Upload
others
View
1
Download
0
Embed Size (px)
Citation preview
Futuretech Alert
(TechVision)
Generation IV Nuclear Reactor Technology
D835- TV
April 2016
“Developing Safer and More Reliable Nuclear Power”
2 D835-TV
Contents
Section Slide Numbers
Generation IV Nuclear Reactors 4
Technology Background 5
Key Features of Generation IV Reactors 6
Drivers For Generation IV Reactors Development 7
Challenges for Generation IV Reactors Development 8
Region-wise Technology Development Scenario 9
Key Programs and Innovations in Generation IV Nuclear Reactors 10
Travelling Wave Sodium Cooled Fast Reactors 11
Integral Molten Salt Reactor 12
Next Generation Nuclear Plant 13
Korean Advanced Nuclear Reactors 14
Stable Salt Reactor 15
3 D835-TV
Contents
Section
Slide Numbers
European Sustainable Nuclear Industrial Initiative 16
The Road Ahead 17
Technology Roadmap 18
Appendix 19
Key Patents 20
Key Contacts 23
4
Generation IV Nuclear Reactors
5 D835-TI
Technology Background
Generation IV nuclear reactors are the conceptual reactors which are still in design phase and are expected to be commercialized by
2030. These reactors are expected to improve the power yield from nuclear reactors, safety of the reactors, and the ability to reuse the
existing nuclear waste as fuel. They differ from the previous generation reactors by refraining from using pressurized cooling and heat
transfer systems. They also have been developed to minimize the use of water as coolant in reactors to enable better thermal recovery
at reduced pressure.
In 2002, The Generation IV International Forum (GIF) classified six
nuclear reactors as generation IV technologies. These reactors can
be classified into two broad categories:
• Thermal reactors
• Fast reactors
Thermal reactors use slow or low velocity thermal neutrons to enable
fission. They use moderators to slow down the neutrons such as
graphite.
Fast reactors do not need moderators to control the velocity of the
neutrons.
Of the six chosen technologies VHTR is considered as pure thermal
reactor. The Supercritical Water Cooled reactor and Molten Slat
reactor may be used as either thermal or fast neutron reactors.
The reactor types being considered are
• Very high temperature reactor ( Thermal)
• Molten salt reactor (Thermal/ Fast)
• Supercritical water cooled reactor (Thermal/ Fast)
• Gas cooled fast reactor (Fast)
• Sodium cooled fast reactor (SCFR)/sodium fast reactor
(SFR) (Fast)
• Lead cooled fast reactor (LCFR)/lead fast reactor (LFR)
(Fast)
The main aim behind creating these reactors is to enable closed
nuclear fuel cycle where the spent nuclear fuel is reprocessed
and used again.
Nuclear Fuel Cycle:
• Nuclear fuel cycle defines the stages through which
the fuel goes through, from mining to disposing the
used fuel.
• The spent fuel may be reprocessed and reused
(closed cycle) or may be disposed after a single use
(open cycle).
• Reprocessing involves getting fissile materials from
the spent fuel materials.
• One advantage of reprocessing is that it reduces the
time the refuse takes for decaying to harmlessness.
• Employing closed cycle makes nuclear energy as a
renewable source and also makes the process
safer and cost effective.
• Most of the reactor models selected by the GIF are
based on closed cycle operation.
6 D835-TI
Key Features of Generation IV Reactors
Gas Cooled Fast Reactors:
• They are high temperature gas cooled reactors and employ closed
fuel cycle.
• They bring in the advantages of fast reactors and high temperature
reactors.
• Disadvantages include rapid heating up of core in the absence of
forced cooling.
• The reactor is expected to be put to demonstration by 2020.
Generation IV Fast Reactors Generation IV Thermal Reactors
Lead Cooled Fast Reactors:
• These fast neutron reactors will employ lead or alloys such as lead-
bismuth eutectic as coolant.
