overview of the international initiatives for the ... of the international initiatives for the...
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IAEA International Atomic Energy Agency
Overview of the International Initiatives for the
Development of Innovative (GENIV) Fast Reactors
Stefano Monti ([email protected])
Team Leader - Fast Reactor Technology Development
Division of Nuclear Power
IAEA Education and Training Seminar on
FAST REACTOR SCIENCE AND TECHNOLOGY
Centro Atòmico Bariloche, October 1 – 5, 2012
IAEA
Outline
Generation IV International Forum - GIF
IAEA – International Project on Innovative Nuclear Reactors and
Fuel Cycles - INPRO
IAEA Technical Working Group on Fast Reactors - TWGFR
European Sustainable Nuclear Industrial Initiative – ESNII
Real construction and operation: Russia, India and China
Conclusions
2
IAEA
Fast Neutron Systems in a Closed Fuel Cycle:
Towards a more sustainable nuclear energy
Tomorrow’s generation of reactors / Fast Neutron Reactors:
The above and….
Multiplication by a factor 50 to 100 the
energy produced by a given amount of
uranium,
Minimization of volume, thermal load
and radiotoxicity of waste …
“Closing the fuel cycle”:
enough resources for thousands of years
Today’s generation of reactors:
Safe, reliable and competitive
Availability of secure resources (about 100 y at the present rate of consumption)
Reprocessing of spent fuel for enhanced use of resources
Technical solution for waste management
IAEA 4
Generation IV International Forum – GIF
GEN-IV International Forum is an
international initiative launched by US-
DOE in 2001 to:
Identify potential areas of multilateral
collaborations on Generation IV nuclear
energy systems
Foster collaborative R&D projects
Establish guidelines for collaboration and
reporting of results
Regularly review the progress and make
recommendations of the direction of
collaborative R&D projects
January, 2003
E.U.
China
Russia
IAEA
Generation IV International Forum - GIF
4th Generation Nuclear Systems for
sustainable energy development
E.U.
China
Russia
Technical maturity around 2030
Steady progress
• Economic Competitiveness
• Safety and reliability
Significant progress
• Waste minimisation
• Resource saving
• Security: non proliferation, physical protection
Opening to other applications:
• High temperature heat for industry
• Hydrogen, drinking water
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Sodium-cooled Fast Reactor Lead-cooled Fast Reactor
Molten Salt Reactor
Gas-cooled Fast Reactor
Supercritical Water-cooled Reactor
Very High Temperature Reactor
The six GEN-IV nuclear systems
IAEA
The GIF Management
Framework
Agreement
System
Arrangement
(SA)
Project
Arrangement
(PA)
Instruments R&D Plans
System
Research Plan
(SRP)
Project Plan
(PP)
Technology
Roadmap
IAEA
Project Management
Boards
Project Management
Boards
Energy Conversion
Project Management
Boards
GIF Nuclear Systems studies in Brief
System Steering
Committees
Co-Chairs
Project Management
Boards
System
Arrangements
Project
Arrangements
Framework Agreement
Fuel and Fuel Cycle
Materials
…other
PG: Defines Policy; Sets guidelines
SSC: Defines a System Research Plan
Coordinates and monitors the
implementation
PMB: Agrees on a Project Plan
Revises annually a Work
Plan
Enters members funding
in the accounts
IAEA
Contributions to the GIF
Japanese Chairmanship since end of
2009 (3 year term):
Mr Yutaka Sagayama, from JAEA
Generation IV
International
Forum China
Russia Euratom
VHTR
GFR
SFR
LFR
MSR
SCWR
IAEA
Status of GIF agreements (May 2012)
Framework Agreement
MSR
Agreement
LFR
Agreement
Conceptual
Design & Safety
Project
Fuel and other
Core Materials
Project
Fuel & Fuel Cycle
Project
H2 Production Project
Advanced Fuel
Project
Component
Design & Bal. Of
Plant Project
SFR Agreement VHTR Agreement
GACID Project
Safety & Operation
Project
GFR Agreement
Signed
Not yet signed Materials Project
SCWR Agreement
Thermal-
Hydraulics &
Safety Project
Material &
Chemistry Project
Fuel Qualification
Project
System Integration &
Assessment Project
Computational Methods,
Validation & Benchmark
Project
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Overview of SFR Technology
System Integration and Assessment: design and safety studies will be integrated into generalized design concepts evaluated against Generation-IV goals and criteria.
