Fast reactor development and worldwide cooperation in Generation-IV International Forum FR13 Paris, France March 4, 2013 Yutaka Sagayama Former Chair of the Generation-IV International Forum Senior Advisor to the Ministry of Education, Culture, Sports, Science and Technology of Japan
Contents 1. First decade of GIF 2. Basic concept of GIF activities 3. Governance of GIF 4. GIF activities 5. Recent Topics 6. Expectation for FR13 Slide 2
1. First Decade of GIF Jan. 2000 Joint Statement was announced. Jul. 2001 GIF Charter was signed. Jul. 2002 Selection of 6 Innovative systems Dec. 2002 Technology Roadmap was created Feb. 2005 Framework Agreement (FA) was signed. 2006-2010 Arrangements & Memoranda of Understanding (MOU) for 6 systems were signed. Technology Roadmap for GIF systems Signing of FA (Washington D.C.) Slide 3
2. Basic concept of GIF activities Generation of Nuclear Energy Systems JSFR, ASTRID, BN-1200 Slide 4
Objectives of Gen-IV systems development Goals:Four challenging technology goals have been defined to be applied to innovative nuclear reactor concepts in the 21st century: 1) Safety and Reliability (safe and reliable operation, no offsite emergency response) 2) Sustainability (effective fuel utilization, minimization of nuclear waste) 3) Proliferation Resistance & Physical Protection (to assure unattractive and the least desirable route for diversion or theft of weapons-usable materials, and provide increased physical protection against acts of terrorism) 4) Economic Competitiveness (life-cycle cost advantage over other energy resources) Phase: Each Generation-IV reactor system is one of three stages. 1) Viability Phase 2) Performance Phase 3) Demonstration Phase Target:Commercial Deployment is expected around 2030s or beyond. Slide 5
GIF s Goals and design approach Development Goals Safety & reliability Sustain ability PRPP Economics Safe & reliable operation No offsite emergency Minimization of nuclear waste Effective fuel utilization Non-proliferation System & technology development of physical protection Life -cycle cost advantage Examples of Design Approach Safety and reliability during normal operation, and likely operational events that assume forced outage rate Minimizing frequency of initiating events, and design features for controlling & mitigating any initiating events without causing core damage Safety architecture to manage & mitigate severe plant conditions, for minimizing the possibility and the amount of releases of radiation Burning of MA and restrain of piling-up of long-lived fission products Utilization of all U resources by burning of MA with consideration for the transition from LWR to FR cycle Provision of institutional measures and technological features against diversion of nuclear materials and illegal utilization of institutions Adopting physical protection system consistent with IAEA guideline and law/rule and with fuel cycle system concept Pursuing the compactness of plant system with innovative technologies and materials Higher core fuel burnup and plant availability Slide 6
Six Gen-IV systems Sodium-cooled Fast Reactor (SFR) Gas-cooled Fast Reactor (GFR) Lead-cooled Fast Reactor (LFR) Supercritical Water cooled Reactor (SCWR) Very High Temperature Reactor (VHTR) Molten Salt Reactor (MSR) Slide 7
GIF Member Implementing Agents NR-Can JRC CEA ANRE, JAEA CAEA, MOST MEST, NRF DOE ROSATOM PSI DOE 3. Governance of GIF GIF Governance Structure Report to Provide Secretariat for Communicate closely with Slide 8
