Development and World-Wide
Cooperation within the GIF
Hark Rho Kim
INPRO Dialogue Forum on Generation IV Nuclear Energy Systems
IAEA Headquarters, Vienna
13-15 April 2016
2INPRO DF, 13-15 April 2016
I. Overview of GIF
II. Current R&D Status of Six Reactor Systems
III. Methodology Working Groups and TFs
IV. Plan for International Cooperation
V. Conclusion
Contents
3INPRO DF, 13-15 April 2016
I. Overview of GIF
II. Current R&D Status of Six Reactor Systems
III. Methodology Working Groups and TFs
IV. Plan for International Cooperation
V. Conclusion
4INPRO DF, 13-15 April 2016
� The GIF was founded in July 2001 as a co-operative international
endeavor to carry out the R&D needed to establish the
feasibility and performance capabilities of the next generation
nuclear energy systems
� Gen IV concepts defined via technology goals and legal
framework
� Thirteen Members signed its founding document,
the GIF Charter, which was first signed in July 2001 and
extended in July 2011
� The technology goals (sustainability, safety, economics,
PRPP) provided the basis for identifying and selecting six
nuclear energy systems for further development
� Technology Roadmap 2002 was updated to additional 10
years in Jan. 2014
� Framework Agreement (FA) was extended to additional 10
years in Feb. 2015
About GIF
5INPRO DF, 13-15 April 2016
� Sustainability
�Secure long term fuel supply
�Minimize waste and long term stewardship burden
� Safety & Reliability
�Excel in safety and reliability
�Keep very low likelihood and degree of core damage
�Eliminate need for offsite emergency response
� Economics
�Maintain life cycle cost advantage over other energy
sources
�Reduce financial risk comparable to other energy projects
� Proliferation Resistance & Physical Protection
�Prevent unattractive materials diversion pathway
�Enhance physical protection against terrorism
GIF Technology Goals
6INPRO DF, 13-15 April 2016
Canada China France Japan Korea Russia
South
Africa Swiss USA EU
SFR ● ● ● ● ● ● ●
VHTR ● ● ● ● ● ● ●
LFR* ● ● ● ●
SCWR ● ● ● ● ●
GFR ● ● ●
MSR* ● ● ● ●
*All activities, except LFR and MSR, are carried out based on the system arrangement.
The activities of LFR and MSR are carried out based on Memoranda of Understanding.
Argentina Brazil UK
are also members as non-active member.
Membership and System Development
7INPRO DF, 13-15 April 2016
Safety and Operation (SO)
System Steering
Committee (SSC)
Methodology Working
Groups (MWG)
SFR
SCWR
Economic Modeling Working
Groups (EMWG)
Proliferation Resistance and Physical Protection Working Groups (PRPPWG)
Risk and Safety Working
Groups (RSWG)
Advanced Fuel (AF)
Project Management Board (PMB)
Computational Methods Validation and Benchmarking (CMVB)
Thermal-Hydraulics & Safety (TH&S)
Global Actinide Cycle Int. Demonstration (GACID)
Component Design and Balance-O-Plant (CDBOP)
System Integration and Assessment (SI&A)
Hydrogen Production (HP)
Fuel and Fuel Cycle (FFC)
Materials (MAT)
Materials and Chemistry (M&C)
GFR
LFR
MSR
Conceptual Design and Safety (CD&S)
Fuel and Core Materials (FCM)
already set up
under preparation or discussion
VHTR
System Integration and Assessment (SI&A)
Task Force (TF)
Safety design criteria (SDC)
Education and Training (E&T)
Sustainability
R&D Projects, Methodology WG and Task Force
8INPRO DF, 13-15 April 2016
� Depending on their respective degrees of technical maturity, the
Generation IV systems are expected to become available for
commercial introduction in the period around 2030 or beyond.