• Both lead and bismuth have low neutron absorbing capability making
them ideal for the usage.
• Operating temperatures above 800 degrees C enable the
thermochemical production of hydrogen although the corrosive
properties of lead at these temperatures must be dealt with. Molten Salt Reactors:
Two variants of this reactor are available.
• In variant one, the fissile material itself is dissolved in the
molten fluoride salt and circulated through channels
made of graphite.
• In the second one, the molten salt acts as the coolant
alone and the fuel is in solid form, similar to those used
in VHTRs.
• The molten salt reactor may be either fast or thermal based on
the core design.
Sodium Cooled Fast Reactor:
• Molten sodium is used as the coolant enabling a system with low
coolant pressure.
• This also helps achieving high power density and electricity
generation is enable through a secondary coolant circuit.
• Operation temperatures are around 500 degrees C to 550 degrees C.
Supercritical Water Cooled Reactor:
• The reactor operates at very high temperature and pressure
values well above the critical point of water.
• Supercritical water (25 megapascal and 500 degrees C to 600
degrees C) is used to drive the turbine associated with
electrical generation.
• Reactor may be thermal reactor or fast neutron one based on
the core design.
Very High Temperature Reactor (VHTR):
• This is a high temperature reactor with gas cooled core.
Graphite is used as moderators and helium can be used as the
coolant.
• Can be used to generate both heat and electricity with high
efficiency.
• One of the safest reactor models to be developed.
7 D681-TI
Source: Frost & Sullivan
The need for cleaner and
a sustainable source of
power
Safer than the previous
generation reactors
Resistance against
proliferation
Need to adopt safer
nuclear technologies
Better power density and
generation
Generation IV nuclear reactors are mostly fast neutron reactors. The fast neutrons used are capable of splitting the
Uranium 238 atoms, which make up more than 99% of the fuel used. The generation IV reactors thus enable efficient
fuel usage and also makes the fuel disposal less frequent due to the reuse of the U-238 atoms.
Using reprocessed and recycled spent fuel reduces the amount of radioactive waste disposed from the reactors to a
great extent. Thus the generated waste remains radioactive for a shorter period of time. These time periods are much
lesser than how long the wastes from existing nuclear plants and technologies remain radioactive.
These reactors enable reprocessing of the spent fuel to a great extent. Almost all the generation IV reactors can be
powered and run by using the recovered and reprocessed actinides and the spent fuel matrices. This makes them
more efficient and cost effective and also enhances the life of the plant.
The need for safer and more efficient reactors is an essential factor that can determine the future of nuclear power
this point forward. With most countries planning to reduce their dependence on nuclear power a better and safer
reactor may change the outlook aiding the adoption rate considerably.
The Generation IV nuclear reactions can generate more power than the contemporary technologies. This can be
attributed their ability to use the Uranium reserves much efficiently than the slow neutron reactors.
Drivers For Generation IV Reactors Development
8 D681-TI
Source: Frost & Sullivan
Global outlook toward
nuclear power
Maturity level of
technologies
Cost of development
Adoption technologies
deployable in the near
term
Availability of Cost-
effective renewable
sources
With recent meltdowns in Japan, the general public is apprehensive toward nuclear power. This apprehension will be
one major barrier authorities will be facing in the future while deploying these technologies. Hence, creating
awareness among the people regarding the benefits and safety of generation IV reactors has become highly
necessary.
The technologies are still under development and actual results are yet to be seen. Though there have been some
demonstrations about their capability, the actual products are yet to developed and the proposed time frame for the
same is between 2020 to 2030. Long time frames could delay adoption of these technologies.
Governments are more interested in encouraging research in energy solutions those will be commercially available
within 2 to 5 years. Such a funding attitude is seen in most developing countries toward funding researches related to
technologies that will not be commercialized in the near future.
Research to develop renewable energy solutions especially solar cells is yielding better results and newer products
with better efficiency. The funding demanded by the research is also much less when compared to Generation IV
reactors.