Membership to GIF System Arrangements (GIF members: 12 countries and 1 agency) X: Signatory, MOU: Memorandum of Understanding Sodium-cooled Fast Reactor (SFR) Very High Temperature Reactor (VHTR) Gas-cooled Fast Reactor (GFR) Supercritical Water-cooled Reactor (SCWR) Lead-cooled Fast Reactor (LFR) Molten Salt Reactor (MSR) CAN FRA JPN ROK ZAF CHE USA EUR PRC RUS UK RFB ARG X X X X X X X X X X X X X X X X X X X X X MOU MOU MOU MOU MOU Slide 9
R&D Projects of 6 Systems in GIF Project Management Board (PMB) Methodology WGs (MWG) System Steering Committee (SSC) SFR (Sodium-cooled Fast Reactor ) VHTR (Very-High-Temperature Reactor) SCWR (Supercritical-water-cooled Reactor ) GFR (Gas-cooled Fast Reactor) LFR (Lead-cooled Fast Reactor) MSR (Molten Salt Reactor) Advanced Fuel (AF) Global Actinide Cycle Int. Global Demonstration Actinide Cycle Int. Demonstration (GACID) Component Design and BOP (CDBOP) Safety and Operation (SO) System Integration and Assessment (SI&A) Materials and Chemistry Thermal-hydraulics & Safety Fuel Qualification Test Conceptual Design and Safety (CD&S) Fuel and Core Materials (FCM) Economic Model Proliferation Resistance and Physical Protection Risk and Safety Hydrogen Production (HP) Fuel and Fuel Cycle (FFC) Materials Computational Methods Validation and Benchmarking (CMVB) already set up under preparation Slide 10
4. GIF Activities Sodium-cooled Fast Reactor(SFR) Four project arrangements have been implemented. A project arrangement of SI&A is ready for signing. AF: Selection of high burn-up Minor actinide (MA) bearing fuels, cladding and wrapper tubes. GACID: To demonstrate, using Joyo and Monju, that Fast Reactors can transmute MAs and thereby reduce the concerns of High Level radioactive wastes and proliferation risks. CDBOP: Enhancement of SFR system performance through development of advanced components aiming at economics improvement and R&D for supercritical CO 2 cycle. SO: Analyses and experiments supporting safety approaches, development of computational tools and acquisition of reactor operation technology. Slide 11
EXHAUST TO VENT STACK 7m (23') IHX X-SECTION (FLATTENED FOR CLARITY) CONTROL RODS (7) PLAN VIEW OF IHX AND PUMPS IHX (2) 2 1.7m EACH PUMPS (2) ON Ø 142.5" B.C. DRACS (2) 2 0.4m EACH SECONDARY CONTROL RODS Na-CO2 HEAT EXCHANGER SODIUM DUMP TANK Ø 2.5 m x 3.8 m LONG (Ø 7.5' x 12.6' LONG) PRIMARY CONTROL RODS CORE BARREL Ø 266 / 268 cm (104.7" / 105.5") PLAN VIEW OF THE CORE 0 1 2 3 4 5 METERS 10 TURBINE/GENERATOR BUILDING 3.25m (10'-8") 7m [23FT] (29.5") 0.75m THERMAL SHIELD 1m TRAVEL DISTANCE OF THE CONTROL RODS 4.57m Primary Vessel I.D. [15FT] IHX 5.08m Guard Vessel I.D. [16.7FT] 3 12.03 m 3,186 gal. 1.89m [6.2FT] (Ø 25.5') Ø 7.7m SECTION A - A Na-Air HEAT EXCHANGER (2) ELEVATOR 3.5m 1m (11'-8") (39.4") GUARD VESSEL (1" THICK) PRIMARY VESSEL (2" THICK) CONTROL BUILDING 12.72m [41.7FT] 14.76m [48.4FT] 1.93m [6.3FT].61m [2FT] Hot Pool Normal sodium level Cold Pool Normal sodium level 2.29m [7.5FT] Pump off Sodium Level Sodium faulted level Gen IV SFR System Options Loop Pool Modular JSFR ESFR KALIMER SMFR Secondary Pump AHX Chimney SG Primary Pump/IHX PDRC piping IHTS piping Steam Generator Reactor Vessel IHX DHX PHTS pump Reactor core IHTS pump In-vessel core catcher 1500MWe MOX 1.0-1.2 Japan (JAEA) 1500MWe MOX, Metal - 600MWe Metal 1.0 Korea (KAERI) 50MWe Metal 1.0 US (ANL) Slide 12
Gas-cooled Fast Reactor (GFR) Fuel & Core Material project is being prepared for official arrangements, and Conceptual Design & Safety (CD&S) project is in progress. CD&S: To define a conceptual design with operating parameters and appropriate safety architecture. Lead-cooled Fast Reactor (LFR), Memorandum of Understanding (MOU) has been implemented for the LFR systems. Its System Research Plan is being prepared. Slide 13