� The path from current nuclear systems to Generation IV systems is
described in the technology roadmap update:
www.gen-4.org/gif/upload/docs/application/pdf/2014-03/gif-tru2014.pdf
Updating Technology Roadmap
9INPRO DF, 13-15 April 2016
I. Overview of GIF
II. Current R&D Status of Six Reactor Systems
III. Methodology Working Groups and TFs
IV. Plan for International Cooperation
V. Conclusion
10INPRO DF, 13-15 April 2016
550°°°° C
� Started in Feb. 2006
– China, EU, France, Japan,
Korea, Russia, USA
� Integral part of the closed fuel
cycle
– Can either burn actinides or
breed fissile material
� System options
– Loop, pool, small modular
� R&D focus
– Analyses and experiments that
demonstrate safety approaches
– Development of High burn-up
minor actinide bearing fuels
– Development of advanced
components and energy
conversion systems
500 ∼∼∼∼ 550℃℃℃℃
Sodium-cooled Fast Reactor (SFR)
11INPRO DF, 13-15 April 2016
� Large past experience + Several Demonstrator projects either in
Operation/Construction* or at Design stage**:
Performance Phase: Will be in demonstration phase around 2022
in *China, *Japan**, *Russia**,
France**, Korea** +
India(outside GIF)
SFR : Current Phase
� Designs being developed
– CFR600 (China)
– ASTRID (France)
– JSFR (Japan)
– PGSFR (Korea)
– BN-1200 (Russia)
� Operation/Construction
– CEFR (China)
– JOYO, MONJU (Japan)
– BOR-60, BN-600, BN-800
(Russia)
– FBTR, PFBR (India)
Loop Pool Small Modular
KALIMERJSFR AFR-100
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 m3,186 gal .
P LAN VIEW OF THE CORE
PRIMARYCONTROL RODS
1m TRAVEL DISTANCEOF THE CONTROL RODS
( 10 '- 8")
THERMALSHIEL D
(29 .5")0 .75m
3.25m
Na-CO
HEAT EXCHANGER
7m
IHXX-SECT ION (F LATTENED FOR CLARITY )
(23 ')
(Ø 7 .5 ' x 12 .6' LONG)
IHX
2
SECT ION A - A
No rm al s o di um le v e l
No r ma l s o di um l ev e l
So d ium fa ul te d l ev e l
P ump o f fSo d ium L e v el
SODIUM DUM P TANKØ 2.5 m x 3 .8 m LONG
CORE BARREL Ø266 / 268 cm(104.7" / 105 .5")
SECONDARYCONTROL RODS
CONTROL
RODS (7 )
PUMPS (2 )
ON Ø 142 .5" B.C.
P LAN VIEW OFIHX AND PUM PS IHX (2)
1 .7m EACH2
DRACS (2 )0.4m EACH2
Prima ry Ve sse l I.D.
Gua rd Ve sse l I.D.
Ho t P oo l
Co ld P o o l
PRIMARY VESSEL(2" THICK)
3 .5m( 11 '- 8")
GUARD VESSEL(1" THICK)
1m(39 .4")
3
TURBINE/ GENERATORBUIL DING
ELEVATOR
(Ø 25 .5 ')Ø 7.7m
Na -AirHEAT EXCHANGER (2 )
CONTROLBUIL DING
0 1 2 3 10METERS4 5
5 .08m
[16.7FT ]
4 .57m [15FT ]
7m [23F T]
1 .89m [6 .2F T]
12.72m [41.7FT ]
14 .76m [48.4FT ]
1 .93m
[6 .3F T]
.61m [2F T]
2 .29m [7.5FT ]
EXHAUST TO VENT STACK
ESFR
12INPRO DF, 13-15 April 2016
�Advanced Fuel: – Selection of high burn-up MA bearing fuel(s), cladding and wrapper
withstanding high neutron doses and temperatures, e.g., ODS steel
�Global Actinide Cycle Int. Demonstration: GACID– Demonstration of MA transmutation using reactors, Joyo and Monju
�Component Design and Balance-Of-Plant:– Development of advanced cycles for energy conversion
– Development of straight tube type SG and evaluation of SWR
– Development of ISI using ultrasonic technologies
� Safety and Operation:
– Improving core inherent safety, development of passive shutdown system
– Prevention and mitigation of severe accident with large energy releases
– Validation of decay heat removal (DHR) & ultimate heat sink, ISI&R
