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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
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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.
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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)
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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)
15
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
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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)
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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