美元关口，此后便开始回落。“铀矿国际市场价格的波动，正给我国核

电发展和铀资源的战略启示。”在第十届中国国际核工业展览会上，多位业

内专家向记者表示。这些专家表示，2007 年国务院批准的核电中长期发展规

划，确定2020年我国核电装机容量建成4000万千瓦、在建1800万千瓦的目标。

为保障核电的健康发展，应开源节流并举，建立长期稳定的天然铀资源保障

体系。

实际上，“虽然我国核电发展目标有大幅增长，成为未来世界核电最

具增长性的市场。但是与世界其他国家相比，我国核电发展仍然很低。”中

国核学会秘书长付满昌说。统计数据显示，目前我国已投产核电装机容量约

900 万千瓦，占电力总装机的 1.3%，比例很低。而世界各国核电站总发电量

的比例平均为 16%，法国、日本、美国等国的比例更高。

“显而易见，法、日等国核电市场已经接近饱和，对铀资源的需要量

相对稳定，中国当前铀资源需求量有限，铀矿正处于买方市场。”中国核电

技术公司专家委员会资深专家郁祖盛说。他告诉记者，在这种情况下，正有

利于增加我国对国际铀矿价格的话语权。“在目前技术条件下，每百万千瓦

核电机组一年需要 130 吨至 150 吨天然铀（八氧化三铀）。”另一位铀矿资

深专家说。他给记者算了一笔账，按照我国 2020 年核电装机容量建成 4000

万千瓦估算，我国一年铀矿需求量仅 5200 吨至 6000 吨铀矿。值得庆幸的是，

在去年底，中国核工业集团公司披露消息，中国天然铀的地质勘查正取得突

破性进展。在鄂尔多斯盆地等地区，已探明国内迄今为止最大铀矿床。中核

集团公司表示，中国每年新增铀资源量远远大于需求量，不仅能满足中国核

电发展的需求，还为中国中长期铀资源保障奠定了良好基础。据预测，中国

潜在铀资源超过数百万吨。

综合上述情况，我国在铀矿资源上有更多优势谋求话语权。而据记者了

解，目前我国核电企业集体谈判价格的机制正在形成。

但是，“由于铀矿资源有一定的特殊性，不仅仅是市场供需决定价格，

还有一些其他因素，所以还要多方面做好资源储备。”该专家说。“从其他

国家发展经验看，在国内铀矿资源量有保证的同时，我们还要积极拓展海外

市场，做到两条腿走路。”付满昌说。

据核电技术资深专家郁祖盛介绍，每百万千瓦核电机组每天的经济效益

高达 1000 万人民币，因此提早一天运转，其经济效益显而易见。“同理，

如果核电机组因为铀矿资源不足，损失也是很大的。”另一位铀矿勘探专家说，

红沿河核电站 1号机组来源：辽宁日报


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为此多条腿走路以保障铀矿资源是必须的，大多数核电企业都这样做。


海阳核电一号机组堆内构件顺利到货

近日，运载海阳核电项目一号机组堆内构件的轮船顺利抵达海阳核电重

件码头。

一号机组堆内构件于 2012 年 12 月 9 日在美国朴茨茅斯港装船，2013

年 2 月 6 日到达上海港，2月 10 日堆内构件转内贸船发运海阳核电现场。

堆内构件是核岛的关键设备之一，由上部堆内构件和下部堆内构件两部

分组成，其主要作用是为反应堆堆芯提供支撑、为控制棒驱动机构提供导向

及构造反应堆冷却剂流道等。

海阳核电项目一号机组堆内构件由美国西屋公司纽因顿工厂承制。该设

备到货将为海阳核电项目一号机组核岛安装和 CV 顶封头就位打下了坚实的

基础。


马英九：核能四厂安全至上才会运转

据台湾媒体报道，马英九今天说，当局坚定地在核能安全上采最高标准，

必须确实符合安全至上、稳定商转目标，才会让核四厂运转。

据报道，马英九上午在马英九办公室接见法国前核能安全署署长拉柯斯

特时表示，台湾地区正在兴建中的核能四厂，当局要求相关单位必须进行更

完整、更严谨的试运转测试，并透过当局分层监督管理机制，与公正的国际

机构评估与视察，确实符合安全至上、稳定商转的目标，当局才会让核四运转。

他说，前年提出台湾地区能源政策时提到，确保核安、稳健减核、打造

绿能低碳环境、逐步迈向非核家园，是目前核能政策，且必须在不限电、维

持合理电价、达成国际减碳承诺三原则下，积极推动各项节能减碳措施，达

到稳健减核目标。

马英九指出，在核能安全上，当局坚定地采取最高标准，没有核安就没

有核电；在日本福岛核能事故发生后，当局对目前营运中的核能一、二、三

厂进行全面体检，从地震、海啸可能的防护及对整个核能运作的安全，每个

步骤都经过详细检验。

来源：http://realtime.xmuenergy.com/

2013 中国核电发展国际峰会将在杭州召开

由浙江省核学会、四川省核学会、黑龙江省核学会联合发起的 2013 中

国核电发展国际峰会将于 2013 年 5 月 28 日在浙江杭州召开。

据悉，2013 中国核电发展国际峰会旨在以浙江省核电项目为依托，聚

焦中国核电产业分析、核电装备制造、认证、核电站安全升级、新建核电站

项目及未来核电技术路线等热点话题，共同探讨行业面临的最新机遇与挑战，

搭建行业交流、合作和创新的平台，推进国内外技术交流、项目合作，帮助

企业和政府共同实现“走出去”，实现共赢。

据了解，本次国际峰会由哈尔滨电气集团公司、中国东方电气集团有限

公司、上海电气集团股份有限公司及中国核电城支持，上海广尧商务咨询有

限公司承办。


中广核与 WANO 巴黎中心举办第二届年度会议

近期，中广核集团与世界核电运营者协会 (WANO) 巴黎中心在大亚湾核

电基地举行了第二届年度会议。会议总结了过去一年中广核集团参与 WANO

高层交流、WANO 同行评审和技术支持等方面的情况，并就如何加强双方沟通

与合作进行了交流。

会议肯定了过去一年大亚湾核电基地在WANO指标方面取得的优秀成绩，

以及中广核集团作为 WANO 巴黎中心的重要成员所发挥的重要作用。双方就

新一年如何充分利用 WANO 平台确保中广核集团核电运行业绩和新机组的顺

利启动进行了探讨，并把提升 WANO 活动价值、深化参与 WANO 活动的程度、

强化对新基地新机组的支持确定为 2013 年双方合作的重点，同时希望通过

合作共同推动和提高世界核电机组的安全状况。

WANO 巴黎中心主任 Ignacio Araluce 等一行 4 人出席了会议。中广核

集团有关人员、WANO 工作组成员参加了会议。

来源：http://news.bjx.com.cn/

我国可能将加快新建 30 座核电站

“各种研究显示，中国将很快成为最大的二氧化碳排放国。”昨日，在

北京召开的“铀监护和可持续发展国际研讨会”上，联合国开发计划署能源

环境部经理何平认为，这将给中国在全球气候变化谈判中带来巨大压力。

据介绍，核电目前占全世界发电量的 16%，在全球范围内，核电每年约

减少二氧化碳排放 6亿吨，而这相当于现在全球温室气体排放的 8%。

事实上，“中国是头号二氧化碳排放国”的论调时有耳闻。

此前，一份由荷兰环境评估机构发布的报告宣称，中国在 2006 年温室

气体排放已经超过美国 4亿吨。

但中国外交部当即否认了此观点，称该结论没有根据，同时表示中国正

在积极参与全球温室气体减排行动。

近几年来，中国推进节能减排的力度日益增大，并加快进行能源结构的

调整，其中包括积极发展核电。

在何平看来，自 2001 年到 2005 年，随着世界制造基地转移到中国，中

国的重工业开始快速增长，特别是钢铁、化工、水利等行业的快速增长是能

源强度上升的主要因素。

他指出，中国要推进可持续发展，除调整产业结构及增加可持续能源的

国家预算外，加快核电等清洁能源的发展也是重要方向。





http://news.bjx.com.cn/html/20130220/418562.shtml

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对于这一观点，国家环保总局核安全管理司副司长王中堂表示赞同。