Safety and Operation: verification of safety tools, evaluation of the effectiveness of inherent mechanisms and design features, reactor operation and technology testing campaigns in existing SFR reactors.
Advanced Fuels: development of high-burnup fuel systems (fuel form and cladding) research on remote fuel fabrication techniques recycle fuels that contain minor actinides
Component design and BOP: development of advanced energy conversion systems (Brayton Cycle) development of advanced in-service inspection and repair technologies.
Global Actinide Cycle International Demonstration (GACID): Demonstrate effective management of all actinide elements in the fuel cycle
IAEA
GFR System Arrangement
System Arrangement signatories: France (CEA),
Japan (JAEA), Switzerland (PSI), Euratom (JRC).
Two Projects:
Conceptual Design and Safety (Participants: France,
Switzerland and Euratom)
Fuel and other Core Materials (Participants: France, Japan,
Switzerland and Euratom)
IAEA
GIF – LFR
System Research Plan – Completed October 2010
SRP Identifies four main research areas as follows: System Integration and Assessment (Feasibility & Gen IV Goals)
System and Component Design (System and component development)
Fuel Development (long term project but “easy” short term solution)
Lead Technology / Materials (short term: available tech – long term: high T)
IAEA
The Risk and Safety Working Group
“Promote a consistent approach on safety, risk, and regulatory issues
between Generation IV systems”
Advise and assist the Experts Group and the Policy Group particularly
on matters of:
• Generation IV safety goals and evaluation methodologies to be
considered in the design
• Interactions with the nuclear safety regulatory community, the IAEA,
and relevant stakeholder
As directed by EG, recent work principally focused on development of a
safety assessment methodology suitable for Gen IV systems
IAEA
The Proliferation Resistance and Physical
Protection Working Group
Monitor the integrity and quality of PR&PP evaluations for GIF
• Provide peer-review of PR&PP evaluations upon request
Maintain capability to perform or direct PR&PP studies on request of GIF
Maintain configuration control over the PR&PP methodology, its documentation and
revisions
Strengthen the link with Generation IV system designers, in particular with GIF
System Steering Committees
Promote and facilitate early consideration of PR&PP in the development and design
of Generation IV systems
Maintain cognizance of related GIF activities, e.g., those of the RSWG
Maintain cognizance of and interactions with non-GIF activities such as IAEA
initiatives and specific national initiatives
Promote PR&PP goals and broad acceptance of the PR&PP methodology
IAEA
The Economics Modelling Working Group
Formed in 2004 for developing a cost estimating methodology to be used for assessing GIF systems against the GIF economic goals
From 2009: improvement of the G4ECONS software for analysis of heterogeneous fuel cycles for
• fast reactor systems,
• actinide management applications
Monitoring the use of the methodology
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The International Project on Innovative Nuclear
Reactors and Fuel Cycles (INPRO)
IAEA
International Initiatives
IAEA - INPRO
The International Project on Innovative Nuclear Reactors
and Fuel Cycles (INPRO) was authorized by IAEA
General Conference resolution in 2001
To help ensure that nuclear energy is available to contribute to meeting the energy
needs of the 21st century in a sustainable manner
To bring together technology holders, technology users and other stakeholders to
consider jointly the national and international actions required to achieve desired
innovations in nuclear reactors and fuel cycles.
