Generation IV International Forum Overview Dr John E

Generation IV International Forum Overview Dr. John E. Kelly GIF Policy Group Vice Chairman and Chief Technology Officer, Office of Nuclear Energy FESAC TEC Meeting May 30, 2017

Genesis of Generation IV Concept q In 1999, low public and political support for nuclear energy • Oil and gas prices were low q USA proposed a bold initiative in 2000 • The vision was to leapfrog LWR technology and collaborate with international partners to share R&D on advanced nuclear systems • 9 Countries and EU joined USA in developing the initiative • Oil prices jumped soon thereafter q Gen IV concept defined via technology goals and legal framework • Technology Roadmap released in 2002 • 2 year study with more than 100 experts worldwide • Nearly 100 reactor designs evaluated and down selected to 6 most promising concepts • First signatures collected on Framework Agreement in 2005; first research projects defined in 2006 “This may have been the first time that the world came together to decide on a fission technology to develop together. ” ~William Magwood IV, First Chairman of the Generation IV International Forum

Generation IV Goals q Sustainability • Long term fuel supply • Minimize waste and long term stewardship burden q Safety & Reliability • Very low likelihood and degree of core damage • Eliminate need for offsite emergency response q Economics • Life cycle cost advantage over other energy sources • Financial risk comparable to other energy projects q Proliferation Resistance & Physical Protection • Unattractive materials diversion pathway • Enhanced physical protection against terrorism

Generation IV International Forum

Fourteen Current Members of Generation IV Argentina * Japan Australia * Korea, Republic of Brazil * Russian Federation Canada South Africa China Switzerland Euratom United Kingdom * France United States *Argentina, Australia, Brazil and the United Kingdom are non-active, i. e. they have not acceded to the Framework Agreement which establishes system and project organizational levels for further co-operation. Australia signed the GIF Charter on June 22, 2016, thus becoming the GIF’s newest and 14 th member.

Generation IV System Development Matrix Generation IV Systems Sodium-cooled Fast Reactor (SFR) Very-high Temperature Gas cooled Reactor (VHTR) Gas-cooled Fast Reactor (GFR) Supercriticalwater cooled Reactor (SCWR) Lead-cooled Fast Reactor (LFR) Molten Salt Reactor (MSR) Canada China France Japan Korea Russia South Africa Switzerland U. S. A. Participating member, signatory of a System Arrangement as of February 2017 EU

Generation IV Organization Policy Group Chair • Francois Gauche (France) Experts Group Chair • Alexander Stanculescu (USA) Methodology Working Groups • Proliferation Resistance & Physical Protection • Risk & Safety • Economic Modelling Vice Chairs • John E. Kelly (USA) • Hideki Kamide (Japan) • Hark Rho Kim (Korea) System Steering Committees Senior Industry Advisory Panel Chair • Haeryong Hwang (Korea) Policy Secretariat Policy Director • François Storrer (France) Technical Director • Alexander Stanculescu (USA) Co-Chairs Technical Secretariat Project Management Boards • Henri Paillère (NEA) (Multiple R&D projects) Chairs as of February 2017

System Steering Committees Sodium-Cooled Fast Reactor Supercritical-Water Cooled Reactor Chair • Hiroki Hayafune (Japan) Chair • Yanping Huang (China) Co-Chairs • Jean Michel Ruggieri (France) • Robert Hill (USA) Co-Chair • Laurence Leung (Canada) Molten Salt Reactor Chair • Jerome Serp (France) Gas-Cooled Fast Reactor Chair • Branislav Hatala (Euratom) Senior Industry Advisory Panel Lead Fast Reactor Chair • Alessandro Alemberti (Euratom) Very High Temperature Reactor Co-Chair • Hans Gougar (USA) Co-Chair • Michael Fuetterer (Euratom) Chairs as of February 2017

Technology Roadmap Update q Roadmap first published 2002 q Decadal update just completed 2013 VHTR SFR SCWR MSR LFR GFR 2000 2002 2013 2010 viability 2020 performance 2030 demonstration www. gen-4. org/gif/jcms/c_60729/technologyroadmap-update-2013