– Prevention & mitigation of sodium fires
� Safety Design Criteria (SDC) consolidation
Key R&D challenges for demonstration phase:
SFR R&D Plans
13INPRO DF, 13-15 April 2016
� Started in Nov. 2006
– China, EU, France, Japan, Korea, Swiss, USA
(Canada, South Africa withdrawn)
� High temperature enables non-electric applications
900 ∼∼∼∼ 1,000℃℃℃℃
� Reference configurations are the
prismatic and the pebble bed
– Designed to be “walk away safe”
� R&D focus on materials and fuels
– Development of a worldwide
materials handbook
– Benchmarking of computer models
– Shared irradiations
• Confirmed excellent performance
of UO2 TRISO
Very-High-Temperature Reactor (VHTR)
14INPRO DF, 13-15 April 2016
Performance Phase: Will be in demonstration phase around 2025
� Leading projects: HTR-PM, Construction in China
NGNP, R&D & Design study in USA
HTTR study in Japan
� Two stages of development
– 700-950℃℃℃℃ outlet
• Technical maturity: 950℃℃℃℃ is demonstrated in AVR & HTTR
• Large market: electricity, process heat
• Main tasks: demonstration, optimization, deployment
– 1000℃℃℃℃ outlet
• Need more R&D
• Improve fuel performance
• Develop material for this high temperature
VHTR : Current Phase
15INPRO DF, 13-15 April 2016
【【【【Long term R&D::::1000℃℃℃℃】】】】
� Require developments of advanced materials (SiC/SiC composites,
graphite, …) and fuels at high burnup up to 200 GWd/tHM)
� Key component development for heat users and H2 production:
Intermediate Heat Exchanger, etc.
【【【【Near term R&D::::700-950℃℃℃℃】】】】
� Hydrogen Production: Outlet temperatures between 700 and 950℃
� Materials: Qualification of Ni alloys & of new grades of graphite
� Fuel and Fuel Cycle: Qualification of UCO TRISO fuel (1,250℃;
burnup≤ 150 GWd/tHM)
� Computational Methods Validation and Benchmarking:
Thermal-hydraulic safety demonstration (LOCA, Passive DHR, etc.)
Key R&D challenges for demonstration phase:
VHTR R&D Plans
16INPRO DF, 13-15 April 2016
� Started in Nov. 2006
– Canada, China, EU, Japan, Russia
� Merges GEN-III+ reactor technology with
advanced supercritical water technology used in coal plants
� Operates above the thermodynamic critical point
(374℃℃℃℃, 22.1 MPa) of water
� Fast and thermal spectrum
options
� R&D focus
– Materials, water chemistry, and
radiolysis
– Thermal hydraulics and safety
to address gaps in SCWR heat
transfer and critical flow databases
– Fuel qualification
510 ∼∼∼∼ 625℃℃℃℃
Supercritical-Water-cooled Reactor (SCWR)
17INPRO DF, 13-15 April 2016
� 2017, possible decision about a SCWR by demonstrator
Just entering Performance phase:
Demonstration phase foreseen in 2025
SCWR : Current Phase
� Canadian SCWR design concept with
pressure tubes
– Design completed and assessed
in Oct. 2015
� China SCWR design concept with
pressure vessel-CSR1000
– Design to be completed and
assessed in 2018
18INPRO DF, 13-15 April 2016
【【【【Near term R&D: - 2017】】】】
� Materials and Chemistry ::::
– Out-of pile, small scale fuel assembly test; cladding
material selection
� Thermal-Hydraulics & Safety:
– Qualification of computational tools
� System Integration and Assessment:
– Pre-conceptual design phase completion
【【【【Long term R&D: 2017 – 】】】】
� In-pile, small scale fuel & assembly tests
Key R&D challenges for demonstration phase:
SCWR R&D Plans
19INPRO DF, 13-15 April 2016