Challenges for Generation IV Reactors Development
Genration IV reactors require a lot of funding for research, development, and deployment. This could be prohibitively
high for developing countries, thereby preventing active participation from them.
9 D835-TI
Asia
• Countries such as Russia,
China, and South Korea
are interested in
developing Generation IV
reactors.
• China is developing
‘sodium cooled fast
reactors’ and has also
announced plans to
establish ‘supercritical
water cooled reactors’ by
the mid 2020s.
• South Korea has exhibited
interest in electro refining
and fuel reprocessing.
• It is also involved in
developing two different
Generation IV reactors.
• Institutions such as
Rosatom of Russia,
Korean Atomic Energy
Research Institute (KAERI)
are involved in developing
Generation IV reactors and
related technologies.
Region-wise Technology Development Scenario
Europe:
• European Union has a number reactor of programs
announced by governments.
• French Alternative Energies and Atomic Energy
Commission has announced the Advanced Sodium
Technological Reactor for Industrial Demonstration
(ASTRID) program to develop ‘sodium cooled fast
breeder reactors.’
• Belgian Nuclear Research Center has been working on
the Multi-purpose hYbrid Research Reactor for High-
tech Applications (MYRRHA), which is a lead cooled
fast reactor.
North America
• North America has the most
number of companies involved in
developing generator IV reactors.
• Government participation to
develop generation IV reactors
also is very high in the US.
• The US Department of Energy
(DOE) has announced $6 million
funding each to Southern
Company Services and X-
energy to develop advanced
nuclear reactor solutions such as
molten chloride fast reactor.
• DOE has also initiated a number
of programs such as Advanced
Reactor Concepts (ARC), and
Advanced Small Modular Reactor
(aSMR) program to develop
Generation IV reactors and
technologies aiding their adoption.
• Companies such as Transatomic
Power USA, Terrestrial Energy
Canada are involved.
10
Key Programs and Innovations in Generation IV
Nuclear Reactors
11 D835-TI
• TerraPower projects its travelling wave reactor technology as the most secure and the most proliferation resistive among
the available Generation IV technologies. The TWR technology is considered safe as it does not require the spent fuel to
undergo any reprocessing and enrichment processes, bringing down the chances for proliferation.
• The company has claimed that their TWR can enable its users to achieve 50 fold gain with respect to fuel efficiency and
usage.
• Converts the depleted uranium to usable fuel as the operation continues, making the process sustainable in true sense.
This also increases the resource efficiency and availability.
• TerraPower has partnered with Kobe Steel Ltd., Japan, to develop a steel alloy, which will be used in packaging of
materials, ducts, and tubes in reactors.
• TerraPower has partnered with the Scientific Research Institute of Atomic Reactors of Russia for establishing an
irradiation fuel program for the development of TWR. It has also partnered with Ion Beam Laboratory at the University of
Michigan to infuse new features to the HT-9 steel alloy used in fast breed reactors.
• The company aims at developing a 600 megawatt prototype between 2025 to 2030.
• Terra Power is a Washington-based nuclear reactor company that is involved in developing a sodium-cooled fast reactor. It is
developing the reactor based on the travelling wave reactor design.
• The company was started in 2008 and the technology has already attracted investments and partnerships fro around the globe.
International partners include Japan’s Kobe Steel, Ltd., Scientific Research Institute of Atomic Reactors and Rosatom, Russia.
These partners have aided the development of associated technologies such as clamps and irradiation measurement.
Travelling Wave Reactor (TWR)
• TerraPower is developing metallic nuclear fuel extrusions for its TWR reactor together with Idaho National Laboratory
(INL). These fuel extrusions are currently under testing in the advanced test reactor at INL.
• It has already manufactured the full sized test assembly of TWR by partnering with AREVA Federal Services.