“作为清洁、安全、经济的能源，核电发展是中国未来一段时期的必然

选择。”王中堂认为，积极发展核电，既有助于保障能源安全、优化能源结构，

也能帮助中国应对当前面临的温室气体排放压力。

按照中国的核电中长期发展规划，到 2020 年，中国将建成 4000 万千瓦

机组，年发电量达到 2600 亿～ 2800 亿千瓦时，在总发电装机容量中占到 4%

～ 6%。

“这意味着中国在 20 年内至少还要建立 30 座新的核电站。”中国可持

续发展工商理事会副秘书长翟齐说，中国非常重视核能的绿色效应，但与法

国、美国等核电发展水平较高的国家相比，中国的核电发展还处在起步阶段。

来源：http://www.cnnc.com.cn/

ACME 试验项目反应堆压力容器顺利通过水压试验

经过现场连续两周的昼夜奋战，ACME 试验项目的反应堆压力容器于

2013 年 2 月 6 日下午 13 点 47 分顺利通过水压试验。反应堆压力容器经过电

加热棒及密封件安装、电缆安装、内部构件组装、上封头扣盖等过程，最终

完成反应堆压力容器的组装，并顺利通过水压试验。

来源：http://www.snptrd.com/

三代核电项目进口设备免税专家审查会在京召开

2 月 21 － 22 日，财政部、发改委、工信部等部委在京组织召开了三代

核电项目进口设备免税专家审查会。来自行业协会、研究院所、制造企业的

专家，以《国内投资项目不予免税的进口商品目录》为主要依据，对三门核

电一期、海阳核电一期、台山核电一期工程项目以及田湾 3、4 号机组进口

设备申请免税清单进行了审查，将国内能够生产，或不满足《目录》条件的

设备进行了梳理。经过仔细审核和反复讨论，会议形成了专家意见，供有关

部门制定政策时参考。

中国核能行业协会副秘书长、专家组成员徐玉明、龙茂雄参加了会议。

徐玉明代表专家组向与会代表宣读了专家意见。


热工院承办第二期 “RCC-M 压水堆核岛机械设备设计和建造规则”培训班

为了更好地消化、理解和充分掌握 RCC-M 系列标准，推进我国核电设备

自主化进程，提高国内核电设备制造水平，中国核能行业协会定于 2013 年 4

月 23 至 27 日，在江苏省无锡市举办第二期 “RCC-M 压水堆核岛机械设备

设计和建造规则”培训班。培训班由苏州热工院具体承办。


企业新闻

新兴际华集团气瓶类产品首次进入核电领域

日前，新兴际华集团新能装备公司研制的“海南昌江核电工程 SGZ 系统

氮气高压储罐”正式交付使用。

海南昌江核电工程是海南省首个核电项目，“SGZ 系统氮气高压储罐”