To support national strategic and long range planning and decision making in the
field of nuclear energy development and deployment
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INPRO Memberships - 2011
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INPRO Projects
Project 1: National long-range nuclear energy strategies
To assist Member States in building national long-range nuclear
energy strategies and in long-range nuclear energy deployment
decision making through the INPRO methodology (NESA) and
other tools
Project 2: Global nuclear energy scenarios
To develop global and regional nuclear energy scenarios, on the
basis of a scientific-technical analysis, that lead to a global vision
on sustainable nuclear energy development in the 21st century
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INPRO Projects
Project 3: Innovations
To investigate innovations in selected nuclear energy technologies
and related R&D and in innovative institutional arrangements to be
deployed in the 21st century and to support Member States in
pursuing such innovations and exchanging progress towards their
realization
Project 4: Policy and Dialogue
To provide to Member States’ guidance, policy planning, and
coordination with other international organizations and initiatives and
to bring together technology holders and technology users to share
information on long-range nuclear energy system strategies, global
nuclear energy scenarios and technical and institutional innovations
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NESA & INPRO methodology
INPRO takes an holistic approach to assess innovative nuclear systems in
several areas
The methodology is based on a set of Basic Principles, User Requirements
and Criteria
The Nuclear Energy Systems Assessment (NESA) using INPRO methodology
covers
Innovative and evolutionary designs of all reactor
types and NFC facilities
All facilities of a nuclear energy system (no matter
where located)
All phases of a nuclear energy system, i.e. cradle
to grave
IAEA
Investigate technical challenges of cooling reactor cores
that operate at temperatures up to 1000oC using liquid
metals (LM) and molten salts (MS) as coolants (e.g.,
FRs, HTRs, and ADS)
• Heat transfer and pressure drop studies (experimental and computational)
• Thermo-physical properties at high temperatures
• Chemistry monitoring and control
• Materials compatibility with high temperature coolants
Participants: Brazil, China, Germany, India, Italy, Korea
CP COOL: Investigation of Technological Challenges related to Heat Removal by Liquid
Metal and Molten Salt Coolants from Reactor Cores Operating at High Temperatures
IAEA
CP DHR: on Integrated Approach for the Modelling of Safety Grade
Decay Heat Removal System for LMR (Report ready for publication)
Reference Design: 500 MWe pool type PFBR
International benchmark for safety grade DHR
system applicable to pool type LM-FRs.
Identify relevant R&D areas, e.g. related to
natural convective heat transfer.
INPRO Collaborative Project:
“Integrated Approach for the Modelling of Safety Grade Decay Heat
Removal System for Liquid Metal Reactors"”
Participants
China EU/JRC
India Korea, Republic of
Russian Federation
IAEA
The IAEA Technical Working Group on
Fast Reactors
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Members of the IAEA Technical Working Group on Fast Reactors
Full Members
Belarus Brazil
China France
Germany India
Italy Japan
Kazakhstan Korea, republic of
Netherlands Russian Federation
Sweden Switzerland
Ukraine UK
USA European Commission
OECD/NEA
Observers
Argentina Belgium
Spain
45th Annual Meeting
Argonne National Laboratory (USA),
20 – 22 June 2012
Full Members Observers
Members of the IAEA Technical Working Group on Fast Reactors
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Organize regular Topical Technical Meetings for information exchange;
Organize large conferences on different aspects of FR and related fuel
cycles;
Establish a forum for broad exchanges on technical requirements;
Carry out collaborative research projects;
Secure training and education in the field of fast neutron system
physics, technology and applications;
Provide support to IAEA Nuclear Safety and Security Department for
preparation of fast reactor safety standards, requirements and guides;
Support fast reactor data retrieval and knowledge preservation within
the Member States.
Main activities of TWG-FR
IAEA
CRP on Analyses of, and Lessons Learned from the Operational
Experience with Fast Reactor Equipment and Systems
• Preserve the feedback from commissioning, operation, and decommissioning
experience of experimental and power sodium cooled fast reactors
• Retrieve, assess, review and archive of all the relevant documentation and
information
• Enable easy access to the information from this feedback
• Produce lessons-learned, synthesis reports of lessons learned and
recommendations from the commissioning, operation, and decommissioning
of experimental and power sodium cooled fast reactors
“Analyses of and lessons learned from the operational