Travelling Wave Sodium Cooled Fast Reactors
12 D835-TI
• The fuel used in the IMSR is in liquid form, which improves the safety of operation of the reactor as there will no meltdown.
• The developed solution does not use pressurized component or water as the fuel itself acts as the coolant.
• Operates at atmospheric pressure unlike conventional reactors that operate at a pressure of 160 atmospheres of pressure.
• Much better fuel recycling is viable when compared to reactors using solid fissile material.
• No centralized fuel reprocessing is required to remove the fissile waste generated as IMSR enables continuous removal.
• IMSR is considered to be six times more efficient than conventional nuclear reactors, thanks to its ability to remove fissile
wastes continuously with minimal effort.
• IMSR is expected to operate at 700 degrees C providing heat for various industrial applications.
• The reactor requires low enriched uranium as it requires less enrichment than conventional reactors.
• The IMSR differentiates itself from the other molten salt reactors by using low or slightly enriched liquid uranium cycle
instead of thorium cycle.
• This reduces the proliferation risks associated with thorium cycle as it requires highly enriched uranium additives.
Integral Molten Salt Reactor
• Terrestrial Energy of Ontario, Canada, is involved in developing a safe and reliable integral molten salt reactor (IMSR).
• It has developed the reactor based on the first variant of the molten salt reactor where the fissile material itself is dissolved in a
molten fluoride salt and used to power the reactor.
• This is considered to be a safer nuclear technology than the contemporary ones using solid fuels.
Integral Molten Salt Reactor
Terrestrial Energy established a partnership with Oak Ridge National Laboratory (ORNL), USA, to take its reactor design to
the next stage. This collaboration is expected to help Terrestrial Energy to arrive at the parameters for concept and start
developing the engineering blueprint for the prototype. The blueprint is expected to be developed by the end of 2016.
13 D835-TI
• The program sponsored and funded various collaborative efforts between universities, research entities, and industries to
develop safe, gas cooled reactors in the United States.
• The three main bodies involved are Idaho National Laboratory (INL), Department of Energy, and NGNP Industrial Alliance
• The main areas of the research focused are:
• Cost effectiveness
• Applicability
• Efficiency
• Safety and accident tolerance
• It was intended to develop a reactor with a thermal output capacity of 400 to 600 MW with a coolant output temperature of
850 to 900 degrees C.
• Other targets include production of hydrogen using the high temperatures.
• The fissile fuel and the fuel form for the VHTR is yet to be selected and the alliance expects to develop and operate an
prototype by 2021.
• The cost of the projects has been estimated to be around $4 billion.
Next Generation Nuclear Plant Program
• The Next Generation Nuclear Plant (NGNP) program is supported by the Office of Advanced Reactor Technologies (ART) of the
US DOE. This program aims at funding research and development of advanced generation IV reactor technologies.
• It was established to measure the technical and commercial viability of high temperature gas cooled reactors. These reactors can
supply electricity and high quality process heat for industries.
Facilitating Collaborations To Develop Very High Temperature Reactors
• In 2012, INL approved Areva prismatic steam-cycle high-temperature gas-cooled reactor (SC-HTGR) design as the optimal one for
the high temperature reactor prototype. This was chosen over the other two models, gas-turbine modular helium reactor (GT-MHR)
of General Atomics, USA and the conceptual configurations based on the pebble bed modular reactor (PBMR) submitted by
Westinghouse Electric Company LLC, USA.
14 D835-TI
Kalimer-600
• It is based on KAERI’s sodium cooled fast reactor concept that was developed to meet the effective utilization of resources
and reduce nuclear waste.
• Currently, Waveguide sensor visualization technology is being developed by KAERI to analyze and inspect the interiors of
the reactor and the various sub-assemblies.
• It has been designed to have a electrical and thermal output of 600 MWe and approximately 1500 MWth respectively.
Very High Temperature Reactor
• The VHTR is considered as a source of thermal energy and hydrogen rather than as a source of electricity.