作为海南昌江核电工程的系统部件，是液态氮气化后的贮存设备，起到高压

氮气的储存和缓冲作用。储存在其中的氮气通过中压氮气减压站减压后供给

中压氮气用户。

“海南昌江核电工程 SGZ 系统氮气高压储罐”是该公司气瓶类产品第一

次进入核电领域，公司研发人员克服各种困难，按时保质的完成了设计研发

任务，通过这次核电产品的研发与制造，提高了该公司的设计研发能力，增

强了产品的制造精度，为以后的核电项目积累了丰富的经验。


久立特材获核电站核心设备制造许可证

久立特材2月18日晚公告称，公司于近日收到国家核安全局有关通知，

认定公司在所申请的民用核安全机械设备制造方面具备了所要求的各项能

力，批准公司《民用核安全机械设备制造许可证》增加附件所列许可活动范围，

扩大的范围主要涉及核安全一级镍基合金热交换器传热管的制造许可。

久立特材称，该证书的取得标志着公司成为国内有资格进入核电站核岛

主要核心设备 - 核电蒸汽发生器主要部件和关键材料：镍基合金 U 形传热管

制造领域的第二家企业，从而增强了公司的核心竞争能力，有助于公司加快

全面实现募投项目所制定的目标。

久立特材自成立以来，一直从事工业用不锈钢管的生产、销售和研发，

产品主要运用于石油、化工、天然气、电力 ( 包括核电 ) 设备制造等行业。

公司目前的产品主要是不锈钢无缝管和不锈钢焊接管两大类。公司产品的主

要消费群体是石油、化工、天然气、电力(包括核电)设备制造、造船、造纸、

其他机械制造等行业用户。


辽宁电科院圆满完成红沿河电站 1 号机组励磁参数测试试验

2 月 10 日至 13 日，辽宁电科院圆满完成大连红沿河核电站 1 号发电机

的励磁参数测试试验工作。

http://www.cnnc.com.cn/publish/portal0/tab60/info71882.htm

http://www.snptrd.com/

http://www.china-nea.cn/




新闻105

红沿河核电一期工程是国家“十一五”期间首个批准开工建设的核电项

目，是中国首次一次性审批通过 4 台百万千瓦级核电机组标准化、规模化建

设的核电项目，也是是东北地区第一个核电站。红沿河核电一期工程 1 号机

组于 2007 年 8 月 18 日正式开工，计划于 2013 年春节后并网，4 月投入商

业运行。

辽宁电科院技术人员进入红沿河核电站 1号机组调试现场后，不顾疲惫，

马上开展试验前的准备工作，与现场调试单位制定了详细的试验计划，并严

格按照核电工程的要求入场着装。2 月 11 日 23 时，辽宁电科院技术人员完

成了 1 号发电机组的空载特性试验和大阶跃试验；2 月 13 日 17 时 30 分，

完成了 1 号发电机组的 5% 阶跃试验。本次试验的完成，标志着红沿河核电

站 1 号机组已完成并网前的空载试验工作，为春节假期后 1 号机组顺利并网

打下了坚实的基础。中广核工程有限公司领导对辽宁电科院技术人员放弃春

节休假，全力支持红沿河核电调试工作的精神给予了高度评价。


国内首次完成 AP1000 椭圆形封头

近日，中国第二重型机械集团公司顺利完成由上海电气核电设备有限

公司承制的 AP1000 核电椭圆形封头精加工，并一次交检合格。这是国内首

次实现第三代椭圆形封头的一体化制造，它的加工完成标志着中国二重在第

三代 AP1000 核电蒸发器锻件领域制造又取得一项重大突破。

椭圆形封头是AP1000核电蒸发器的重要部件，直径大，加工工艺复杂。

中国二重通过科研攻关，突破了椭圆形封头整体成型、整体加工瓶颈，完成

和优化了产品的设计和工艺编制，建立了一整套严格的质量控制和保证体系；

在生产中，精心组织安排，及时完成了精加工任务。

来源：http://www.cnnc.com.cn/

第三代核电站核级泵实现国产化分析

AP1000 核电站是目前全球核电市场中最安全、最先进的商业核电技术，

由美国西屋电气公司设计开发，为了最大限度减少泄漏点，这样一台百万千

瓦机组核岛中只有两种核级泵。日前，大连深蓝泵业有限公司完成了其中的

余热排出泵的国产化，达到国际先进水平并通过了国家鉴定。同时，该公司

设计制造的核岛非核级泵启动给水泵样机、常规岛用的凝结水泵样机也通过

国家鉴定，达到国内先进水平。

正常余热排出泵是核岛正常余热排出系统的重要设备，负责在电厂正常

停堆期间排出反应堆冷却剂系统的热量。AP1000 核电站对泵的抗震等级和技

术可靠性要求极高，目前国内在建的 4 个 AP1000 核电站机组用泵全为国外

进口，大连深蓝泵业的创新将打破这种局面。中国工程院专家认为，大连深

蓝泵业完成的 AP1000 核岛正常余热排出泵样机结构设计合理，完成了苛刻

的工况试验，满足了核电站使用要求。

大连深蓝泵业自 2005 年取得核三级泵设计制造许可证以来，紧紧围绕

石化、煤化工、核电行业大力进行新产品、新材料的研究与开发。近年来，

先后完成了 3 种核二级泵和 5 种核三级泵样机并通过国家鉴定。其中，5 种

核三级泵的成功研发，率先完成了我国核三级泵国产化的目标，并荣获国家

能源局“百万千瓦核电站泵阀国产化”科技进步一等奖。目前，其在国内核

三级泵市场占有率达到了 80%。


中核运行一厂正式进入第十四次换料检修阶段

2 月 20 日 6 时 37 分，中核核电运行管理有限公司一厂 30 万千瓦核电

机组顺利与华东电网解列，按计划完成第十四个燃料循环运行，正式进入第

十四次换料检修阶段（R14）。

本次大修是 30 万千瓦核电机组的五年大修，计划工期 42 天，将对汽

轮发电机组进行全面解体检修。大修将实施主泵 A 轴承箱、离心上充泵 A、

安注泵 A、停冷泵 A 解体大修在内的核岛主要检修项目，实施 PSR 弱项和

福岛核事故后安全专题整改项目等重大技改项目。R14 大修计划安排预防性

维修项目共 3210 项，技改项目 26 项、变更项目 60 项、状态报告纠正行动

55 项、在役检查 80 项、定期试验 219 项以及 300 多项纠正性维修处理。

为了下一燃料循环的安全稳定运行，中核运行一厂全体员工将秉承“细

准备、重执行、迎挑战、创全优”的大修理念，抓好项目的跟踪管理和实施，

严把安全关和质量关，在保证安全、保证质量、控制进度的前提下，持续优

化大修成本，确保换料检修各项任务圆满完成。


我国具备了核燃料生产的自主化工业能力

记者 2 月 22 日了解到，历经长期艰苦攻关，中核集团研制的铀浓缩离

心机在兰州成功实现工业化应用，这标志着我国具备了核燃料生产的自主化

工业能力，完全掌握了离心法铀浓缩技术，对保障我国核电可持续发展有着

重大战略意义。

铀浓缩离心机技术是核燃料生产的关键技术，是衡量国家核技术水平的

重要标志。离心机具有高真空、高转速、强腐蚀、高马赫数、长寿命、不可

维修等特点，其研制涉及机械、电气、力学、材料学、计算机应用等多种学

科的理论和技术领域，技术难度很大。国际上从事离心机研制的国家有俄罗

斯、德国、英国、美国、日本等 10 余个国家，真正实现工业化生产的有西

欧 Urenco 合资公司和俄罗斯 Rosatom 公司。

中核集团科研人员成功攻克了离心机研制中的众多技术难关，突破多项

关键技术，完成了研制任务并装配铀浓缩工厂，实现了离心机的工业化应用，

多项技术指标达到国际先进水平；形成了离心机研发制造，离心工程设计、

建造和运行的完整的铀浓缩研发和产业体系，现有装备能力满足目前国内核

电装机的需求，且技术水平和装备制造能力可以保障和满足国内核电发展的

需要。


一号模拟机投运于海阳核电

为做好模拟机软件安装、SAT（现场验收试验）和操纵人员培训相关准

备，2 月 25 日，公司组织召开了一号模拟机 SAT 及培训相关准备工作会议。

公司党委书记、副总经理余兵，副总经理王有志出席会议。





http://www.china-nea.cn/html/2013-02/25811.html

新闻 106

会议听取了模拟机安装、测试和培训期间西屋对现场支持方面的需求介

绍，梳理了影响模拟机 SAT 及培训工作的问题，明确了各相关部门的工作任

务目标，为一号模拟机按计划完成SAT以及后续的培训可用做好了充分准备。

余兵强调，一号模拟机的按时投运是保证公司首批操纵人员顺利培训和

取照的前提，是海阳核电一期工程的重要里程碑节点之一。希望各部门高度

重视模拟机 SAT 及培训的准备工作，加强协调合作，落实准备工作任务，确

保一号模拟机顺利可用于培训。

来源：http://www.sdnpc.com/

昌江核电厂应急预案通过评审

国家核应急办公室近日在北京组织召开《海南昌江核电厂场外应急预案》

( 以下简称《预案》) 专家评审会，来自核应急领域的 5 名专家对《预案》进

行评审。

专家组一致认为，《预案》内容符合国家核应急相关法规、规定，内容

翔实，较好地吸收了日本福岛核事故后国内外开展核应急工作的经验，符合

海南省核应急工作实际，针对性和可操作性较强，一致同意《预案》通过评审。

海南省核应急办表示，将进一步加强核应急能力建设，加快推进与《预

案》相配套的《海南昌江核电厂场外应急执行程序》的编制，同时指导海南

省核应急委各成员单位开展相应核应急工作。


国际合作

Centrica 总裁赖德劳表示：“ 自从我们首次投资之后，投入资金一直在

增加，建设时间表延伸了几年，综合考虑这些因素，以及投资时长和资金回

转的规模，令我们认为，参与这次建设计划对公司和控股者并不合适。” 这

四座反应堆中有两座位于 HinckleyPoint 和森马实的核电站，另有两座位于

修克福的 Sizewell。

尽管 Centrica 撤销其在新的四座反应堆中 20% 控股，该公司仍保持其

在现有 8 个核电站的 20% 控股，这些核电站将在未来 20 年内关闭。


我国核电业日渐强大法国核电巨头陷两难境地

在中国和法国的经济合作中，核电、航空、铁路一直被视为三大支柱，

但是法国似乎在逐渐陷入一种尴尬的地位。一方面，中国是公认的未来全球

最大核电市场，法国不想放过这块 “ 肥肉 ”。另一方面，他们担心：不断加

强技术水平的中国核电企业，未来在国际市场上会不会抢了法国的饭碗？对

此，中国国际经济交流中心秘书长魏建国对此作出点评。

在中法核电领域的合作，有人说，中国绕不开法国的核电企业，但是也

有人说，中国企业未来会取代法国企业，中国与法国谁更有话语权？

魏建国：中国市场无论从汽车也好，还是从其他的产品来看也好，都是

国外非常羡慕也非常看重的大市场，如果法国核电上面有一些核电技术，这

个核电技术也在一定时间内比较先进，如果不继续在实践中加以应用，实践

中加以发展，这个技术也是落后的。所以今后，在这种博弈中，最好的是中

法共同联合起来，利用中国核电市场大发展有利时机，这样对法国的核电企

业也是有发展前景的市场。

法国核电巨头 “ 又馋又怕 ” 中国市场，面对这样的两难境地，他们如何

权衡？

魏建国：法国在这个问题上面最终会选择占领市场，利用技术换市场，

这套路子还可以走下去，如果不想把这个技术尽快的转让，最后技术可能会

落后，甚至会失掉中国市场。

在未来的核电国际合作中，面对法国提出的条件，中国企业又该注意些

什么？怎么做？

魏建国：中国在这个方面游刃有余，我们不仅可以跟法国合作，我们也

可以有美国的技术，我们也可以参照日本的技术甚至还有俄罗斯的技术，中

国企业应该完全把握住整个市场，货比三家。第二，我们也要承认，法国技

术有它的先进性，可以利用法国想多占有一些市场的心理，跟它进一步的博

弈，希望它能够尽快的多一些的转让先进技术，快一些转让先进技术，这些