Current situation of SFR development (1/2) Japan E: Joyo (MK-III reactor core: 140 MWt): P: Monju (280 MWe): D: JSFR (1500 MWe): in design (2025) France P: Phenix (250MWe):ended operation (2009) P(D): ASTRID(600 MWe): in design (2023*) Russia E: BOR-60 (12 MWe): in operation P: BN-600 (600 MWe): in operation D: BN-800 (880 MWe):under construction (2014*) C: BN-1200 (1200 MWe): in design (2020*) E: MBIR (ca. 40 Mwe): in design (2019*) E: Experimental, P: Prototype, D: Demonstration FR, *Operation Start Slide 14
Current situation of SFR development (2/2) China E: CEFR (25 MWe): in commissioning test (initial criticality, 2010) D: 2 reactors (ca. 800MWe): under negotiation (ca. 2020*), C: CFR-600 or 1000 (600 or 1000 MWe; 2023*) India E: FBTR (13 MWe): in operation P: PFBR (500 MWe): under construction (2013*) D/C: CFBR (500 MWe): under design (2023*-) E: MFTR (120MWe): under design (2020*) Korea P: PGSFR (150 MWe): in design (2028*) E: Experimental, P: Prototype, D: Demonstration FR, *Operation Start Slide 15
5. Recent topics in GIF (1) Safety Design Criteria : SDC International collaboration should be fostered on the utilization of nuclear energy for future. For that, it becomes more significant to build common criteria which should be flexible within an acceptable range. Based on that background, PG chair proposed to create the safety design criteria (SDC) on Gen-IV SFR as international common criteria at PG meeting in October, 2010. GIF created a taskforce under the PG and has started examination on the SDC. The SDC is the SFR design criteria to achieve safety goals of Gen-IV systems. Slide 16
Safety Design Criteria : SDC SFR SDC by GIF Slide 17
Safety Design Criteria : SDC After the SDC have been discussed in GIF for 2 years, its draft report is almost completed. The SDC was also discussed at the GIF-IAEA joint workshop last week in Vienna and final report of SDC/taskforce will be reported in Beijing GIF/PG meeting, May 2013. Safety Design Criteria for other Gen-IV systems need to be considered in GIF as well. MDEP SDC IAEA Slide 18
5. Recent topics in GIF (2) Decadal Strategic Planning for GIF Strategic planning is underway to further progress of GIF. Strategic planning for next decade Ten years have passed from establishment of GIF Development of Gen-IV systems is progressing to next phase Technology has advanced Taskforce for next decadal planning (Sub-teams) Technology roadmap update Strengthening R&D collaboration Strengthening ties with other international organizations Technology Roadmap(2002) Slide 19
Decadal Strategic Planning for GIF Current status of Decadal Strategic Planning was explained and discussed in the 2 nd GIF symposium and Policy Group meeting in San Diego. The final report will be prepared by April, 2013 and be discussed in next Policy Group meeting in Beijing, China in May 2013. We expect GIF will progress further to the next stage under new decadal strategic planning. Slide 20
6. Expectation for FR13 A series of international conferences on fast reactors was revived with FR09 (Kyoto, Japan, Dec., 2009) for the first time in 18 years. Now is a critical time for SFR development because it is progressing towards demonstration phase. Expect the success of FR13 and meaningful information exchange in this conference. Slide 21
Summary GIF has played a major role as an international framework for development of Gen-IV nuclear systems since 2001. Countries expanding energy demand plan to enlarge the capacity of nuclear power. Gen-IV systems also need to be deployed. After Fukushima Daiichi NPP accident, more enhancement of safety is crucial, and Gen-IV systems importance has not changed. Expect the success of FR13. Slide 22
Thank you for your attention! http://www.gen-4.org/ Slide 23