• The KAERI aims to achieve generation of hydrogen and industrial grade heat by attaining reactor temperatures of up to
900 degrees C.
• Other targets include development of high temperature corrosion resistant materials for reactors, refractory coated particle
fuel, and a thermochemical hydrogen generation technique.
Very High Temperature Reactors (VHTR)
• Korean Atomic Energy Research Institute (KAERI) of Korea, is developing two generation IV reactors—Kalimer600 and a very
high temperature reactor (VHTR).
• It is interested in developing nuclear power plants that meet these criteria; effective utilization of resources, minimization of waste
produced; reduced impact on environment; and improved competitiveness in terms of economics, safety, and reliability.
Nuclear Reactors for Heat and Hydrogen production
• KAERI has plans to start with the demonstration phase of the VHTR reactor by 2020 and commercialize the reactor by
2025.
• It plans to commercialize the advanced sodium cooled fast reactor by 2030.
15 D835-TI
• The tubes holding the fuel salts are bundled together to form the fuel assemblies, which act as the reactor modules.
• The tank in which the assembly is placed is filled with the molten salt coolant.
• The molten salt coolant has the following characteristics:
• Not pressurized
• Does not react violently with air and water like the molten sodium coolant
• A secondary molten salt coolant arrangement is used to draw all the heat from the assembly to power generation.
• Coolant refueling is done by moving the fuel rod assembly out of the core and changing the molten salt coolant. This is
simpler than conventional methods.
• Further cooling of the reactor is enabled by natural flow of cold air.
• No high pressure systems are used making the construction cost effective and safer.
• Two models have been developed based on the type of fuel that can be used along with molten salt coolant.
Stable Salt Reactor
• Moletx Energy LLP of London has developed a reactor that is based on the second model of the molten salt reactors.
• The molten fuel salt mixture is held stable in vented tubes instead of being circulated.
• This technology has been patented globally and is expected to simplify the nuclear power generation process.
Non Circulating Molten Salt Reactor
The stable salt reactors are under construction and can be modeled to generate power from 150 to 1500 MWe. They can
be powered by low enriched uranium or by radioactive waste (such as actinides and plutonium) produced by conventional
reactors.
16 D835-TI
ESNII
• ESNII has launched a number of projects in Europe including ASTRID and MYRRHA. One of the main goals of ESNII is
to complete and put these two projects into operational phase before 2025.
• ASTRID is a sodium fast reactor and MYRRHA is a flexible fast irradiation facility.
• Other programs of ESNII include
• Advanced Lead Fast Reactor European Demonstrator (ALFRED) a LFR demonstrator project to be constructed
by 2020. The National Agency for New Technologies, Energy and the Environment (ENEA) of Italy and Ansaldo
Nucleare of Italy and Nuclear Research Institute (Institutul de Cercetari Nucleare, ICN) of Romania are involved in
the construction of the ALFRED reactor.
ESNII+
• ESNII+ project was started in September 2013 and will be operational until September 2017.
• It is a preparatory phase project for supporting ESNII and preparing ESNII for the technical and economic challenges
for the period beyond 2020.
• ESNII+ will develop has 9 different work packages for guiding ESNII designed to strategically guide ESNII to complete the
research and development programs.
European Sustainable Nuclear Industrial Initiative
• The European Sustainable Nuclear Industrial Initiative (ESNII) was launched by the European Commission at the SET-Plan
Conference, Brussels, in 2010.
• The ESNII is considered to be one of the three main pillars of Sustainable Nuclear Energy Technology Platform (SNETP) of the
European Union.
Pillars of European Nuclear Research
ESNII aims at completing the Allegra and the MYRRHA projects first as they have been operational for long. ESNII will also
ably support SNETP to develop and complete similar nuclear research programs.
17
The Road Ahead
18 D835-TI
2018
Operation of scaled up Chinese HTR 10 plant.