作为中国企业来讲，也不失为一个好办法。

来源： http://finance.huanqiu.com/

仪控协议签订将加快中国核电国产化进程

西屋电气公司将与中国国核自仪系统工程有限公司（SNPAS，简称国

核自仪）携手合作，共同为中国今后的 AP1000 核电站提供仪表控制系统。

中法两国或将控制英国核能市场

耗资上亿镑的英国核电站发展计划中，英国唯一核电公司 —Centrica

正式宣布退出四座核反应堆的建造计划，法国电力集团 EDF 正寻求新合伙

公司，中国国有企业中广核集团与 EDF 进行磋商，这意味着英国未来的核

能源供应很可能由法国和中国政府共同控制。

GMB 工会对此提出异议，认为英国核电发展唯一选择是将其国有化，

由英国控制，而不是让其落入法国和中国政府手中。Centrica 是英国唯一

的核电公司，拥有建设新核电站的财经资源和专业人才。而且，EDF 给予

Centrica 该四座核电反应堆 20% 股份。然而，2011 年日本福岛大地震引致

核电条例更改，核电站建设费用增加，Centrica 出于此担忧而决定退出建设

计划。




http://finance.huanqiu.com/

新闻107

国核自仪与西屋在北京签署了该协议，协议规定了基本条款、条件、双

方在中国 AP1000 项目中的职责分工和工作范围，同时对双方未来的项目合

同的签订做了相关安排。

根据双方商定的合作模式，国核自仪为今后AP1000项目的仪控总包商，

西屋电气公司为仪控主要分包商。西屋核能自动化高级副总裁大卫 . 豪威尔

（David Howell）称，协议的签订，标志着公司着手通过当地合作伙伴“利

用最优的本地资源为核电站寿期内的产品提供长期生命力”，从而“提供业

内领先的全球技术”。另一方面，国核自仪总经理邱韶阳高度赞赏双方开展

的“良好合作关系”。

目前中国三门和海阳共有 4 座在建 AP1000 压水反应堆。三门 1 号机组

预计明年并网发电，其余 3 台机组预计 2016 年发电。中国一方面计划继续

建造 AP1000 机组，另一方面也在开发本土的先进反应堆设计，并在 2007

年签署了技术转让协议，计划在三门和海阳建造新机组。

国核自仪是一家由国家核电技术有限公司 (SNPTC，简称国家核电 ) 和

上海自动化仪表股份有限公司（SAIC）组成的合资公司，目前为三门和海阳

核电站业主提供仪控系统和设备。此外，公司还在为中国自主研发的大型先

进压水堆开发仪控系统。

国产化越来越成为核电站建设项目的重要特色，要求反应堆供应商增加

项目中当地供应商和承包商角色。甚至在项目确定之前，西屋电气公司等反

应堆建造商和本地供应商就频繁签订合作协议，供应商在争取拿到订单的同

时，也越加注重与本地供应链的联系。


中国和阿根廷将扩大核能领域合作

近日，中国和阿根廷签署了两份协议，这表明两国将扩大核能行业的合

作。协议涉及到合作方式、技术、中国供货产品及阿根廷出口服务等内容。

阿根廷核电公司 NASA 与中国核工业集团公司在布宜诺斯艾利斯签署

了这两份协议，阿根廷联邦计划部部长胡里奥先生，中国大使殷恒民及中核

集团中国中原对外工程有限公司参加了签约仪式。

NASA 与中核集团签署的第一份协议以反应堆压力管为主，涵盖工艺、

制造、使用和维护。同时，该协议还设计到了核能源的制造与储存、许可证、

周期延长和技术提高等。该协议指向的是在运行的核电站以及未来要建的核

电站。

第二份协议要求中国向阿根廷提供技术转移。阿根廷将作为技术平台，

向第三国家输送核电技术、中国的产品及服务。

此外，中核集团的代表向对方展示了我国 CAP-1000 反应堆的技术及相

关费用。阿根廷第四核电站反应堆将会考虑 CAP-1000 反应堆在内的几个设

计方案。

阿根廷有两个在运行的核反应堆，一个位于 Atucha，一个位于

Embalse。Atucha 的 2 号机组现在几近完工。该项目与 1981 年开工，20 世

纪 90 年代由于资金短缺一度停工，2006 年工程得以继续。该项目的 3 个机

组均为重水压水堆 (PHWRs)。Embalse 的反应堆是 600 兆瓦的 Candu-6 反

应堆，Atucha 的机组是由西门子特别为阿根廷设计的。

阿根廷政府计划建立第四机座核电站，可行性研究报告已在撰写中。

2007 年 7 月，NASA 与加拿大原子能有限公司就 740 兆瓦 Candu 6 加强反

应堆与 Atucha 2 号机组签署了合同。然而，由于政府现在正在于包括法国、

俄罗斯、日本、南韩、中国、美国在内的多家反应堆供应商谈判，所以最终

会采用的设计方案还尚未知晓。Atucha 3 号机组的设计方案将会取决于 2 号

机组的完成情况。

2007年9月，加拿大原子能有限公司与NASA和中核集团签署了备忘录，

他们将会携手合作，对阿根廷、加拿大、中国将建的 Candu 核电站项目进

行研究，合作范围将含括 Candu 反应堆的设计、制造、建设及运行灯。此外，

中核集团与阿根廷 NASA 公司就加强 Candu 6 反应堆运行维护经验进行交

流与共享达成一致。


贺禹会见摩根士丹利董事局主席高闻

2 月 21 日上午，中广核集团公司董事长贺禹在深圳科技大厦会见了来

访的摩根士丹利董事局主席兼首席执行官高闻（james Gorman）一行。高

闻表示，中广核集团是国内一流的核电集团，摩根士丹利作为国际领先的投

资银行，愿意为中广核集团提供投资银行服务。双方还就欧美及中国的经济

形势进行了交流。

摩根士丹利亚太区、中国区、亚洲投行部有关领导，中广核集团公司相

关人员参加了会见。

来源：http://www.cgnpc.com.cn/

中俄加强在第三国建核电站等合作

国务院副总理、中俄能源合作委员会中方主席王岐山 25 日在北京与俄

罗斯副总理、俄方主席德沃尔科维奇举行会晤。

王岐山说，能源合作是中俄全面战略协作伙伴关系的重要组成部分，两

国元首和总理均高度重视。中俄能源谈判机制建立 5 年来，取得了丰硕成果，

为深化两国务实合作，推动中俄全面战略协作伙伴关系健康发展，发挥了十

贺禹会见摩根士丹利董事局主席高闻来源：www.cgnpc.com

http://realtime.xmuenergy.com/


http://www.cgnpc.com.cn/n2881959/n3065920/n3069980/6497415.html

www.cgnpc.com

新闻 108

分重要的作用。中俄能源合作互有需求，资源、市场、技术各有所长。双方

进一步加强能源合作，不仅有互补性、必要性和可能性，更具有战略和全局

意义，符合两国人民的根本利益。此次中俄能源合作委员会主席会晤取得了

实实在在的成果，为中俄全面战略协作伙伴关系注入了新的动力。

王岐山表示，近日双方达成了扩大原油贸易的重要共识，中俄能源合作

取得新的重大进展。双方政府部门应就原油增供问题抓紧磋商、尽快签署政

府间协议，两国企业在互利基础上加快商务谈判。关于中俄天津炼厂项目，

希望双方尽快磋商，签署政府间协议文本。两国政府支持企业进行东部管道

供气谈判，双方确认将通过东线管道每年对华供气 380 亿立方米，并就东线

液化天然气项目和西线供气合作继续研究论证。中俄两国核能合作势头良好，

前景广阔，希望双方开展全方位合作，同步推进核电站、空间堆、浮动堆、

快堆以及在第三国建设核电站等一揽子合作。支持两国企业在互利共赢的基

础上，继续推动电力、煤炭、能效与可再生能源、铝业等领域的长期合作。

德沃尔科维奇表示，俄方对两国全面战略协作伙伴关系的发展及在能源

领域的合作感到满意。俄方认为，原油增供既有必要性，也有可能性，符合

两国共同利益。天然气项目是两国能源合作的优先和重点方向，希望并行不

悖地推进东线管道气和液化天然气项目合作。在核能项目合作方面，双方照

顾彼此关切，成熟一个推出一个。俄中在石油、天然气、电力、煤炭、新能

源等各领域全方位合作，充分体现了两国全面战略协作伙伴关系的精神。

会晤后，王岐山与德沃尔科维奇共同签署了《中俄能源合作委员会双方

主席会晤纪要》。

来源：http://news.bjx.com.cn/html/

李干杰会见土耳其能源与自然资源部代表团团长阿特金

中新网 2 月 26 日电据环境保护部网站消息，环境保护部副部长李干杰

日前指出，中国核电发展30年，截至目前，中国已有商业运行核电机组15台，

在建核电机组 30 台，持续保持着良好的安全运行记录。

李干杰日前在京会见了土耳其能源与自然资源部代表团团长阿特金一

行。双方就共同关注的核电及核安全合作等议题进行了交流。李干杰首先代

表环境保护部、国家核安全局对土耳其能源与自然资源部代表团一行表示欢

迎，并预祝中土两国在能源领域的合作圆满成功。

李干杰介绍说，中国核电发展 30 年，截至目前，中国已有商业运行核

电机组 15 台，在建核电机组 30 台，持续保持着良好的安全运行记录。

李干杰指出，2011 年日本福岛核事故的教训是十分深刻的，但是这并

没有改变世界对核能的基本需求和认识。核安全是核能发展的生命线，是核

电发展的重要保障。中国政府在日本福岛核事故后采取了一系列加强核安全

的措施，包括对所有核设施进行了综合安全检查、制定核安全规划、编制核

电厂安全改进通用技术要求等，提出和实施了针对福岛核事故经验教训的改

进要求。

李干杰称，众所周知，经济发展离不开能源的支撑，中国愿意与土耳其

进一步加强合作，在确保安全的基础上，共同推进核电的发展。

阿特金详细介绍了土耳其的能源发展现状。他介绍说，土耳其经济发展

迅速，能源需求巨大，发展核电是其解决能源供应和结构问题的重要选择。

他希望土中两国加大核能合作，带动土耳其的核电发展。

来源：http://www.dzwww.com/

中荷探讨荷兰核安全峰会筹备工作

2013 年 2 月 20 日，外交部部长助理马朝旭会见到访的 2014 年荷兰核

安全峰会荷方协调人德克勒克大使，就荷兰核安全峰会筹备进程相关问题交

换了意见。

来源：http://www.smnpc.com.cn/

核电站

新闻福清首个蜗壳合并施工完成浇筑

2 月 5 日，福清核电项目 3PX 泵房泵室 B区蜗壳成功完成混凝土浇筑。

蜗壳施工作为核电站的土建施工三大难点之一，钢筋密集，绑扎复杂，

施工作业面狭小，甲供埋件安装精度高，纤维加硅粉混凝土浇筑困难，3PX

泵房在吸取以往经验的前提下，对施工方案进行优化，合理安排施工，将D、

F1 块进行了合并浇筑，一次浇筑高度为 6.363m，成为福清筏板类混凝土浇

筑高度最高的子项工程，节约了约一个半月工期。同时加强现场巡视，消除

各类质量安全隐患。

3PX 蜗壳的浇筑完成是各单位通力协作、密切配合的结果，春节前完成

施工有效的避免了春节期间功效降低的影响，为 2013 年各目标节点的实现

创造了有利条件。

来源：http://www.cnpe.cc/

海阳核电 1# 机组主管道焊接拉开序幕

2 月 2 日，海阳核电 1# 机组 B 环路主管道的三根管段顺利吊装并导入

核岛预定位置就位。B 环路主管道的吊装完成表明海阳 1# 机组主管道导入工

作已经全部完成，为现场主管道组对焊接创造了条件。2 月 3 日主管道成功

开焊，标志着主管道焊接工作正式拉开序幕。

AP1000 主管道主要包括两个热段管和四个冷段管，它是连接反应堆压


http://www.dzwww.com/xinwen/xinwenzhuanti/2008/ggkf30zn/201302/t20130226_8192080.htm