Sodium Fast Reactor q Major features • Fast neutron spectrum • Low pressure liquid metal coolant • Flexible fuel cycle applications q SFR design activities • ASTRID (France) • JSFR (Japan) • PGSFR (Korea) • BN-1200 (Russia) • ESFR (European Union) • AFR-100 (United States) • CFR-1200 (China)

SFR System Status q More than 400 reactor years operating experience since 1951 • EBR-II, FFTF, Phenix, Superphenix, BOR-60, BN-600, and JOYO • BN-800 (Russia) and CEFR (China) started operating in the last decade q GIF SFR Projects • Systems integration and assessment • Safety and operation • Advanced fuel • Component design and balance of plant • Global actinide cycle international demonstration project q GIF SFR notable accomplishments • Developing, validating and applying safety codes • Irradiation and examination of minor actinide fuel samples • Under sodium viewing, remote welding, inspection sensors • Preliminary irradiations for actinide recycle demonstration

Very High Temperature Reactor q Major features • Inert helium coolant • Unique TRISO fuel • Thermal neutron spectrum • Exceptional safety • Very high temperature operation • Non-electric applications q VHTR Design Activities • HTR-PM demonstration plant under construction (China) • Next Generation Nuclear Plant (United States) • Naturally Safe High Temperature Reactor (Japan) • Clean Burn High Temperature Reactor (Japan) • Multi-purpose HTGR (Japan and Kazakhstan) • PBMR (South Africa)

VHTR System Status q Operating experience gained since 1963 • AVR and THTR (Germany) • Peach Bottom and Fort St. Vrain (United States) • HTTR (Japan) • HT 10 (China) q GIF VHTR Projects • Fuel and fuel cycle • Hydrogen production • Materials • Computation, modeling, validation and benchmarking q GIF VHTR notable accomplishments First Concrete poured for China’s HTR-PM ~ Courtesy Tsinghua University • Fuel irradiation and examination • More than 300 reports uploaded into the Materials Handbook • Hydrogen production testing

Gen IV Materials Handbook • Gen IV Handbook is digital, web-based database system developed to collect and manage all GIF VHTR materials data (>$150 M) • Includes graphite, metals, and ceramics & composites data • Mandatory usage required by VHTR Materials Project Arrangement • Includes technical reports, test data, materials pedigree, microstructures, data analysis and comparison tools, etc. • Very strong access control for individuals, organizations, and data • Funded by DOE-NE as part of GIF contribution & managed at ORNL • Separate volumes funded for additional DOE and other programs n ASME has signed contract with ORNL to develop separate volume · Will contain entire ASME materials data base when complete · ASME to bear incremental costs

Lead-cooled Fast Reactor q Major features • Liquid metal coolant that is not reactive with air or water • Lead or lead-bismuth eutectic options • Fast neutron spectrum q LFR design activities • BREST (Russia) • SVBR-100 (Russia) – Lead-bismuth • ALFRED (European Union) • ELFR (European Union) • SSTAR (United States) • MYRRHA (European Union) – Accelerator driven system 480º - 800º C

LFR System Status q Operating experience • 80 reactor years of Russian submarine LBE reactor operation (15 units) q GIF LFR Projects • GIF has no formal system arrangement for LFR • Cooperation conducted under an MOU q GIF LFR notable accomplishments • Developed an international LFR community • Developed a provisional system research plan • Materials corrosion tests ongoing with lead loops in several laboratories

Gas-Cooled Fast Reactor q Major features • Fast neutron spectrum • Inert helium coolant • Very high temperature operation • Fuel cycle and non-electric applications • Significant development challenges for fuel, safety and components q GFR design activities • Allegro (European Union) 850º C

GFR System Status q No operating experience for this challenging concept • Development relies on VHTR technology q GIF GFR projects • Conceptual Design and Safety • Fuel and core materials q GIF GFR notable accomplishments • Promising fuel concept based on a multi-barrier cylinder • Safety system design GFR reference design