Development of protypes of VHT reactors with
700 to 900 degrees C outlet temperature. 2020
Demonstration of molten salt and
sodium-based prototypes.
Development of conceptual designs
for Supercritical Water Cooled
Reactor
2025
2022
2028
Commercial scale up of molten salt
and sodium-based reactors.
Development of prototypes for the
VHTR with 1000 degrees C outlet
temperature. Realization of other generation IV
technologies and development of
prototypes.
Development of prototypes of
molten sodium- and molten
salt-based reactor.
The generation IV technologies are still in concenptual stage. Some reactors have reached pilot stage. The reoadmap describes what
evolution colud be expected and how long will it take to see the actual deployment of reactors. Based on the existing scenario it can be
evaluated that these demostrator plants based on these reactors can be expected between 2025 to 2030.
Technology Roadmap
19 D835-TI
Appendix
20 D835-TI
Key Patents
Patent Number Title Issue/Publication Date Applicants/Assignee
GB 2508537 A
A molten salt fission
reactor June 4, 2014 Scott Ian Richard
Abstract: A nuclear fission reactor is disclosed comprising a core, a pool of coolant liquid, and a heat exchanger 103. The core
comprises an array of hollow tubes 102 which contain molten salts of fissile isotopes, the tube array being at least partly immersed in the
tank of coolant liquid 101. The tube array comprises a critical region, where the density of the fissile isotopes during operation of the
reactor is sufficient to cause a self-sustaining fission reaction. Heat transfer from the molten salts of fissile isotopes to the exterior of the
tubes is achieved by any one or more of natural convection of the molten salts, mechanical stirring of the molten salts, boiling of the
molten salt, and oscillating fuel salt flow within the tubes. The molten salts of fissile isotopes are contained entirely within the tubes during
operation of the reactor.
US 2009/0252277 A1
Upper plenum structure
of cooled pressure
vessel for prismatic
very high temperature
reactor
October 8, 2009
Korea Atomic Energy Research
Institute
Korea Hydro & Nuclear Power
Co.
Abstract: An upper plenum structure of a cooled pressure vessel for a prismatic very high temperature reactor which secures a space for
coolant to supply to a core and also supports an upper reflector located inside a graphite structure on top of the core. The upper plenum
structure includes a cavity structure where the coolant goes down in the upper plenum structure, a plurality of upper reflector supports
formed with the cavity and supporting the upper reflector located on top thereof, and a plurality of coolant distributing blocks. Each of the
coolant distributing blocks is coupled with a bottom portion of a respective one of the upper reflector supports and is located on top of the
core in order to distribute the coolant collected in a cavity, formed by the upper reflector support, to the core. The coolant distributing
blocks cooperate with the upper reflector supports to define the cavity structure.
21 D835-TI
Key Patents (continued)
Patent Number Title Issue/Publication Date Applicants/Assignee
WO 2015/094450 A9 Molten salt reactor October 22, 2015 Transatomic Power Corp
Abstract: A molten salt reactor includes: a fluoride fuel salt; and a metal hydride moderator.
WO 2015/038922 A1
Hybrid molten-salt
reactor with energetic
neutron source
March 19, 2015 Woolley Robert Daniel
Abstract: In an embodiment, a hybrid molten salt reactor includes a source of energetic neutrons, the energetic neutrons having a typical
energy per neutron of 14 MeV or greater, a critical molten salt reactor, and a molten salt comprising a dissolved mixture of fissile actinides
and fertile actinides. The molten salt circulates in a loop through the reactor vessel and around the source of energetic neutrons. The
fissile actinides and fertile actinides sustain an exothermic nuclear reaction in which the actinides are irradiated by the energetic neutrons,
the energetic neutrons inducing subcritical nuclear fission, and undergo critical nuclear fission when circulating through the critical molten
salt reactor. A portion of the daughter neutrons generated by nuclear reactions are captured by the fertile actinides in the molten salt and
induce transmutation of the fertile actinides into fissile actinides and sustain critical fission chain reactions in the molten salt reactor.