http://www.smnpc.com.cn

http://www.cnpe.cc/tabid/593/InfoID/71711/frtid/591/Default.aspx

新闻109

春节期间，JPMO 驻厂监造人员仍然坚守岗位，见证了穿管工作的顺利

进行。


红沿河核电站 2 号机组冷试开始 2 月 20 日 16:56，当班值长向试验负责人颁发了红沿河核电站 2 号机冷

试工作许可证，标志着 2号机组冷态功能试验正式开始。

冷态功能试验是机组进入系统调试阶段后的第一个综合性调试试验，主

要通过相关试验检验主回路安装质量。福岛核事故后，国家核安全局加大了

对核电机组的核安全监督力度，并增设冷态功能试验为控制点。在工程、生

产双方的共同努力下，红沿河核电公司顺利完成了 2 号机冷态功能试验前的

所有准备工作。2 月 20 日，国家环保部东北核与辐射安全监督站向红沿河核

电厂下发了《关于批准释放辽宁红沿河核电厂 2 号机冷态功能试验控制点的

通知》（国环东北核监（2013）15 号），批准 2号机组冷试可以进行。

标签：http://www.cgnpc.com.cn/

大亚湾核电基地六台机组未受河源地震影响

中广核集团 22 日下午对外通报表示，当天发生在广东省河源市的地震

距离大亚湾核电基地较远，本次地震未对大亚湾核电基地六台机组造成任何

影响。

通报表示，当天基地内的大亚湾核电站、岭澳核电站一期、岭澳核电站

二期的地震仪表系统均未触发报警。

据中国地震台网测定，2013 年 2 月 22 日 11 时 34 分在广东省河源市东

源县（北纬 23.9 度，东经 114.5 度）发生 4.8 级地震，震源深度 11 公里。

据预测，震中距大亚湾核电基地约 145 公里。

中广核集团表示，设计上，大亚湾核电站、岭澳核电站一期、岭澳核电

站二期与核安全相关的构筑物和系统抗震设防烈度为 8 度，核电站的安全有

保障。


宁德核电 2 号机组 CRDM 耐压壳安装与焊接工作顺利完成

2 月 22 日，宁德核电 2 号机组控制棒驱动机构耐压壳安装与焊接工作

顺利完成。

CRDM 是用来驱动控制棒束组件、控制反应堆反应性的重要设备。它的

安装与焊接的质量及施工逻辑要求非常高。宁德 EM2 队为确保整体施工质量

以及进度的顺利推进，组织施工技术人员认真分析总结前期 1 号机组施工经

验、调整作业模式、优化人员配置，最终在质量可控、安全高效的条件下，

顺利完成全部耐压壳的引入、安装、焊接和检查工作，在焊缝目视检查、液

体渗透检查和水压试验过程中均一次通过。

来源：http://www.cni23.com/

力容器、蒸汽发生器和反应堆冷却剂泵最关键的核安全 1 级设备之一。反应

堆冷却剂系统由两个环路构成，每个环路包括一条热段和两条冷段。核反应

堆的冷却剂由 4台反应堆冷却剂泵 (RCP) 驱动，流经反应堆容器内部冷却堆

芯，被加热的水通过 RPV 排出接管和 RCL 热段管道输送到蒸汽发生器（SG），

再由 RCP 驱动经冷段重返压力容器，从而完成一个循环。

主管道施工是核岛施工的重中之重，将直接影响后续工程的施工进度，

为确保施工正常进行，海阳总包部主系统施工队及各相关部门人员全力以赴

进行各项准备，实现 2013 年开门红。

来源：http://www.cnec5.com/

内陆核电“十二五”获批准无望转战沿海核电

虽然我国从 80 年代开始就进行内陆核电选址，并确定了几十处可建设

区域，但目前在运行及开工建设的41个机组全部坐落于滨海省份的近海区域。

考虑到福岛事件以及安徽省望江县政府报告所引起的民众情绪反弹，再加上

今年以来相关决策机构对于内陆核电的谨慎表态，“十二五”核准这三处电

站的可能性较小。本次三大内陆核电站具备核岛负挖条件以及彭泽核电增资

的新闻，更多是各地政府和相关参股公司表明对内陆核电的信心，实际意义

可能有限。

目前正在开展前期工作的沿海机组共 21 个，共 2224 万千瓦。加上在

运行机组 1242 万千瓦，在建机组 2705 万千瓦，三者总共 6171 万千瓦。这

一数字与此前预估的 7000 万千瓦目标尚有 900 万千瓦缺口。但根据统计，

几大核电公司在沿海地区实际规划的机组数量众多。其中大部分虽未获得路

条，但已开展一定工作。不少机组甚至完成或正处于可研阶段，初步具备开

展前期工作条件。从历史情况看，机组从获路条至核准一般在 2 年内。这也

就意味着尚未开展前期工作的机组若在 14 年前获得路条，就能在 15 年底前

获得核准，从而在 2020 年形成装机。这一块的储备装机量，弥补 900 万千

瓦的缺口基本不存在问题。因此，内陆电站“十二五”期间的缓建并不会必

然导致核电装机目标低于市场预期。

三大内陆电站实际已完成部分主设备的招标。若暂不核准相关内陆机组，

这部分订单将推迟收入确认甚至取消，从而造成设备制造商部分在手核电订

单的“失效”。与之相对的是，若发改委为了满足设定的装机目标 ( 如 7000

万千瓦 )，将向暂未开展前期工作的沿海机组颁发“路条”以替代内陆机组。

考虑到这些机组目前基本未进行招标，届时将为相关企业带来对应的新增订

单。


海阳核电 2 号机组蒸汽发生器 A 管束支撑板安装完成

2013 年 2 月 7 日，海阳核电二号机组蒸汽发生器 A 完成了全部 10 块蒸

汽发生器管束支撑板 (TSP) 的安装工作。管束支撑板安装工艺复杂、精度高

难度大，是蒸汽发生器整个制造活动中最关键的重大工序之一。

海阳二号机组蒸汽发生器 A 管束支撑板于 1 月 15 日开始安装，共历时

24 天。该关键工序的结束标志着海阳二号机组蒸汽发生器 A 制造活动取得可

喜进展，为推动海阳项目建设进展提供了有力保障。



http://www.china-nea.cn/html/2013-02/25809.html

http://www.cni23.com/Show.asp?cataid=A00430001&id=12536

http://www.cnec5.com/News/NewsView.aspx?id=1742


新闻 110

阳江核电站 2 号机组反应堆压力容器吊装就位

广东阳江核电站 2 号机组反应堆压力容器吊装就位，该反应堆将于明年

开始运行。

中国核建称阳江核电站 2 号机组反应堆压力容器于是 2 月 18 日开始安

装。该公司制定的目标是 2013 年 3 月 15 日之前完成 1080 兆瓦 CPR-1000 机

组的所有重型设备的安装，其中包括 3 个蒸汽发生器。蒸汽发生器于上月

抵达核电站。

中广核有 4个反应堆在建项目，阳江核电站 2号机组是其中之一。1、2、

3、4号机组的建设时间分别为2008年 12月、 2009年、2010年和 2012年底。

1 号机组预计本年末开始发电，其它机组将会延至 2017 年。预计阳江核电站

还有 2个机组建设项目，现在这两个项目已经提交审查。

阳江核电站将由大亚湾核电运营管理公司操作，该公司是由中广核和香

港中电控股有限公司共同建立的。该公司现在负责的项目有大亚湾核电站、

岭澳核电站及岭澳二期核电站。

来源：http://www.cni23.com/

红沿河核电站 1 号机组电源切换试验完成

2 月 17 日晚，红沿河核电站 1 号机组顺利完成了电源切换试验，进一

步验证了 1 号机组电源的可靠性。该试验是红沿河核电站 1 号机组首次并网

发电后的一个重要试验，是调试启动中风险最大的试验之一，涉及系统多，

影响范围广。在调试和生产部门的全面配合下，值内现场操作员提前到达应

急响应区域，做了充分的响应准备；主控操纵员严格执行试验程序，机组相

关参数演变符合预期，有效地控制了机组风险，顺利完成了该项试验。

来源：http://www.cgnpc.com.cn/

海阳核电 2 号机组反应堆压力容器 DVI 接管组焊完成

2 月 25 日，上海核电设备有限公司承制的海阳核电项目 2 号机组反应

堆压力容器 DVI 接管组焊完成，标志着压力容器制造工作向前迈出坚实的一

步。

DVI 接管（Direct Vessel Injection Nozzle）是 AP1000 反应堆压力

容器的重要部件。在事故情况下（包括失去反应堆冷却剂），堆芯补水箱、

安注箱及换料水箱通过管道经 DVI 接管向反应堆紧急注水，冷却堆芯。接管

组焊（4 个进口接管、2 个出口接管及 2 个 DVI 接管）的焊接工作量大，易