experience with fast reactor equipment and systems”
Participants
France India
Japan Korea, Republic of
Russian Federation
IAEA
“Control Rod Withdrawal and Sodium
Natural Circulation Tests Performed
during the PHENIX End-of-Life
Experiments”
Participants
China France
India Japan
Korea, Republic of Russian Federation
Switzerland USA
CRP on Control Rod Withdrawal and Sodium Natural Circulation Tests
Performed During the PHENIX End-of-Life Tests (special session at ICAPP-12)
Experimental benchmark exercises (preparatory
analyses, blind calculations, and post-
experiment analyses) based on the data
obtained during the PHENIX End-of-Life tests
V&V of methods and codes currently employed
in the field of FR neutronics, thermal hydraulics
and plant dynamics to achieve enhanced safety
IAEA
“Benchmark Analyses of Sodium Natural
Convection in the Upper Plenum of the MONJU
Reactor Vessel”
Participants
China France
India Japan
Korea, Republic of Russian Federation
USA
CRP on Benchmark Analyses of Sodium Natural Convection in the Upper
Plenum of the MONJU Reactor Vessel
Validation of CFD methods and turbulence models
based on Na thermal stratification measurements
performed in MONJU during a reactor turbine trip
test conducted in December 1995 in the course of
the original start-up experiments
Thorough assessment of the calculation versus
measured data comparisons
IAEA
“Benchmark Analyses of an EBR-II Shutdown Heat Removal
Test”
Expression of Interest
China Germany
Italy India
Japan Korea, republic of
Netherlands Russian Federation
Sweden Switzerland
USA
CRP on Benchmark Analysis of an EBR-II
Shutdown Heat Removal Test
A comprehensive testing program (45 tests !) conducted
between 1984 and 1987 A unique set of whole-plant
safety tests that demonstrated the potential for SFR to
survive severe accident initiators with no damage
Two EBR-II loss of flow tests chosen for this IAEA CRP:
SHRT-17, the most severe of the loss of flow with
scram tests
SHRT-45, the most severe of the loss of flow without
scram tests
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New CRP on SFR: Sodium Properties, Sodium Facility Design and
Safety Guidelines (to be launched in 2012-2013)
This CRP is proposed by France and it is
intended to address the needs of
standardization of Na physical and
chemical properties, the main rules for
designing experimental facilities, good
practices and safety guidelines
The CRP – making available validated
data and correlations for Na coolant - will
also improve the modelling and simulation
capabilities in various fields of SFR
technology
The outputs of this CRP will contribute to
an improvement of the future benchmark
exercises and of the design of sodium
facilities and their safe operation.
IAEA
New CRP on Source Term for Radioactivity Release under FR Core
Disruptive Accident (CDA) Conditions (to be launched in 2013-2014)
Demonstrate through numerical simulations of
FPs transport mechanisms that in future FBRs
the radioactivity release to the environment is
very low even in the extreme case of CDA
Under whole core accident, the fission products
and radioactive sodium are the basic source for
the radioactivity release
Reference design for the
safety analysis:
500 MWe pool type PFBR
??
?
? ?
?
IAEA
Technical Reports Published or closed to Publication
Proceedings of FR09, Kyoto,
December 2009 (published)
Liquid metal coolants for Fast
Reactors: reactors cooled by sodium,
lead and lead-bismuth eutectic (ready
for publication)
Design Features and Operating
Experiences of Experimental Fast
Reactors (ready for publication)
33
IAEA
Status of Fast Reactor Research and Technology
Development (850 pages TECDOC ! Ready for publication):
Background and overview
Operating experience with SFR
Sodium-cooled FR Designs
HLM-cooled FR Designs
Gas-cooled FR Designs
Status of FR core R&D
Reactor plant engineering technology development
Reactor safety design and analysis
National strategies, international initiatives, public acceptance and final
remarks
34
Technical Reports Published or close to Publication
IAEA
Technical Reports and NES under Editing / Review
BN-600 Hybrid Core Benchmark Analysis: methods to reduce
calculation uncertainties of the LMFR reactivity effects
Benchmark analyses on the Natural Circulation Test
Performed During the PHENIX End-of-Life Experiments
Final Reports of the CRP on Control Rod Withdrawal Tests
Performed During the PHENIX End-of-Life Tests
Final Report of the CRP on Benchmark Analyses of Sodium
Natural Convection in MONJU Reactor Vessel
Final Report of the CRP on Lessons Learned from the
Operational Experience on Fast Reactors
35
IAEA
ESNII
European Sustainable
Nuclear Industrial Initiative
36
IAEA
Towards Sustainable Nuclear Energy in Europe
Gen IV: Sustainability and U resource preservation: x 50-100
Waste management Improvement
Major role of LWRs in the 21st century:
Current PWRs (Gen II): life time management (> 40yr)
Gen III PWRs : starting around 2015
Deployment of fast neutron systems foreseen around 2040,
depending on the maturity of the technology and on the market
needs.