Supercritical Water - Cooled Reactor q Major features • Merges LWR or PHWR technology with advanced supercritical water technology used in coal plants • Operates above thermodynamic critical point (374º C, 22. 1 MPa) of water • Fast and thermal spectrum options q SCWR Design Activities • First design effort 1957 • Pre-conceptual design of SC PHWR (Canada) • Pre-conceptual SC LWR design activities (Japan and European Union)

SCWR System Status q Operating experience • No SCWR has been constructed • Vast operating experience in supercritical coal plants q GIF SCWR projects • Thermal hydraulics and safety • Materials and chemistry • Fuel qualification test • System integration and analysis q GIF SCWR notable accomplishments • Experiments on heat transfer with supercritical water and other fluids • Corrosion testing for different steel alloys • Fuel qualification testing planned

Molten Salt Reactor q Major features • Molten salt eutectic coolant • High temperature operation • Thermal or fast spectrum • Molten or solid fuel • On-line waste Management q Design Activities • 2 -MWt FHR test reactor (China) • Pre-conceptual designs to guide R&D planning – Molten Salt Actinide Recycler and Transmuter (MOSART) – Molten Salt Fast Reactor (MSFR)

MSR System Status q Operating experience • Molten Salt Reactor Experiment (MSRE) • Aircraft Reactor Experiment (ARE) q GIF MSR Projects • No formal system arrangement • Cooperation proceeding under an MOU q GIF MSR notable accomplishments • The participants conducted benchmark analyses on neutronics, mutiphysics, and safety • Studies are ongoing to measure thermo physical properties of candidate salts • Identification of key research needed for viability assessment

Methodology Working Groups q Developing methodologies for measuring progress against the GIF goals q Three working groups reporting to the Technical Director • Risk and Safety (ISAM-Integrated Safety Assessment Methodology) • Proliferation Resistance and Physical Protection • Economics Modeling (Generation IV Cost Estimating Guidelines) q The efforts are relatively mature with notable accomplishments • Methodology incorporated into framework for evaluation • Trial applications • User training • G 4 -ECONS cost estimating software available for general use • Starting to develop safety design criteria

SFR Safety Design Criteria Task Force q Task Force created to develop safety design criteria and guidelines • Sodium fast reactor was selected as the most mature system • Effort is being extended to other systems q Phase 1 produced a draft report containing the proposed criteria • “Safety Design Criteria for Generation IV Sodium-cooled Fast Reactor System” • Several workshops organized with technical experts, regulators, and design organizations to assess the criteria q Phase 2 is developing detailed guidelines for the SDC q Regulatory engagement • On-going engagement with international regulator organizations through the NEA ad hoc Group on the Safety of Advanced Reactors (GSAR)

Education and Training Task Force q Formed to develop education and training materials related to Generation IV systems q Created a webinar series (monthly) to provide presentations for the general public on the Gen IV systems and cross-cutting topics q Connecting with other nuclear education organizations to share information on educational opportunities and Summer Schools

Over 20 Advanced Fission Reactor Designs in the United States • Sodium Fast Reactor • Terra. Power, General Electric, etc • High Temperature Gas Reactor • X-Energy, AREVA, Terra. Power, Hybrid Energy, Ultra Safe, etc • Molten Salt Reactor • Terra. Power, Transatomic, Terrestrial, Elysium, FLIBE Energy, etc • Lead Fast Reactor • Westinghouse, Gen IV Energy, Lake-Chime, etc • Gas Fast Reactor • General Atomics

Future of Generation IV q Over the last decade Gen IV has had major accomplishments • Legal framework established for collaboration • Collaborative projects started with significant R&D investment worldwide • Prototype demonstrations are being designed and/or built – SFR (France and Russia) – VHTR (China) q Much still needs to be done before Gen IV systems are a reality • Continue R&D on Gen IV systems • Develop advanced research facilities • Engage industry on the design of Gen IV systems • Engage regulators to establishing regulatory framework • Develop the workforce for the future