发生变形，是反应堆压力容器制造的工艺难点。DVI 接管组焊完成后压力容

器上筒体将与下筒体组对，之后进行 4个进口接管及 2个出口接管的组焊。

公司驻上核监造人员将密切监督后续压力容器进、出口接管的组焊

工作，重点关注接管组焊过程中的防变形问题。

来源：http://www.sdnpc.com/

反应堆压力容器吊装就位来源：CNI23

反应堆压力容器 DVI 接管组焊来源：SDNPC



http://www.sdnpc.com/

111 新闻摘要

捷克共和国

法国电力集团 EDF 努力寻求达到有国家支持的担保价格，以确保在

英国的核电输出量。而这一行动启发了捷克国有电力公司，该公司

正在为泰梅林核电站（未来将建的核电站项目）寻求一个类似的运

作模式。“谈判只是刚刚开始。” 捷克首席财务官 Martin Novak

在本周 2 月 1 日发布的采访中这样告诉彭博社，要得到政治界的

一致支持将需要长时间的磨合期。正如 EDF 失去了英国合作伙伴

Centrica公司一样，捷克也很难找到一个合适的合作伙伴。Novak说：

“我们必须做好自己单干的打算”。与此同时，泰梅林项目的招标

工作正在有序进行中。去年阿海珐被取消竞标资格，今年有资格投

标的公司就只剩下俄国原子能公司和美国西屋电气公司。阿海珐对

捷克取消其资格进行了上诉，但同时也有言论呼吁 1 月 18 日制定一

个条款以保证竞标过程照常进行。

日本

日本经济贸易产业省（METI）提议对电力系统进行大修检查，并建

议从下一个财政年开始将新能源的预算增加一倍。据路透社报道，

这项改革分为三个阶段，最后一个阶段会在 2018-2020 年完成，届

时公共事业单位将会失去电力系统的传输和分配垄断权，新的竞争

机制将会引入电力行业。新的草案呼吁公用事业单位从 3 月份开始

向国家提供剩余的电力以复兴国家电力市场。专家小组现在正在完

善该草案。在第一个阶段，日本将建立国家电网。为了确保稳定的

电力供应和公平竞争，全新的监控机制将会在2015年左右运行。同时，

METI 宣布下一个财政年的四月伊始，新能源行业的预算高达 977 亿

日元—用以实现新能源部署的最大化，而今年预算额仅有 435 亿日

元。风电行业也将得到政府的大力支持，发电工程预算为2.7亿美元，

技术开发（特别是大型离岸风电的技术开发）预算为 1.55 亿美元。

研究开发高性能的太阳能电池领域将获得 1 亿美元，而地热方面将

得到 1.2 亿美元的资金支持。

日本

据日本时报 2 月 10 日报道，日本核监管机构 NRA 开除了一位高层官

员，原因是这位官员涉嫌与地区公共设施和电力公司的高官秘密召

开至少 30 次会议，此举违反了管理规定。NRA 秘书处处长 Tetsuo

Nayuki 私自将一份关于 Tsuruga 抗震情况的分析报告交给了日本原

子能公司（JAPC），这一行为引起了民众的强烈抵触情绪。原因是

该报告尚未公布于众。日本时报称，该事曝光后他就被 NRA 开除了。

据报道，Tetsuo Nayuki 曾经和 JAPC 公司的高官召开了 8 次会议，

和北陆电力公司召开过 7 次会议，与九州电力公司和日本东北电力

公司的高官分别召开了 4 次会议。NRA 禁止本组织的官员单独参与这

种会议。

英国

法国电力集团 EDF 继续与英国能源和气候变化部进行商讨，讨论的

焦点确定位于萨默塞特郡的欣克利角核电站的电力输送的第一个 20

年的执行价格，同时在协商的问题还包括确立政府担保的工程费。

7 月份 George Osbourne 大臣公布了新的计划，即国库将花费 400

亿英镑（即 620 亿美元）投资重要基础设施建设，这个项目是在

政府接受担保之后的 12 个月内开始实施。EDF 财政执行官 Thomas

Piquemal 在 2 月 14 日发表的一篇文章中分析道，“对于像欣克利角

核电站这样的工程来说，这个投资意义重大”。现在 EDF 正在就执

行价格与英国政府进行谈判，如果达成一旦意见，我们可以就可以

制定财政结构，开始寻求合作伙伴。同时，基础设施债务和担保等

问题也会在于英国政府签订的合同中出现。”

美国

上周，参议员 Barbara Boxer （民主派 - 加利福尼亚人士）和

Bernie Sanders （无党派人士 - 佛蒙特州人士）提出遏制温室气体

排放的策略，即征收碳税并且列入立法，这一举措有利于发展核电

和可再生能源。虽然这项提议没有获得党派支持，但是与他们之前

提出的限额交易体系相比，征收碳税相对操作起来更简单。根据法案，

释放一吨二氧化碳或甲烷征收 20美分，没过十年增加 5.6% 的费用。

Boxer 和 Sanders 说，碳税只用于 2900 家排放温室气体的企业，包

括炼油厂，天然气处理厂和煤矿加工厂。本周，从美国总统奥巴马

的国情咨文演讲中得知，他已经催促国会起草立法，全线追随 2003

年 7 月提出的麦凯恩 - 利伯曼限额交易法案。当时，奥巴马是这项

法案的担保人，那时他还只是伊利诺斯州的一个美国参议员。

哈萨克斯坦

2013 年 1 月 13 日，哈萨克斯坦所有就地开采的铀矿都受到暴风的巨

大影响，目前这些铀矿已经正常运转了。2 月 20 日哈萨克斯坦原子

能公司发言人发邮件给 NIW，就民众提出的问题作出回应。公司发言

人 Kristina Podshivalova 说，“铀矿开采之所以中断，是因为损

坏的输电线路，但是事故并没有破坏生产设备。尽管电力故障影响

了铀矿的生产，但是我们还是期待按照合同所约圆满完成工作。”

阿海珐日前透露，旗下子公司 Katco（阿海珐和哈萨克斯坦国家原

子能共同分股）负责的 Tortkuduk 和 Muyunkum 工厂只停工了三天，

因为他们提前准备了柴油发电机。哈萨克斯坦原子能公司的生产量

到底受到暴风多大的影响，现在尚未得出具体结论。“公司财政损

失可能会增加铀的价格。且原子能公司需要资金修复飓风带来的损

失，”Podshivalova写道，“输电线路和员工的宿舍都需要重新修整”。

美国

美国核管理委员会表示将会对美国联合能源集团运行的九哩岬核电

厂和安特吉管理的菲茨帕特里克核电厂增加监管系统，这两个核电

厂均位于纽约的 Scriba。

核管会发言人 Diane Screnci 说，每运行 7000 小时，九哩岬核电厂

菲茨帕特里克核电厂就会意外停电且停电次数超出阈值，因此需要

增加额外监管。核管会声称，核电站年龄和反应堆没有任何关联。

但是瑞士信贷银行本周发布的报告估算截止到 2012 年，美国反应堆

舰队的中断时间持续了 5100 天，比前今年多了 1000—2000 天。银

行称这一情况在 2013 年会有好转。在过去的五年里，舰队的运行费

和维修费以每年平均4.8%的速度增长，目前花费已经达到20亿美元；

这些项目造成了成本膨胀，其中燃料费，资本支出维修费，分别增

加了 3% 和 5%，并仍然保持上涨势头。瑞士信贷银行强调金融界关注

核电厂的运行期限，而运营商更关注的是成本增加及电价下滑。

112Source List

Editorial Source List Rosatom Energy Solution: Engineering Perspective

STATE ATOMIC ENERGY CORPORATION ROSATOM

April 2-3, 2012 Johannesburg, Sandton Convention Center Alexander Kukshinov Head of External Relations, Department of Perspective Projects, Moscow Branch of NIAEP JSC Rosatom Seminar on Russian Nuclear Energy Technologies & Solutions

TECHSNABEXPORT Annual report 2009

TECHSNABEXPORT Annual report 2010

NATIONAL REPORT OF THE RUSSIAN FEDERATION FOR THE SECOND EXTRAORDINARY MEETING OF THE CONTRACTING PARTIES TO THE CONVENTION ON NUCLEAR SAFETY