European Nuclear Industrial Initiative
Possible scenario for future development of nuclear fleet
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ESNII: European Sustainable Nuclear
Industrial Initiative Instrument for coordinating the implementation of the SNETP pillar on
sustainability of nuclear fission, based on Gen IV fast reactors with
closed fuel cycle (targeted deployment 2040)
The programme includes 3 FNR concepts:
An SFR prototype (ASTRID) as main and more mature technology
Demonstrators for GFR (ALLEGRO) & LFR (ALFRED) as alternative
technologies
A fast neutron spectrum multipurpose irradiation facility (MYRRHA) also
acting as LFR pilot plant
Supporting infrastructures and R&D
The ESNII Task Force started working in 2008, with actors from
industry and research under the Sustainable Nuclear Energy
Technology Platform (SNETP)
IAEA
2040: Target for the deployment of Gen-IV Fast Neutron Reactors with
closed fuel cycle
5 b€
1.96 b€
1.2 b€
2.65 b€
Total estimated cost: 10.81 b€
ESNII: Building Blocks and Budget
IAEA 40
French actors get organised (650M€)
Open to EU / international cooperation
- Belgian programme
for MYRRHA, 60M€ / 5 years
- East European support to ALLEGRO
- Romania could host ALFRED
• Preliminary design phases: partially funded
• Next steps: strong need for Public - Private Partnerships (National - EU - Private funding)
ESNII: the projects
IAEA
GENIV SFR Astrid
IAEA
2009 2010 2011 2012 2013 2014 2015 2016 2017
Decision to
continue
Preliminary choice
of options
ASTRID: Schedule
Decision to
build
Conceptual
design -1
Conceptual design
-2
Basic
design
Fuel loading
Detailed design
& Construction
ASTRID
Facilities
Feasibility Report
on minor
actinides
partitioning
Position Report on
minor actinides
partitioning and
transmutation
Core
manufacturing
workshop (AFC)
MA bearing fuels
fabrication facility
(ALFA)
IAEA
LFR Strategy
A general discussion about the LFR strategy was conducted inside the LEADER project and taking into account the past experience, the development of the Lead cooled technology is expected to follow the following steps:
• Experimental facilities, corrosion tests, materials etc (already in operation)
• GUINEVERE - Zero power facility
• MYRRHA - Technology Pilot Plant (SCK•CEN - Mol) - 100 MWth
• ALFRED - LFR Demonstrator (electrical grid connection) - 300 MWth
• PROLFR - Industrial Prototype - 800/1200 MWth
• ELFR (ELSY) - FOAK European LFR - 600 MWe
+ ELECTRA - Education & Training Facility for LFR (KTH - Sweden)
IAEA
The VENUS-F configuration for GUINEVERE
Pb radial reflector
Pb top reflector
6 B4C safety rods with fuel follower
(2 B4C control rods are not shown)
Core in metallic uranium and lead
Pb bottom reflector
IAEA
Reactor
• Subcritical or Critical modes
• 65 to 100 MWth
Accelerator
(600 MeV - 4 mA proton)
Fast
Neutron
Source
Spallation Source
Lead-Bismuth
coolant
Multipurpose
Flexible
Irradiation
Facility
MYRRHA : Multipurpose hYbrid Research Reactor for High
tech Applications
IAEA
MYRRHA: The project schedule
©
SCK•
CEN
46
2010-2014
Front End
Engineering
Design
2019
On site
assembly
2016-2018
Construction of
components &
civil engineering
2015
Tendering &
Procurement
2020-2022
Commissioning
2023
Progressive
start-up
2024-
Full
exploitation
FEED
(Front End
Engineering
Design)
2010-2014
Minimise
technological
risks
Secure
the licensing
Secure a sound
investment
structure
DOF Safety Option
File
PDP Preliminary
dismantling
plan
EIAR environmental
impact
assesment
Central
Project
Team
Owner
Engineering
Team
Owner
Consortium
Group
IAEA
ALFRED – System Configuration
IAEA
Gas Fast Reactor systems
48
2400 MW th design by GOFASTR
European Project (PSI, AMEC, CEA)
ALLEGRO 75 MW th Design
Czech, Hungarian, Slovakian
Consortium
IAEA 49
The ESNII Task Force • Memorandum of Understanding under SNETP umbrella
• 13 founders, now 22 partners
• Balance between industry and research
ESNII: the actors
Industry Research
IAEA 50
June 2010 Sept. 2007
SNETP – ESNII: From vision to strategy
June 2009
Deployment
Strategy Vision Report Strategic
Research Agenda
IAEA 51
2011 January 2010
ESNII Reports
October 2010
Implementation
Plan Deloitte Study Concept Paper
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ESNII – Technology Review
Technical criteria Objectives and mission
Technological readiness
Safety demonstration
Synergies and potential spin-offs
Stakeholders Existing and committed R&D capabilities
Framework for industrial participation
Involvement level of industry (utilities / vendors / engineering firms)
Member States support
Status of international collaboration (including involvement in GIF)
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Siting Existence of host country/-ies
Licensability
Financial & legal Status of committed financing
Eligibility to EU financing instruments
Eligibility to EU legal instruments
Implementation plan 2012-2014
Preparedness of legal schemes
Market Expected market
Time to market
ESNII – Technology Review
IAEA 54
BOR-60 reactor facility has been
operating for more than 42 years and
will be replaced by MBIR in 2019
BN-600 reactor, being the largest
operating SFR in the world, is under
operation since more than 32 years.
