ISU Role of International Cooperation 27Jan2014 (1)
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The Role of In ternat ionalCooperat ion in Nuc learEnergy RDD&D
Harold McFarlane
Director, International Programs
Idaho State University 27 January 2014
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As a pract ical matter, INL mus t play a leadership
role in in ternat ional nuclear energy Support U.S. Global interest in
nuclear technologyadvancement, safety and non-proliferation
Enable U.S. experts andcreation of American jobs bypartnering with the privatesector to sustain U.S.leadership in nuclear energy
technology
Fulfill a stewardship role inutilizing/accessinginternational intellectual andphysical capabilities
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Dif fuse internat ional awareness throughout the
organizat ion; focus on relevance and impact Attain positions of
leadership in internationalforums
Apply differentiatingcapability in support of U.S.led international programs
Attract internationalparticipation to INLintellectual and physicalcapabilities
Promote U.S. nuclear energyRDD&D capabilityinternationally
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Character is t ics o f successful col laborat ion
Binding legal framework to protect the rights ofindividual partners
Significant domest ic investment in technology,physical capability and human infrastructure
Motivationcost savings, improved public acceptance,stronger support for domestic program, enhancedassurance for regulator, beneficial outcomes for allparties
Productive use of infrastructure excess capacity
Agreement on common metrics, standards, etc.,including collaboration on development of commontools
Personnel exchanges4
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How INL establ ishes global relationships
Provide critical support to DOEs Office of International NuclearPolicy and Cooperation
Provide experts for International Atomic Energy Agency andOECD/Nuclear Energy Agency working groups and programs
Support for National Nuclear Security Programs (NNSA)
Global Threat Reduction Initiative
Establish collaborations with companies looking to develop andexport nuclear technologies (e.g., TerraPower)
Attract international R&D work to US
Acquire international talent or experience
Lab Directors outreach activities to key nuclear states
Memoranda of Understanding with laboratories in 7 countries
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Venues for internat ional R&D
Generation IV International Forum
Trilateral agreements
Bilateral agreements
Lab-to-lab agreements
International Nuclear Energy Research Initiatives(INERI)
Multinational Design Evaluation Project (MDEP)
European framework Halden Project
OECD/Nuclear Energy Agency projects
Internal domest ic col laborat ion is also v i tal ly important6
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Add it ional Internat ional Success Metr ics fo r INL
Few options available for doing work for foreign organizations
Cooperative Research and Development Agreements (CRADA) we have 6with 4 countries (Canada, France, Japan, and Republic of Korea)
Work for Others (WFO) agreements with Australia, Canada and Japan
License agreements with 17 countries
Membership in the Halden Reactor Project
Collaboration through DOE-NE programs under bilateral andmultilateral agreements
Primary participants are France, Japan, Euratom, China, Russia, Republic ofKorea, and India
Areas of collaboration include reactor design, advanced fuels, fuel cycletechnologies, modeling and simulation, light water reactor sustainability,safety, sensors and instrumentation, and nonelectric applications
Key opportunities
Saudi Arabia, Japan, and South Korea. China?
Membership on Civil Nuclear Trade Advisory Committee (CINTAC) 7
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Potent ia l barr iers to co l labo ration
Market competition
National concerns about:
intellectual property
continued viability of internal facilities and programs
constraining or conflicting policies or agreements
Technological disparity
Policy instability
Inadequate funding of participants (meetings, but not actual work)
Collaborat ion at i ts core is harnessin g the dif ferences that each
person br ings and leveraging the co ntr ibut ions of ind iv iduals tocreate a greater sum. K.Q. 2013
In nuclear, independent verification is good, even necessary to achieve therequired level of quality assurance.
Partners must bring something unique to the table
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Foreign Nat ional Emp loyees
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BEA International Licensing Agreements
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INL Employee International Assignments
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Impacts of 20-year product development cycle
20 years is the rule of thumb for bringing new nucleartechnology to market, which is probably optimistic fora sustainable energy system
Patents developed in the R&D phase expire before
significant market penetration Vast stores of research data and know-how are on theverge of being lost
changes in storage media
retirement
weak knowledge management programs
Appropriate collaboration and sharing are best hopefor preserving essential data and experience
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An INL Success Story : nuc lear cooperation w iththe Republ ic of Korea (ROK)
INL has developed a strategicR&D relationship with theRepublic of Korea (ROK)
There is a strong rationale for
this effortROK has become a leader in
development and deployment ofnuclear technology.
There are significantprogrammatic synergies between
INL and the Korean AtomicEnergy Research Institute(KAERI).