� Started in Nov. 2006
– EU, France, Japan (Swiss withdrawn)
� High temperature, inert coolant and
fast neutrons for a closed fuel cycle
– Fast spectrum enables extension of
uranium resources and waste
minimization
– High temperature enables non-
electric applications
– Non-reactive coolant eliminates
material corrosion
� Very advanced system
– Requires advanced materials and
fuels
� R&D focus
– SiC clad carbide fuel
– High temperature components and
materials∼∼∼∼ 850℃℃℃℃
Gas-cooled Fast Reactor (GFR)
20INPRO DF, 13-15 April 2016
Viability Phase: Will be in performance phase around 2022
� Viable concepts for fuel and cladding have been developed
� Work remains to be done on refining the safety architecture such that the
safety goals can be met in a cost effective manner
� Design studies for an experimental reactor under
consideration: ALLEGRO
GFR : Current Phase
� Work continues in the V4G4*
consortium on developing ALLEGRO to
be a GFR demonstrator – funded at a
fairly low level by the European
Commission and the Governments of
the V4 member states
� ALLEGRO concept has been re-worked
to start with a much smaller core of
10MWth, instead of 75MWth, starting
with UO2 fuel as opposed to MOX
*Czech Republic, Hungary, Slovakia and Poland
21INPRO DF, 13-15 April 2016
� Conceptual Design and Safety:
– Design for safe LOCA
management system & robust
DHR system without external
power supply
� Fuel and Core Materials:
– Developing suitable Fuel
technologies (out-of-pile test +
irradiation experiments)
Key R&D challenges for performance phase:
GFR R&D Plans
22INPRO DF, 13-15 April 2016
480 ∼∼∼∼ 800℃℃℃℃
� Started in Nov. 2010
– EU, Japan, Korea, Russia
� Lead is not chemically reactive
with air or water and has lower
coolant void reactivity
� Three design thrusts:
– European Lead Cooled Fast
Reactor (Large, central station)
– Russian BREST-OD-300
(Medium size)
– SSTAR (Small Transportable
Reactor)
� R&D focus on materials corrosion
and safety
Lead-cooled Fast Reactor (LFR)
23INPRO DF, 13-15 April 2016
� Demonstrators: in Russia PSVBR-100 (Pb-Bi) and BREST-300, ALFRED project (120 MW) in Europe
� Selection of Materials resistant to erosion-corrosion for fuel cladding and reactor structures & components
� Material / Lead chemistry management for T > 480-500℃
� Fuel developments: MOX; Nitride fuel; MAs bearing fuels;
� Fuel handling technology and operation: Core instrumentation. Advanced modeling and simulation, etc.
Performance Phase: Will be in demonstration phase around 2021
Key R&D challenges for demonstration phase:
LFR : Current Phase and R&D Plans
24INPRO DF, 13-15 April 2016
� Started in Oct. 2010
– EU, France, Russia, Swiss
� High temperature system
– High temperature enables
non-electric applications
� On-line waste management
� Design Options
– Solid fuel with molten salt
coolant
– Fuel dissolved in molten
salt coolant
� R&D focus
– Neutronics
– Materials and components
– Safety and safety systems
– Liquid salt chemistry and properties
– Salt processing 700 ∼∼∼∼ 800℃℃℃℃
Molten Salt Reactor (MSR)
25INPRO DF, 13-15 April 2016
Viability Phase: Will be in performance phase around 2025
� Management and salt control (2012-2014)
– Liquid salt chemistry: multi –component solubility limits
versus T℃ & salt composition
� Confirmation of bubbling efficiency (2014-2015)