Construction completion of the BN-
800 reactor is scheduled in 2014
Large size SFR BN-1200 under
development
Relevant FR projects at the National Level
- Russian Federation -
IAEA 55
• Indigenous Design & Construction
• Comprehensiveness in development - Design, R&D and Construction
• Synthesis of Operating Experiences
• Synthesis of Emerging Concepts
• Focus on National & International Collaborations
• Emphasis on high quality human resources
• Creation of environment for enabling innovations to ehance safety of SFRs
PFBR
•1250 MWt
•500 MWe
•Pool Type
•UO2-PuO2
•Indigenous
•From 2013..
----Thermal
Insulation
12
95110Anchor safety
vessel
11
----Core04
5561Inner vessel05
----Transfer Arm06
----Large Rotatable
Plug
07
----SRP/Control Plug08
----IHX09
----Primary Pump10
3644.8Core support
structure
02
3476Grid Plate03
01
No.
116134Main vessel
CFBRPFBR
Weight in tComponent
10 09
07 08
06
04 05
03
02 01
11
12
13
72
5
Ø11950
CFBR
•500 MWe
•Pool Type
•UO2-PuO2
•3 twin units
•Indigenous
•From 2023…
Future FBR
• 1000 MWe
• Pool Type
• Metallic fuel
• Serial constr.
• Indegenous
• Beyond 2025
FBTR • 40 MWt
• 13.5 MWe
• Loop type
• PuC – UC
• Design: CEA
• Since 1985 MFTR (120 MWe)
Relevant FR projects at the National Level
- India -
IAEA
2002.8
2000.5
1998.10
2008.12
2009.8
Preparation of Site
Main building finished
Reactor block
installation finished
Commissioning of Phase A ended
Thermal power, MW 65
Electric power, net, MW 20
Reactor core,
Height, cm 45.0
Diameter equivalent, cm 60.0
Fuel (first loading, (Pu, U)O2, [UO2]
Pu, total, kg 150.3 239Pu, kg 97.7 235U- (enrichment), (first loading) kg (%) 42.6 (19.6%), [236.7 (64.4%)]
Linear power max, W/cm 430
Neutron flux, n/cm2·s 3.7×1015
Relevant FR projects at the National Level
- China -
IAEA
Conclusions
Fast reactor operated in closed fuel cycle improve drastically the
sustainability of nuclear energy utilization
Several international initiative have been established in the years in order to
promote the development of innovative fast reactors technology
Generation IV international forum (GIF) was launched in 2001 to support the
development of next generation (GEN-IV) nuclear reactors. Among the six
concepts selected, three are FR systems
The IAEA INPRO project also deals with future nuclear energy systems and
establish collaborative projects (CP) in the are of FR
In the EU framework, ESNII has the target of the deployment of Gen-IV Fast
Neutron Reactors with closed fuel cycle by first half of the century
The IAEA TWG-FR has accompanied FR technology development for more
than 45 years and continue to support Members States programmes on FR
IAEA 58
http://www.iaea.org/NuclearPower/FR/
…Atoms for Peace
Thanks for Your Attention !