Collaborations help provideadditional U.S. influence on theKorean peninsula
Construction at Kori Nuclear Power Plant
PRIDE Fuel Cycle Facility at KAERI 13
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ROK Col labo rat ion
Cooperation started under DOEsInternational Nuclear EnergyResearch Initiative (INERI)
Collaboration was initiated underthree critical focus areas for INL
Electrochemical processing
High-temperature gas cooledreactors
Reduced enrichment researchreactor fuels development
Collaboration is supported at ahigh-level in both Laboratories.
Second Memorandum of TechnicalCooperation was approved
Another milestone in reduced enrichment fuel
development collaboration 24 January 2014
Signing INL/KAERI Cooperation Agreement 14
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ROK Col laborat ion Focused on Fuel Cycle
Collaboration in electrochemicalprocessing has expanded extensivelythrough the Joint Fuel Cycle Studies
Starting Phase II of a multi-year, multi-million dollar collaboration with theROK to assess options for managementof used nuclear fuel, includingelectrochemical processing
The objective is to demonstrate closureof the fuel cycle using electrochemicalprocessing and metal fuel
Work scope includes demonstration ofadvanced safeguards technology
Program has strong support of the twogovernments
This is a first of a kind collaboration in bothcountries
Proposed equipment layout at INL
Previous KAERI Assignees
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Next Steps for ROK Col labo rat ion
Based on the strong relationshipestablished between KAERI and INL,we continue to expand the scope ofcollaborations
INL recently signed a CRADA to
support fuel irradiation studies forKAERI research reactor fuel.
INL nuclear cyber expertise inNational and Homeland Security isnow being used by KAERI to support
implementation of cyber security inROK facilities
There is potential to expand scopeinto small modular reactordemonstration and fast reactortechnology
Current KAERI Assignees
Korean Fast Reactor Concept 16
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Generat ions of nuc lear energy
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In 1999, low public and political support for nuclearenergy
Oil and gas prices low
USA proposed a bold initiative in 2000
Leapfrog beyond LWR technology and collaborate with
international partners to share R&D
9 Countries and EU joined in
Oil prices jumped soon thereafter
Gen IV concept defined via ambitious goals andTechnology Roadmap
Goals: sustainability, economics, safety and reliability, andproliferation resistance
Technology Roadmap released in 2002
2 year study with over 100 experts worldwide
More than 100 reactor designs evaluated
6 most promising concepts selected
Genesis of Generat ion IV Concept
This may have been thefirst time that the world
came together to decide
on a fission technology
to develop together.
~William Magwood IV
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From concept to demonstrat ion
Prototype
Demonstration
Horizontal ActivitiesEconomics
Safety
Proliferation
feasibility
viability
performance
GFR
VHTR
SFR
LFR
SCWR
MSR
HA
Ideas(Concepts)
The GIF charter
encompasses the completedevelopment cycle and fuel
cycle
Each horizontal activity
involves collaboration
with IAEA/INPRO
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Generat ion IV organizat ion
Proliferation Resistance &
Physical Protection
Risk & Safety
Economic Modelling
Methodology
Working Groups
System Steering
Committees
Project
Management
Boards
(Multiple R&D projects)
Policy Secretariat
Policy Director - P. Anzieu
Technical Director - D. Hahn
T. Dujardin
Technical Secretariat
Senior Industry
Advisory Panel
ChairVacant
Co-chairVacant
Policy Group
Chair - J. Kelly (USA)
Vice Chair - C. Behar (France)
Vice Chair - K. Aoto (Japan)
Co-Chairs
Experts Group
ChairD. Hahn (ROK)
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Sodium Fast Reactor
550 C
Integral part of the closed fuel cycle
Can either burn actinides or breed fissile material
Designs being developed
ASTRID (France)
JSFR (Japan)
PGSFR (Korea)
BN-1200 (Russia)
BN-800 (Russia)
2014 - Start-up expected
2015 - Fully operational
R&D focus
Analyses and experiments that demonstrate safetyapproaches
High burn-up minor actinide bearing fuels
Develop advanced components and energy conversion
systems
500 -550 C
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Lead Fast Reactor
480 -800 C
Lead is not chemically reactive withair or water and has lower coolantvoid 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 corrosionand safety
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Gas-coo led Fast Reacto r
High temperature, inert coolant and fastneutrons for a closed fuel cycle
Fast spectrum enables extension of uraniumresources and waste minimization
High temperature enables non-electricapplications
Non-reactive coolant eliminates materialcorrosion
Very advanced system
Requires advanced materials and fuels
Key technical focus:
SiC clad carbide fuel
High temperature components and materials
850 C
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High temperature enables non-electric applications
Goal - reach outlet temperature of 1000oC, with near termfocus on 700-950C
Reference configurations are theprismatic and the pebble bed
Designed to be walk away safe
R&D focus on materials and fuels
Develop a worldwide materials handbook
Benchmarking of computer models
Shared irradiations
Confirmed excellent performance ofUO2TRISO
Japan HTTR in operation
China HTR-PM demonstration plantunder construction
Very High Temperature Reactor
900 - 1000 C
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Supercri t ical Water-Coo led Reactor
Merges GEN-III+ reactor technology withadvanced supercritical water technology used in coal plants
Operates above the thermodynamic critical point(374C, 22.1 MPa) of water
Fast and thermal spectrumoptions
Key technology focus:
Materials, water chemistry, andradiolysis
Thermal hydraulics and safetyto address gaps in SCWR heattransfer and critical flow databases
Fuel qualification
510 - 625C
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Molten Salt Reacto r
High temperature system
High temperature enablesnon-electric applications
On-line waste management
Design Options
Solid fuel with molten saltcoolant
Fuel dissolved in moltensalt coolant
Key technical focus
Neutronics
Materials and components
Safety and safety systems
Liquid salt chemistry and properties
Salt processing
700 - 800C
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Generation IV System Development thru 2013
Participating member, signatory of a System Arrangement or a Project Arrangement at some point during the period.This table does not necessarily reflect the status of participation as of 1 January 2014.
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GIF Materials Handbook
International Handbook of Evaluated Criticality Safety Benchmark
Experiments International Handbook of Evaluated Reactor Physics Benchmark
Experiments
Safety Design Criteria for Sodium-cooled Fast Reactors (underdevelopment)
Regulatory standards and convergence
Examples of last ing impact of international
cooperat ion
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Internat ional Handbook o f Evaluated Cri t ical i tySafety Benchmark Experiments
September 2013 Edition
20 Contributing Countries
Spans nearly 67000 Pages
Evaluation of 568 Experimental Series
4,798 Critical, Subcritical, or KConfigurations
24 Criticality-Alarm/ ShieldingBenchmark Configurationsnumerous dose points each
155 fission rate and transmissionmeasurements and reaction rate ratiosfor 45 different materials
http://www.oecd-nea.org/science/wpncs/icsbep/
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ICSBEP International Partners 20 Coun tr ies
Republ icof Korea
1996Japan1994
China2006
India2005
Spain2000
UnitedKingdom
1994
United States
1992
Brazil2004
Russian Federation1994
Israel 2000
France1994
Hungar y 1994Slovenia 1998Serbia 1999Kazakhstan 1999Czech Republic 2004Poland 2005
Argentina2008
Canada2005
Sweden2007
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Internat ional Handbook of Evaluated Reacto rPhys ics Benchm ark Exper iments
March 2013 Edition
21 Contributing Countries
Data from 131 Experimental Seriesperformed at 47 Reactor Facilities
Data from 127 out of the 131 seriesare published as approvedbenchmarks
Data from 4 out of the 131 seriesare published in DRAFT form
http://www.oecd-nea.org/science/wprs/irphe/
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IRPhEP In ternational Partners 21 Countr ies
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Inc reased sharing of h igher f lux US mater ials
test reactors and cr i t ical support faci l i t ies
Infrastructure
Equipment
Knowledge
Technical Expertise
Partnerships
User Facilities
HFIR 35
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Gen-IV International Forum promot ing increased
sharing o f expensive infrastructu re
Type of Capability FR JP KR RU US EUIrradiation X X X X X
Core Design X X X
Post Irradiation Exam X X X X
In Service Inspection X X X
Safety X X X X
Coolant Loops X X X X X
Instrumentation & Control X X X
Power Conversion X
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Other dimens ions of internat ional nuc lear energy
Regulator collaboration (MDEP)
Design specific working groups
AP1000
EPR
APR1400
Issue specific working group
Digital I&C
Codes & Standards
Vendor inspection cooperation
Safeguards and security International Framework for
Nuclear Energy Cooperation
OECD/Nuclear Energy Agency
Global Corporations
Westinghouse
Majority owned by Toshiba
AP1000 construction in China
Technology transfer to ChinaConstruction experience transfer to
US Vogtle and Summer projects
GE-Hitachi
New enrichment technology
Marketing advanced BWR
AREVA global footprint
Emerging Korean export power
ROSATOMRussiastechnology and export
powerhouse 37
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The National Nuclear Laboratory