� Heat exchanger viability (2015-2017)
� Validation of reprocessing flow sheets at laboratory scale
� Definition of safety analysis methodology and
specification of accident scenarios
Key R&D challenges for performance phase:
MSR : Current Phase and R&D Plans
In baseline, the Molten Salt Fast Reactor, MSFR (a liquid fuel concept);
In addition: Fluoride salt-cooled High-temperature Reactor, FHR (solid fuel)
� 2 conceptual designs : MOSART (Molten Salt Actinide Recycler &
Transmuter); MSFR
26INPRO DF, 13-15 April 2016
I. Overview of GIF
II. Current R&D Status of Six Reactor Systems
III. Methodology Working Groups and TFs
IV. Plan for International Cooperation
V. Conclusion
27INPRO DF, 13-15 April 2016
� Established in 2003 to create economic models & guidelines for
assessment of Gen IV systems
– Canada, EU, France, Japan, Korea, USA
� GIF economic goals
– To have a life cycle cost advantage over other energy sources (i.e. to have
lower levelized unit cost of energy on average over the lifetime)
– To have a level of financial risk comparable to other energy projects (i.e.,
to involve similar total capital investment and capital at risk)
� EMWG Products
– Cost Estimating Guidelines for Generation IV Nuclear Energy Systems
Revision 4.2
– Spreadsheet (EXCEL-based) model, i.e., G4-ECONS (Generation 4-EXCEL
Calculation Of Nuclear Systems) Ver 2.0
– User’s Manual for G4-ECONS Ver. 2.0
� Available on a CD-ROM from the GIF Secretariat, Nuclear Energy Agency, OECD
(or at https://www.gen-4.org/gif/jcms/t1_13959/outcomes for members)
Economic Modeling Working Group (EMWG)
28INPRO DF, 13-15 April 2016
� G4-ECONS calculates Total Capital Investment Cost (TCIC) and
Levelized Unit Energy Cost (LUEC)– The Cost Estimating Guidelines define what is to be included in calculation
of TCIC and LUEC
– Bottom-Up Approach: detailed cost estimating technique for mature
designs
– Top-Down Approach: cost estimating technique for systems with less
advanced design detail
� G4-ECONS and cost estimation methodologies demonstrated for– Gen III and Gen III+ systems – HWR, LWR
– Gen IV systems – SCWR, Japanese SFR, GT-MHR
– Hydrogen and process heat – GT-MHR, PH-MHR
– Fuel Cycle Facility costing
� Next Version of G4-ECONS to be released soon for beta-testing
� Continue collaboration with IAEA – Benchmarking of G4-ECONS with INPRO’s NEST for fast reactors in closed
fuel cycle
Economic Modeling Working Group (cont’d)
29INPRO DF, 13-15 April 2016
� Created in Dec. 2002 to establish a framework for assessing
Generation IV nuclear systems against the proliferation
resistance and physical protection goals of GIF– China, Canada, EU, France, Japan, Korea, Russia, USA
� Objectives– Facilitate introduction of PR&PP features into the design process at the
earliest possible stage of concept development ⇒ PR&PP by design
– Assure that PR&PP results are an aid to informing decisions by policy
makers in areas involving safety, economics, sustainability, and related
institutional and legal issues
Proliferation Resistance and Physical Protection Working Group (PRPPWG)
� PR&PP Methodology– A systematic approach to evaluating
vulnerabilities in designs with respect
to the PR&PP goals.
• It provides the assessment
approach that ensures that
assessors “did not do things wrong.”
