Overview of Gen IV Reactor Systems Development

2

Status by project

3

Generation IV GFR - Summary

• Helium coolant

• Fast neutron spectrum

• High outlet temperature

• Longer term alternative to SFR

+ Transparent coolant

+ High temperature/efficiency

+ Strong Doppler effect

+ Weak void effect

+ Chemically and neutronically inert coolant

+ Zero activation cooant

- Decay heat removal (LOCA)

- High power density

- Low thermal inertia

- High coolant pumping power

• Thermal power 2400 MWth

• Coolant in/out 400°C/850°C• System pressure 70 bar

4

Status of GFR System Cooperation

• GFR System Arrangement signed by Euratom, France,

Switzerland and Japan

• Project Arrangement on “Conceptual Design & Safety”

signed by Euratom, France and Switzerland

• Project Plan was intended updated for 2013-2015 but

this has proved to be difficult because no funding

available for the foreseeable future in Euratom and

Switzerland and only small funds available in France

to support ALLEGRO development.

5

SCWR System Agreement (year of sign.) and Representatives

• Canada (2006) L. Leung, D. Brady

• Euratom (2006) T. Schulenberg, J. Starflinger

• Japan (2006) H. Matsui

• Russia (2011) A. Sedov, A. Churkin

• China (2014) Y.P. Huang, L. Zhang

Projects:

• Thermal-Hydraulics and Safety, TH&S, signed (EU, CA, JP),

RU and CN expressed interest to join

• Materials and Chemistry, M&C, signed (EU, CA, JP),

CN expressed interest to join

• Fuel Qualification Test, FQT, provisional (EU, CA, CN)

• System Integration and Assessment, SI&A, provisional (EU,

CA, JP)

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Project “Thermal-Hydraulics and Safety”

Progress in 2013:

− Canada: 8 deliverables on heat transfer, choking flow, safety systems,

thermal insulation

− Euratom: 8 deliverables on turbulence modelling and heat transfer

− Similar in 2014

Joint benchmark exercise completed 2014

− Flow and heat transfer of supercritical

water in a 7 rod bundle

− Tests by JAEA, Japan

− Blind predictions by 10 organizations from

EU and Canada

− Organized by M. Rohde, TU Delft

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“Thermal-Hydraulics and Safety”, Updated Project Plan

Planned future contributions 2015 to 2019, e.g.

− Heat transfer to supercritical water in tubes, annuli, sub-channels and rod bundles (CA, CN, RF)

− Heat transfer to supercritical CO2 and Freon in tubes, annuli and rod bundles; analysis of fluid-to-fluid scaling laws (CA, CN, EU, RF)

− Pressure loss of supercritical water flow in rod bundles (CN, RF)

− Test of rod cladding ballooning (RF)

− Blow-down experiments with supercritical water (CA, CN, RF)

− Flow instabilities (CA, CN, EU, RF)

− SCWR safety requirements and evaluation (CA, EU, CN, RF)

− System code development (CA, CN)

− CFD and turbulence modelling (CA, CN, EU, RF)

8

Project “Materials and Chemistry”Progress in 2014:

− Canada: total of 18 deliverables

− Euratom: total of 14 deliverables; commissioning tests of in-pile

supercritical water loop in Rez completed

− CA, EU, JP: Round- robin corrosion tests and characterization of

identical alloys; development of Materials Databases in SCW

− CA, EU: Development of coatings and surface modification

Updated project plan 2015 to 2019 under negotiation, e.g.

− Tests of un-irradiated material: corrosion, SCC, creep, effect of coatings and surface modification, ODS-materials (CA, CN, EU)

− Radiolysis and water chemistry: corrosion tests with an in-pile supercritical water loop (EU), supported by modelling (CA), and out-of-pile test (CN)

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Gen IV SFR System Options and Design

Tracks

Loop Pool Small

Modular

PGSFRJSFR SMFR

IHX

DHX

PHTS pump

Reactor core

Steam Generator

AHX Chimney

PDRC piping

In-vessel core catcher

IHTS piping

IHTS pump

IHX

DHX

PHTS pump

Reactor core

Steam Generator

AHX Chimney

PDRC piping

In-vessel core catcher

IHTS piping

IHTS pump

12 .03 m3,1 86 ga l.

PL AN VIEW OF THE CORE

P RIMARYCONT ROL RODS

1m T RAVE L DIST ANCEOF THE CONT ROL RODS

(1 0' -8 ")

T HE RMALSHIE LD

(2 9.5 ")0 .75 m

3 .25 m

Na-COHEAT EXCHANGER

7 m

IHXX-SE CT ION (FLAT TE NED FOR CL ARITY )

(2 3' )

(Ø 7 .5' x 1 2.6 ' LONG)

IHX

2

SE CT ION A - A

No r ma l s o di um le v el

Nor ma l s o di u m le v e l

Sod i um fa u lt ed l ev e l

P um p of f

Sod iu m Le v el

SODI UM DUMP T ANKØ 2.5 m x 3.8 m LONG

CORE BARRE L Ø

26 6 / 2 68 cm(10 4.7 " / 10 5.5 ")

SE CONDARYCONT ROL RODS

CONT ROL

RODS (7 )

PUMP S (2 )ON Ø 1 4 2.5 " B.C.