Росатом Вестник Атомпрома

Арарат, коньяк и Нобель, или Почему молчит армянское радио / вестник атомпрома

rosatom strategy / digest atomprom 06

app construction / digest atomprom 06

official event / digest atomprom

our coverage / digest atomprom

HOBOCTиnews / digest atomprom 04

ЯДЕРНЫЙ ТОПЛИВНЫЙ ЦИКЛ В ФОКУСЕ / www.nuclear.ru

за 2010 год – Росатом

ЯДЕРНЫЙ ТОПЛИВНЫЙ ЦИКЛ В ФОКУСЕ / www.nuclear.ru

ОТКРЫТОЕ АКЦИОНЕРНОЕ ОБЩЕСТВО «АТОМНОЕ И ЭНЕРГЕТИЧЕСКОЕ МАШИНОСТРОЕНИЕ» (ОАО «АТОМЭНЕРГОМАШ») За 2011 год

Nuclear Power Technology Development / Nuclear Power Newsletter, Vol. 10, No. 1, January 2013

TVEL Fuel Company Signed a Package of Contractual Documents with Chinese Corporations JNPC and CNEIC / 03.11.2010 16:41 / Communications and Public Affairs Department of JSC "TVEL"

ОАО «ЦКБМ» намерено поставлять оборудование газовых систем для Тяньваньской АЭС/ 26.12.2012 13:10 / Медиа-центр ОАО «Атомэнергомаш»

Соглашение о строительстве реактора БН-800 в КНР может быть подписано в 2012 году/ 12.10.2011 11:27 / Nuclear.Ru

The III International Nuclear Industry Suppliers’ Forum ATOMEX 2011 opened in Moscow / 07.12.2011 17:03 / Communications Department of ROSATOM

На китайском экспериментальном реакторе CEFR начата загрузка топлива/ 15.06.2010 13:09 / Пресс-служба ОАО «ОКБМ Африкантов»

Russia, China work on advanced nuclear / 12.12.2011 18:42 / World Nuclear News

JSC Atomstroyexport and JNPC signed a contract for construction of Tianwan NPP Phase Two / 23.11.2010 19:28 / Press Service of JSC Atomstroyexport

Tvel to be awarded license to export nuclear fuel to Europe and Armenia / 13.10.2011 15:33 / ARKA News Agency

Sodium coolant arrives at fast reactor / 25.01.2013 13:31 / World Nuclear News

СПбАЭП проинформировал заказчика о ходе выполнения работ попроектированию блоков №3 и №4 Тяньваньской АЭС/ 09.07.2012 13:36 / Группа по связям с общественностью ОАО «СПбАЭП»

"ОКБМ Африкантов" поставит две реакторные установки БН-800 в Китай /14.09.2010 15:44 / НТА Приволжье

113 Source List

НИИАР готов продолжить сотрудничество с китайскими специалистами по быстрым реакторам / 27.07.2010 11:14 / Nuclear.Ru

На сайте форума «АТОМЭКСПО 2011» открыта электронная система назначения встреч / 10.05.2011 17:48 / Nuclear.Ru

Подписано соглашение по проекту сооружения второй очереди АЭС «Чернавода» / 21.10.2011 12:17 / Nuclear.Ru

More than 4,000 people from 53 countries visited ATOMEXPO 2012 International Forum / 08.06.2012 11:16 / Press-srvice of JSC ATOMEXPO

Heavy metal power reactor slated for 2017 / 02.04.2012 14:32 / World Nuclear News

S. Kirienko: Building Innovation for a Safe Nuclear Future / 29.10.2010 12:45 / PowerTec Russia & CIS Magazine

Атомстройэкспорт и JNPC подписали контракт на технический проект второй очереди Тяньваньской АЭС / 27.09.2010 14:00 / Пресс-служба ЗАО «Атомстройэкспорт»

Russian nuclear agency Rosatom plans fast reactors / 05.12.2012 12:17 / Russia Now, supplement to The Telegraph (UK)

A commemoration capsule laying ceremony was held on Belarus NPP construction site / 10.08.2012 11:44 / Communications Department of ROSATOM

Main results of TENEX performance in 2010 / 23.12.2010 18:57 / Press service of JSC "Techsnabexport"

ТВЭЛ подписал пакет контрактных документов с китайскими корпорациями JNPC и CNEIC / 02.11.2010 12:45 / Дирекция по связям с общественностью ОАО «ТВЭЛ»

Прошло российско-китайское совещание по проекту ТАЭС-2 и технологии управления жизненным циклом АЭС / 05.07.2012 18:14 / Пресс-служба объединенной компании ОАО «НИАЭП» - ЗАО «Атомстройэкспорт»

Делегация КНР ознакомилась с производством оборудования для АЭС на Ижорских заводах / 02.03.2011 17:46 / Nuclear.Ru

http://www.world-nuclear.org/info/inf63.html[3/3/13 9:21:40 PM]

$12 billion deal in works with China – if Russia can produce / http://www.bellona.org/news/news_2006/china_deal[3/3/13 9:37:31 PM]

Research of Fast Reactor in-core Fuel Management

China, Russia Strike New Nuclear Power Plant Deal / http://www.novinite.com/view_news.php?id=145807[3/3/13 9:04:39 PM]

China Experimental Fast Reactor (CEFR) / http://www.nti.org/facilities/784/[3/3/13 7:13:54 PM]

China signs up Russian fast reactors / world nuclear news

China, Russia reach consensus on energy cooperation / Updated: 2010-11-23 13:27 / Chinadaily Europe

China, Russia to co-build floating nuclear power plants / 2013-01-11 15:41:00 / SINA.com

China, Russia to Expand Nuclear Cooperation / 03 September 2010 | Issue 4470 Reuters

Criticality for China’s first fast reactor / 23 July 2010 / Nuclear Engineering International

China denies nuclear accident / 27 Jan 2012 / The Telegraph

Chinese fast reactor nears commissioning / 07 April 2009 / world nuclear news

Delegation from Russia Pays visit to CIAE / 2012-08-31 / China Institute of Atomic Energy

Alexander Bychkov, Deputy Director General of International Atomic Energy Agency visited CIAE / 2011-10-27 / China Institute of Atomic Energy

Russian Deputy Prime Minister Visits CEFR / 2011-10-12 / China Institute of Atomic Energy

EPC contract signed for Tianwan Phase II / 18.10.2011 13:14 / World Nuclear News

First concrete pouring started at Tianwan-3 / 27.12.2012 18:11 / Press-service of Rusatom Overseas JSC

114Source List

General Contract on construction Tianwan NPP Phase Two has come into force / 16.09.2011 11:36 / Communications Department of ROSATOM

FAST REACTOR TECHNOLOGY R&D ACTIVITIES IN CHINA / NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.39 NO.3 JUNE 2007

Rosatom-owned company accused of selling shoddy equipment to reactors at home and abroad, pocketing profits / www.bellona.org

Скрепили дружбу бетоном /январь 2013 / POCATOM

Мирный атом в 2013 году: ожидания и прогнозы / POCATOM

Пламя мудрости / POCATOM

Больше денег / POCATOM

Ноу-хау под замком / POCATOM

Russia and China sign protocol of cooperation in construction of Tianwan nuclear plant’s power units 3 & 4 / 06.12.2012 / Strategic Culture Foundation

Russia and China signed the road map for cooperation in nuclear energy / The China Times

Russia and China to cooperate on fast reactor / 21 October 2008 / world nuclear news

Russia assists China develop nuclear power industry / 27-08-2004 / http://bellona.no/bellona.org

Russia might construct more nuclear reactors in China / 24-09-2003 / http://bellona.no/bellona.org

Russia not to pay penalty to China for delays at Tianwan NPP /1 0-11-2004 / http://bellona.no/bellona.org

Russia sings on to build reactors, uranium centrifuges for China / 08-11-2007 / http://bellona.no/bellona.org

Russia to build two more nuclear reactors in China / 04-28-2012 / http://www.defence.pk/forums

Russia to help China build new nuclear reactors at Tianwan plant / 09-12-2012 / http://asian-power.com/

Russia, China eye more energy cooperation / 06-10-2011 / http://english.ruvr.ru

Russia, China to bui ld two new reactors at Tianwan nuclear power plant / 24-03-2010 / ht tp: / /en.r ian.ru/world/20100324/158301104.html

World Nuclear News / 12-12-2011/ http://www.rosatom.ru/en/

Russia, China work on advanced nuclear / 08 December 2011 / world nuclear news

Russian nuclear company to work with China in 3 projects / 2010-09-25/ Chinadaily

Russian-Chinese nuclear cooperation develops despite problems / 07-09-2007 / http://en.rian.ru/analysis/

TVEL Fuel Company Signed a Package of Contractual Documents with Chinese Corporations JNPC and CNEIC / 03-11-2010 / Communications and Public Affairs Department of JSC "TVEL"