30INPRO DF, 13-15 April 2016
� Major Accomplishments– The Methodology developed through a succession of revisions – currently
in Revision 6 report
– An example (sodium-cooled) reactor system was chosen to develop and
demonstrate the methodology – resulted in a major report
– Joint Efforts with six GIF design areas - resulted in a major report
� Can be obtained at: https://www.gen-4.org/gif/jcms/c_9365/prpp
� Implementation Activities within National Programs of USA,
Japan, Canada, Europe
� Workshops on PR&PP– To familiarize non-experts on methodology and its applications
– Industry, government, academics, and GIF member community attended
– 2004 (USA), 2006 (Italy), 2007 (Japan), 2008 (South Korea), 2011 (Japan),
2012 (Russia), 2013 (IAEA), 2014 (France), 2015 (USA)
– Joint Workshop with GIF-RSWG: 2003, 2012
� Activities related with IAEA– Interaction between GIF and the IAEA’s INPRO program
– Safeguards by Design ongoing at IAEA and in various countries
Proliferation Resistance and Physical Protection Working Group (cont’d)
31INPRO DF, 13-15 April 2016
� Started in 2005
– Canada, China, EU, France, Japan, Korea, Russia, UK, USA
– In close collaboration with IAEA
� Objectives
– Provide an effective and harmonized approach to the safety
assessment of Generation IV systems in collaboration with and in
support of all six System Steering Committees
� Work Scopes
– Propose safety principles, objectives, and attributes based on Gen IV
safety goals to guide R&D plans
– Provide consultative support to SSCs and other Gen IV entities and
undertake appropriate interactions with regulators, IAEA, and other
stakeholders
– Develop a Safety Assessment Methodology
Risk and Safety Working Group (RSWG)
32INPRO DF, 13-15 April 2016
� Products
– “Basis for the Safety Approach for Design & Assessment of Generation
IV Nuclear Systems” (2009)
– “Integrated Safety Assessment Methodology (ISAM)” (2011)
� Current Activities
– Supports SFR SDC-TF Activities
– Reviews Safety Assessment Document for GIF Systems prepared by
SSCs
– Prepares ISAM Application Guidance Document
– Joint meeting between RSWG and PRPPWG (2015, 22th RSWG meeting)
� Continued collaboration with IAEA
– IAEA supports and reviews to establish safety principles in RSWG
(Basis for the Safety Approach, Integrated Safety Assessment
Methodology, SFR Safety Design Criteria/Guidance)
Risk and Safety Working Group (cont’d)
33INPRO DF, 13-15 April 2016
� SFR Safety Design Criteria (SDC) Task Force was established
by the GIF Policy Group (PG) in Oct. 2010 for the
development of the SDC for the Gen IV SFR system
– Establish reference criteria for safety design of structures,
systems and components
– Achieve harmonization of safety approaches among GIF
member states
» Realization of
enhanced safety
designs common to
Gen IV SFRs
» Preparation for
upcoming licensing
efforts
SDC Task Force
34INPRO DF, 13-15 April 2016
� The SDC Phase-I Report has been approved by GIF in May 2013
– Review is in progress among regulatory bodies/technical
support organizations of FR development countries and by
international organizations (IAEA, OECD/NEA/CNRA, etc.)
– Russia, China, India etc. intend to reflect in the safety design
� The draft report
“Safety Approach
SDG” has been
submitted to
PG/EG/SFR-SSC/RSWG
on 8 October 2015 for
review
SDC Task Force (cont’d)
35INPRO DF, 13-15 April 2016
� Education & Training Task Force (ETTF)
− Established by the GIF PG in Oct. 2015
− To serve as a platform to enhance open education and training as well as
communication and networking of people and organizations in support of
GIF
− will work during the period of 2016-2018
� The ETTF members are basically nominated by PG members
− ask again the PG members for a nomination from China and Canada
Education & Training Task Force (ETTF)
36INPRO DF, 13-15 April 2016
� A social medium platform (Linkedin group of Generation-IV ETTF: https://www.linkedin.com/grp/home?gid=8416234)
− Was created on October 06, 2015
− To communicate with the target groups and start collecting the materials
− The number of members increased to 113 as of 17 Mar. 2016
� Development of first webinar series on GEN IV − Creation of a list of topics
− Finding lecturers who would be willing to present the webinars
� Next steps− Continue GIF-ETTF teleconference monthly to discuss missions and progress
− Launch the first webinar series on GEN IV
− Continue development and maintenance of the social medium platform
− Develop the concept of a summer school for 2017
− Collaborate with relevant conferences, schools and courses
ETTF Activities
37INPRO DF, 13-15 April 2016
� Created in Nov. 2014 by PG authorization (May 2014) with
the purpose of finding out
– if there is any need to develop a GIF-specific narrow
definition of sustainability evaluation methodology
� The 1st and last Interim Sustainability Meeting
– Held in the OECD headquarter, Sep. 16-17, 2015
– Reviewed the relevant sustainability activities in IAEA, NEA
and elsewhere (methodologies and evaluations)
– Collected national views on sustainability
� Conclusion
– More precise evaluation methodology seemed elusive due
to the imprecision of definitions, goals, assumptions,
economics data, technological uncertainties, etc.