P LAN VIE W OFIHX AND PUMP S IHX (2)

1 .7m E ACH2

DRACS (2 )0.4 m E ACH2

Prima ry Ves sel I.D.

Gua rd Ves sel I.D.

Ho t P o ol

Co l d Po o l

PRIMARY VESSE L(2 " THICK)

3.5 m(1 1' -8 ")

GUARD VE SSE L(1 " THICK)

1m( 39 .4")

3

T URBINE/GE NERAT ORBUIL DING

E LE VAT OR

(Ø 25 .5' )Ø 7.7 m

Na-A irHEAT E XCHANGE R (2 )

CONTROL

BUILDING

0 1 2 3 10ME TE RS4 5

5 .08 m [1 6.7 FT ]

4.5 7m [15 FT ]

7 m [23 FT ]

1.8 9m [6.2 FT ]

1 2 .7 2m [4 1.7 FT ]

1 4.7 6m [4 8.4 FT ]

1.9 3m [6 .3F T]

.61 m [2 FT]

2.2 9m [ 7.5 FT]

E XHAUST TO VENT ST ACK

ESFR

BN-1200 will be presented by Russia as new Gen-IV SFR design track for

the next SIA meeting

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System Integration & Assessment ProjectObjectives

– Integration of the results of R&D Projects

– Performance of design and safety studies

– Assessment of the SFR System against the goals and criteria set out in the Gen IV Technology Roadmap

Integration RoleSpecific tasks have been developed and refined

– Identify Generation-IV SFR Options» General system options

» Specific design tracks

» Contributed trade studies

– Maintain comprehensive list of R&D needs

– Review Generation-IV SFR Technical Projects

– Unlike the technical Projects, based on synthesis of results produced by other Projects

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Safety and Operation ProjectPartners

– CHINA INSTITUTE OF ATOMIC ENERGY

– COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES

– EUROPEAN ATOMIC ENERGY COMMUNITY

– DEPARTMENT OF ENERGY OF THE UNITED STATES OF AMERICA

– JAPAN ATOMIC ENERGY AGENCY

– KOREA ATOMIC ENERGY RESEARCH INSTITUTE

– STATE ATOMIC ENERGY CORPORATION ROSATOM

Activities in three areas1. Methods, models and codes,

2. Experimental programs and operational experiences

3. Studies of innovative design and safety systems.

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CD & BOP Project Subjects for 2012-2016

(1) In-Service Inspection & Instrumentation (ISI) technology

• Ultrasonic inspection in sodium using different approaches and technologies, codes and

standards (CEA, Euratom, JAEA, KAERI)

(2) Repair experience

• Phénix, Monju, (CEA, JAEA)

(3) Leak Before Break (LBB) Assessment technology

• Creep, fatigue, and creep-fatigue crack initiation & growth evaluation for Mod. 9Cr-1Mo

(Grade 91) steel, Na leak detection by laser spectroscopy (JAEA, KAERI)

(4) Supercritical CO2 Brayton Cycle Energy Conversion

• S-CO2 compressor tests, S-CO2 cycle demonstration tests, Compact heat exchanger tests,

Material oxidation tests in S-CO2, Sodium-CO2 reaction tests, S-CO2 SFR plant dynamic

analyses and control strategy development, Computer code analysis, S-CO2 SFR design study,

Validation of S-CO2 plant dynamic analyses with S-CO2 loop data, Sodium plugging tests

(CEA, DOE, Euratom, JAEA, KAERI)

(5) Steam Generator design and associated safety & instrumentation (since 2011)

• Na/water reaction, thermal-hydraulics, thermal performance, DWT structural evaluation and

heat exchange performance, DWT-SG fabrication (CEA, JAEA, KAERI)

Overview of GACID Conceptual Scheme

MA raw

material

preparationMonju

Fuel

pin

fabri-

cation

Irradiation

test

MA-bearing

MOX fuel

pellets

�Objective: to demonstrate, using Joyo and Monju, that FR’s can transmute MA’s (Np/Am/Cm) and thereby reduce the concerns of HL radioactive wastes and proliferation risks.

�A phased approach in three steps.

�Material properties and irradiation behavior are also studied and investigated.

Step-1

Np/Am pin

irrad. test Joyo

Step-3

Np/Am/Cm

bundle irrad.

test

Monju

(Final Goal)Test fuel

fabrication

Step-2

Np/Am/Cm

pin irrad. test

Monju

Planning

MonjuJoyo�The Project is being conducted by

CEA, USDOE and JAEA as a GIF/SFR Project, covering the initial 5 years since Sep. 27, 2007.