US 2011/0294083 A1 Molten salt treatment
system and process December 1, 2011 Tate & Lyle Technology Limited
Abstract
A molten salt treatment system and process can include one or more tubular conduits flowably connected to a molten salt reactor, the
tubular conduit containing concentrically within it a pipe or a shaft separated by an annular space therebetween, and one or more gas
sources connected to feed gas into the annular space. The system may include a scrubbing device flowably connected to a molten salt
reactor off-gas outlet to receive an off-gas, a first heating device configured to heat the effluent from the scrubbing device, and a filtering
device flowably connected to receive the effluent from the heating device. An overflow conduit may be flowably connected to a molten salt
reactor overflow outlet to receive molten salt therefrom and discharge the molten salt to a salt recovery vessel, and a blower or other gas
mover may be connected to the molten salt reactor and the recovery vessel to prevent backflow of cold gases through the overflow outlet
to the molten salt reactor.
22 D835-TI
Key Patents (continued)
Title Patent Number Issue/Publication Date Applicants/Assignee
Reactor system with a lead-cooled fast
reactor WO 2015/115930 A1 August 6, 2015
KUBINTSEV, Boris Borisovich;
(RU).
Leonov, Viktor Nikolaevich; (Ru).
Lopatkin, Aleksandr Viktorovich;
(Ru).
Chernobrovkin, Yuriy Vasilievich;
(Ru)
Abstract : The invention relates to nuclear technology and is intended for use in power-generating systems with a fast reactor cooled by
a liquid-metal coolant which is primarily in the form of molten lead or an alloy thereof. The problem addressed by the invention consists in
reducing the specific volume of lead coolant per unit of power of the reactor and in increasing the safety of the reactor. The system
comprises a reactor cavity (1) with an upper cover (2), which is arranged in the reactor cavity (1) with an active zone (4), steam
generators (5), circulation pumps (7), circulation conduits (8) and (9), actuating mechanism systems and devices for starting up, operating
and shutting down the reactor system, wherein the steam generators (5) are in the form of tubular heat exchangers in which the lead
coolant (10) flows within pipes, while the water steam flows in a space between the pipes, the steam generators (5) are arranged in
separate boxes (6) and communicate with the reactor cavity (1) by means of circulation conduits for raising (8) and discharging (9) the
lead coolant (10), the steam generators (5) and a large portion of the circulation conduits (8) and (9) are arranged higher than the level of
the lead coolant (10) in the reactor cavity (1), and the circulation pumps (7) are arranged in the reactor cavity (1) on the circulation
conduits (8) and (9) for raising the "hot" lead coolant, and a technical means (13) is provided for ensuring intrinsic circulation of the lead
coolant (10) through the active zone (4) of the reactor when the circulation pumps (7) are switched off.
23 D835-TI
Key Contacts
Leslie Dewan PhD, CEO, Transatomic Power, One Broadway, 14th Floor, Cambridge, MA 02142. E-mail:
[email protected] Phone: +1-617-470-3847. URL: http://www.transatomicpower.com/
Nicholas Touran, Reactor Physicist, TerraPower, LLC, 330 120th Ave NE, Suite 100, Bellevue, WA 98005. E-mail:
[email protected]. Phone: +1-425-324-2888. URL: http://terrapower.com/
David Hill PhD, Director, Terrestrial Energy Inc., 2275 Upper Middle Road East, Suite 102,Oakville, ON, L6H 0C3, Canada.
Phone: +1 (905) 766-3770 E-mail: [email protected] URL: http://terrestrialenergy.com/
Timothy Abram, Professor in Nuclear Fuel Technology, Scientific Advisor, Moltex Energy LLP, 6th Floor, Remo House, 310-
312 Regent St., London W1B 3BS. Phone: +44 07730 052564 E-mail: [email protected] URL:
http://www.moltexenergy.com/