– Terminate the Interim Sustainability TF (Phase I)
Interim Sustainability TF
38INPRO DF, 13-15 April 2016
I. Overview of GIF
II. Current R&D Status of Six Reactor Systems
III. Methodology Working Groups and TFs
IV. Plan for International Cooperation
V. Conclusion
39INPRO DF, 13-15 April 2016
� External GIF collaborations include interactions with IAEA , OECD/NEA, and
their various initiatives or international projects, to include, but not be
limited to:
– INPRO and other IAEA endeavors (such as GIF-INPRO Interface Meetings,
Joint IAEA-GIF Technical Meetings on Safety of SFR, etc.);
– The International Framework for Nuclear Energy Cooperation (IFNEC);
– The Nuclear Innovation 2050 (NI2050);
– Engagement of national nuclear safety regulators through the
Multilateral Design Evaluation Program (MDEP), the Committee on
Nuclear Regulatory Activities (CNRA), the Committee on the Safety of
Nuclear Installation (CSNI), and the Ad-Hoc Group on the Safety of
Advanced Reactors (GSAR)
� The objective will be to coordinate, where possible, the GIF’s efforts with
these international endeavors to avoid the duplication of efforts
Plan for International Cooperation
40INPRO DF, 13-15 April 2016
I. Overview of GIF
II. Current R&D Status of Six Reactor Systems
III. Methodology Working Groups and TFs
IV. Plan for International Cooperation
V. Conclusion
41INPRO DF, 13-15 April 2016
� Members have collaborated successfully via international
synergistic collaboration framework, GIF
– SFR, VHTR, SCWR, GFR based on system arrangements
– LFR, MSR based on Memoranda of Understanding
� Most of the GIF goals are very challenging and, after the
Fukushima accident, a stronger & more effective International
cooperation is required to be able to reach all of them,
particularly those regarding safety & economic
competitiveness
� GIF maintains a long-standing collaborative relationship with
the IAEA with previous emphasis on IAEA’s International
Project on INPRO
– Cooperation on evaluation methodologies for economics, safety, physical
protection, and proliferation resistance has been ongoing for several
years
Conclusion
Thank you for your attention!
Reference
44
Generation Taxonomy of Nuclear Reactor Systems
45
Sodium-cooled Fast Reactor (SFR)
Lead-cooled Fast Reactor
(LFR) Very-High-Temperature
Reactor (VHTR)
Supercritical-Water-
cooled Reactor (SCWR) Gas-cooled Fast Reactor
(GFR)
Pool
type
Loop
type
Molten
fuel salt
type
Molten Salt Reactor (MSR)
Six Generation IV Reactor systems
A fluoride salt coolant high-
temperature reactor (FHR)
Molten salt serves as the coolant
of solid fuel core
46
Comparison of Gen IV systems
SystemNeutron
Spectrum CoolantOutlet temp.
(℃℃℃℃)Fuel cycle
Power
(MWe)
Sodium-cooled Fast
Reactor (SFR) Fast Sodium 500-550 Closed 50-1500
Very-High-
Temperature Reactor
(VHTR)Thermal Helium 900-1000 Open 250-300
Lead-cooled Fast
Reactor (LFR)
FastLead 480-570 Closed 20-1200
Supercritical-Water-
cooled Reactor
(SCWR)
Thermal/
Fast Water 510-625
Open/
Closed 300-1500
Gas-cooled Fast
Reactor (GFR) Fast Helium 850 Closed 1200
Molten Salt Reactor
(MSR)
Thermal/
FastFluoride
salts700-800 Closed 1000