Atomenergomash Will Present BN-800 Reactor Project in China / 02-04-2012 / Media Center of OJSC Atomenergomash

TVEL Fuel Company Signed a Package of Contractual Documents with Chinese Corporations JNPC and CNEIC / 03-11-2010 / Communications and Public Affairs Department of JSC "TVEL"

CHINA: AREVA TO SUPPLY EMERGENCY DIESEL GENERATORS TO TIANWAN NUCLEAR POWER STATION / January 15, 2013 / http://www.areva.com/EN/news-9674/china-areva-to-supply

Power Machines manufacture standby power equipment for Tianwan NPP (PRC)

/ 21-12-2011 / http://www.power-m.ru/eng/press/news.aspx?news=15290

田湾核电站汽轮机设计方案通过专家评审 / 2012-10-11 / 哈尔滨汽轮机厂有限责任公司

田湾 3、4 号机组汽轮发电机组设备供货合同成功签订 / http://www.jnpc.com.cn/news_content.asp?articleid=1584

115 Source List

On China’s Commercial Reprocessing Policy / Hui Zhang

Prospect on Chinese Fast Reactor Development and Expectations to MONJU / Xu Mi / China Institute of Atomic Energy

A NUCLEAR MILESTONE IN CHINA / www.alfalaval.com/here

国际合作与开发 / 2012-8-20 / http://www.npic.ac.cn/pg6-gjhz.shtml

2012 中国核电可持续发展高峰论坛召开 / http://news.bjx.com.cn/html/20120829/384021.shtml

中俄总结过去一年核能合作成绩并规划未来核能项目 / http://www.cnnc.com.cn/publish/portal0/tab664/info69045.htm

中俄企业有意拓展阿根廷核电项目 / http://news.bjx.com.cn/html/20121010/393260.shtml

核电厂多国设计评价计划 STC 会议在京举行 / http://news.bjx.com.cn/html/20121017/394870.shtml

双原公司 - 中俄核领域合资公司的典范 / 2012-10-19 / http://realtime.xmuenergy.com/newsdetail.aspx?newsid=106305

中俄核技术应用领域首个合资公司成立 20 周年 / 2012-10-30 / http://realtime.xmuenergy.com/newsdetail.aspx?newsid=106406

中俄签署田湾核电二期项目 / 2012-12-6 / http://news.bjx.com.cn/html/20121206/406234.shtml

俄罗斯将与中国在建造浮动核电站领域开展合作 / 2012-12-6 / http://news.bjx.com.cn/html/20121207/406512.shtml

国家能源局局长刘铁男与俄能源部长签署合作文件 / 2012-12-7 / http://www.china-nea.cn/html/2012-12/25070.html

中俄签署合作建设田湾核电站 ( 二期 ) 议定书 / 2012-12-10 / http://www.cnnc.com.cn/publish/portal0/tab59/info70438.htm

周生贤会见俄罗斯总统助理 / 2012-12-17/ http://www.mep.gov.cn/gzfw/tpk/hbzjpic/bzhd/zsx/201212/t20121214_243754.htm

中俄核电科技研发国际科技合作基地理事会成立 / 2012-12-18 / http://www.cnnc.com.cn/publish/portal0/tab664/info70673.htm

俄将在华开建田湾 3、4 号核电站机组 / 2012-12-20 / http://www.china-nea.cn/html/2012-12/25233.html

俄罗斯重型机械公司代表团参观访问中核能源公司 / 2012-12-21 / http://www.chinergy.com.cn/HomePage/ShowInfo.aspx?Id=478,12

钱智民会见 Rosatom 公司第一副总经理洛克申 / 2012-12-27 / http://www.cnnc.com.cn/publish/portal0/tab664/info70874.htm

俄称中俄将合造游动核电站中国负责建设拖船 / 2013-01-07 / http://www.china-nea.cn/html/2013-01/25441.html

中俄两国在核电站建设上的合作迈向新阶段 / 2013-01-07/ http://www.china-nea.cn/html/2013-01/25451.html

俄中将合建水上核电站拟加大可再生能源利用 / 2013-1-11/ http://news.bjx.com.cn/html/20130111/413013.shtml

俄罗斯原子能集团公司希望与 CIAE 就快堆与研发领域加强合作 / 2013-01-15/ http://www.ciae.ac.cn/newsContent.jsp?RID=52&cid_A=10

116核电词汇

all-weld-metal tension (or tensile)testall-welded frameAllen screwalligatoringallowable allowable loadallowable stressallowanceallowance for fabrication tolerancesalloy steelalloyed steelalmen intensityalmen stripalpha decayalpha emissionalpha emitteralpha radioactivityalpha ratioalpha raysalpha-phase prodcuing (metallurgy)alphanumeric codealterationalternate energy sourcesalternate systemalternating currentalternating current motoralternating slidingalternating stressalternative energy sourcesalternatoraluminous cementambient conditionsambient dose rateambient lightingambient temperatureAmerican standard pipe thread plugammeterammonium diuranateampacityamphoteric metalamplification channelamplifieramplifier relayanaloganalog channelanalog controlleranalog diagramanalog digital converteranalog feedbacj controlanalog input analog instrumentationanalog measurement analog relayanalog signal

全焊接金属拉伸（张拉）试验全焊接框架六角固定螺丝裂痕，龟裂容许的容许载荷容许应力公差，允许量允许制造公差合金刚合金刚almen 强度almen 条带α 衰变α 发射α 发射体α 发射现象α 因子α 射线α 相生产（冶金）字母数字编码修改，改进新能源替换系统交流电流交流电动机交替滑动交变应力新能源交流发电机渗铝水泥环境的状况环境剂量率环境照明环境温度美国标注管道螺纹塞安培计，电流表重铀酸铵载流量两性的金属放大通道放大器放大器继电器模拟量模拟通道，模拟电路模拟控制器模拟图模拟数字转换器，交直流变换器模拟反馈控制模拟量输入模拟测量仪表模拟变量，模拟量测量模拟继电器

核电专业词汇Nuclear GlossaryEnglish Chinese English Chinese

analog variableanalyseranalysis(of data)analysis lineanalyzeranchoranchor baranchor boltanchor channelanchor coneanchor drilling anchor plateanchor pointanchor ring (reactor vessel)anchor rodanchoringanchoring pointangleangle angle beam examinationangle beam probeangle beam transducerangle beam ultrasonic examinationangle check valveangle control valveangle gear driveangle ironangle jointangle of frictionangle of the electron gunangle patternangle poleangle styleangle towerangle valveangular adjustmentangular displacement transducerangular momentumanion bedanion bed demineralizeranion bed ion exchangeranion exchange resinanion exchangeranion resinanion vacanciesanisotropy factorannealedannealingannealing passannealing temperatureannular lightingannulus (containment)annunciated

类比信号，模拟信号分析分析（数据）分析管线分析器锚定固定条地脚螺栓，锚栓固定槽条固定锤钻探固定板固定点加固环（压力壳）支架锚定环固定杆锚定系锚点固定接头，锚定点角倾斜（反义“水平”）倾斜（束）检验斜探头斜传送器横向超声波探伤直角单向阀直角调节阀斜角轴伞齿轮转动角铁角焊缝摩擦角电子枪角度（电子束焊）角型角型支架角的类型斜塔架，倾斜支承架角阀角度调整角位移传送器角动量阴离子床阴离子床除盐装置阴离子交换器阴离子交换树脂阴离子交换器阴离子交换树脂阴离子空位各向异性因子退火的，退火（热处理 )退火的，退火（热处理 )退火合格退火温度环形照明环形空间（安全壳）报警的

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L-3的超级仿真培训系统采用Orchid 仿真技术，为电厂操作人员提供真实的操作环境，帮助他们获得处理任何紧急事故的经验。不管是多复杂，多危险的事故工况，都可以在仿真器上实时逼真地推演，对事故工况提供有效的监视并能对事故工况进行适当的调整。

请点击www.L-3com.com/MAPPS您可以详细地了解我们近40年所积累的核电仿真领域的相关经验，以及我们能如何改变您的现在和未来。

Dynatom_Need for Safety.indd 1 9/12/2012 2:41:01 PM

117 新闻摘要

L-3逼真的仿真技术与安全紧密相连

L-3 MAPPS L-3com.com

L-3的超级仿真培训系统采用Orchid 仿真技术，为电厂操作人员提供真实的操作环境，帮助他们获得处理任何紧急事故的经验。不管是多复杂，多危险的事故工况，都可以在仿真器上实时逼真地推演，对事故工况提供有效的监视并能对事故工况进行适当的调整。

请点击www.L-3com.com/MAPPS您可以详细地了解我们近40年所积累的核电仿真领域的相关经验，以及我们能如何改变您的现在和未来。

Dynatom_Need for Safety.indd 1 9/12/2012 2:41:01 PM