GACID overall schedule

1

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VHTR PMBs

• 4 active VHTR Projects:– Hydrogen Production (HP)

» Chair/co-chair: Francois LE NAOUR (FR) / Sam SUPPIAH (CA)

– Fuel and Fuel Cycle (FFC)

» Chair/co-chair: David PETTI (US) / LIU Bing (CN)

– Materials (MAT)

» Chair: William R. CORWIN (US)

» 3 Working Groups: Metals, Graphite, Ceramics

– Computational Methods Validation and Benchmarks (CMVB) restarted since Oct 2014

» Chair/co-chair: SHI Lei (CN) / Hans GOUGAR (US)

– System Integration and Assessment Project (SIA)

» under discussion (limited resources)

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Development targets

Very High Temperature is not a goal per se

•Two stages for VHTR

– Near-term: He outlet temperatures

700 - 950° C for process steam applications

� prepare for construction and licensing

of a demonstrator/FOAK

– Longer-term: New materials and fuels

should enable higher temperatures up to

above 1000° C;

� bulk H2 from thermochemical

processes

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R&D objectives

• Qualification of TRISO fuel» UO2 and/or UCO fuel

– Fuel cycle: Disposal of fuel and graphite

• Metal, Graphite, Composites» Pressure vessel materials, Components (SG /

IHX), core internals, valves

• H2 Production» HTSE, S-I, Cu-Cl

• Computer tool validation

17

MSR systemMemorandum of

Understanding

effective 6 Oct 2010

JRC ( Euratom ) , CEA ( France )

Russia (Nov 2013)

Japan, China, Korea, US observers

Memorandum of

Understanding

effective 22 Nov 2010

JRC ( Euratom ),

Tokyo Institute of Technology ( Japan )

Russia (Rosatom) joined 18 Jul 2011

US, Korea, China observers

LFR system

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Studied MSR ConceptsMSFR

MOSARTTwo reactor concepts using molten salt are discussed in GIF MSR meetings

– Molten salt reactors, in which the salt is at the same time the fuel and the cooling liquid

» MSR MOU Signatories France and EU work on MSFR (Molten Salt Fast Reactor)

» Russian Federation works on MOSART(Molten Salt Actinide Recycler & Transmuter). Russian Federation joined the Memorandum of Understanding (11/2013)

– Solid fuelled Reactors cooled by molten salt

» USA and China work on FHR (fluoride-salt-cooled high-temperature reactor) concepts and are Observers to the PSSC

FHR

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GIF MSR Project

• A Provisional Project Management Board has been set up

– Two meetings per year where members and observers report on their activities and recent progresses

• The project is devoted to Molten Salt Reactors

– Information is also exchanged on solid fuelled reactors cooled by molten salt

• The various molten salt reactor projects like FHR, MOSART, MSFR, and TMSR have common themes in basic R&D areas, of which the most prominent are:

o liquid salt technology,

o materials behavior,

o the fuel and fuel cycle chemistry and modeling,

o the numerical simulation and safety design aspects of the reactor

20

GIF–LFR REFERENCE SYSTEMS

Three reference systems of GIF–LFR are:

ELFR (600 MWe), BREST (300 MWe), and SSTAR (small size)

11

22

33

44

55

1 - Core

2 - Steam Generator

3 - Pump

4 - Refueling Machine

5 - Reactor Vault

CLOSURE HEAD

CO2 INLET NOZZLE

(1 OF 4)

CO2 OUTLET NOZZLE

(1 OF 8)

Pb-TO-CO2 HEAT EXCHANGER (1 OF 4)

ACTIVE CORE AND FISSION GAS PLENUM

RADIAL REFLECTOR

FLOW DISTRIBUTOR HEAD

FLOW SHROUDGUARD VESSEL

REACTOR VESSEL

CONTROL ROD DRIVES

CONTROL

ROD GUIDE TUBES AND DRIVELINES

THERMAL BAFFLE

ELFR

system for central station

power generation

BREST

system of

intermediate size

SSTAR

system of small size

with long core life

SG

Reactor

Vessel

Safety

Vessel

DHR dip

cooler

FAs

Primary

Pump

21

Status of the main activities: SRP, White Paper, SDC, ToR

• SYSTEM RESEARCH PLAN (SRP):

Substantial revision of SRP was started by mid-2012 and is now completed. Final draft

of SRP has been issued by pSSC and the report is currently being reviewed by EG

• LFR White Paper on safety: Review of White Paper on safety (based on ALFRED as

an example of an LFR to apply ISAM to) was completed by EG. The final version of

the paper has already been published on the GIF web-site by RSWG

• LFR – Safety Design Criteria:

Safety Design Criteria (SDC) for LFR will be developed on the basis of SDC for SFRs

Work is still ongoing, first draft is expected to be available by spring 2015

• GIF–LFR abstract was sent to GIF Symposium held in conjunction with the ICONE23

conference in Japan (May 2015)

• Preparation of draft “Terms of reference for GIF system safety assessment” is

currently ongoing and the draft is expected to be available shortly (by March 2015)

• 2014 Annual report was sent to the GIF Secretariat in the first week of December

• Revision of LFR information on the GIF web-site will be available by spring 2015