SFR System Status and Plans Dohee Hahn SFR SSC Chair GIF Symposium San Diego November 15-16, 2012
Outline Overview of SFR R&D Key Priority Objectives Project Status Application of GIF Methodologies Challenging Technology Gaps Slide 2
Key SFR Development Targets 1. Actinide Management 2. Innovative Design Features for Cost Reduction 3. Safety Assurance 4. Reduction in Environmental Burden 5. Resistance to Nuclear Proliferation and Enhanced Physical Protection Slide 3
Basic Description of Gen IV SFR Mission - Primary mission for SFR is the improved utilization of uranium resources and effective management of high-level waste - With reduction of capital cost, SFR is an attractive option for electricity production Typical Design Parameters for Gen IV SFR - Outlet Temperature 500-550 0 C - Power Rating 50-2,000 MWe - Fuel Oxide, Metal Alloy, Others - Breeding Ratio 0.5 1.3 Slide 4
Status of SFR Arrangements EUR FRA JPN PRC ROK RUF USA SFR System Arrangement (15 Feb 2006) SFR AF Project Arrangement (PA) (21 Mar 2007) SFR GACID PA (Sept 2007) SFR CDBOP PA (11 Oct 2007) SFR SO PA (11 June 2009) SFR SIA PA X X X X X X X X X X D X D X X X X D X X X D X D X X D X D X D D D D D D D Advanced Fuel / Global Actinide Cycle International Demonstration / Component Design and Balance-Of-Plant / Safety and Operation / System Integration and Assessment X=Signatory, D=Under Discussion Slide 5
Key Priority Objectives Advanced fuels Make preliminary selection of advanced fuels» Preliminary evaluation of irradiation performance and fabrication technology of (U, Pu) fuels Fuels: Oxide, metal, nitride, carbide Core materials: F/M and ODS Progress towards the resolution of feasibility issues regarding actinide recycling» Ongoing activities on fabrication and irradiation of minor actinide (MA) bearing fuels and advanced cladding materials Slide 6
Key Priority Objectives Safety approach Progress towards converging safety approaches» Reference was made to Basis for Safety Approach and Integrated Safety Assessment Methodology» Participation in establishment of SFR Safety Design Criteria Revisit re-criticality and potentially positive reactivity coefficient issues, to compare approaches and seek for consensus» Definition of optimized ranges of key reactivity coefficients to avoid fuel melting and sodium boiling Coupling of CATHARE and TRIO for Phénix End-of-Life test analysis Core design for reduced sodium void coefficient Slide 7
Key Priority Objectives Safety approach (Cont d) Assess, among other approaches, the effectiveness of innerduct structures to mitigate severe accidents while enhancing fuel discharges without the formation of large molten-fuel pool» Investigation of early molten fuel discharge behavior and post-accident material redistribution, and improvement of computer codes for severe accident analyses FAIDUS Options Code for calculation of duct failure time Slide 8
Key Priority Objectives In-service inspection (ISI) Draw conclusions from related R&D work and set priorities for the future» Development of advanced ISI instrumentation and repair methods using different approaches and technologies: ultrasonic immersion and waveguide sensors, RF-ECT and EMAT sensors Real Time Array Sensor High Temperature Sensor Multi-coil RF-ECT sensor High Resolution Array Sensor Telemetry Array Sensor Under-sodium Immersion Sensors Waveguide Sensor Magnetic sensor Slide 9
Key Priority Objectives In-service inspection (Cont d) Progress towards resolving in-service inspection and repair feasibility issues» Improvement of high reliability sensors, remote-handling systems in sodium, and maintenance and repair equipments Articulated Inspection Arm (Tore Supra 2008) Ultrasonic Inspection from outside of RV Under-sodium Remote Robot Remote Welding of Nozzles (Phénix) Slide 10
Key Priority Objectives Phénix, Monju and possibly CEFR and BN 800 tests Summarize lessons learned from planned experiments and start-up» Phénix End-of-Life tests have provided unique and important test data for validation of system analysis codes» Further discussion is needed regarding sharing of experience Materials, codes and standards Development of codes and standards for high temperature application» No activities Slide 11
Key Priority Objectives Energy conversion systems Draw conclusions from related R&D work and define priority research for the future» S-CO 2 Brayton cycle system can improve SFR economics by eliminating sodium-water reactions and increasing plant efficiency Make progress towards resolving feasibility issues on alternative energy conversion systems with S-CO 2 or gas» Studies show that S-CO 2 Brayton cycle is ideally matched to SFR operating conditions» No issues or show stoppers have been identified» Demonstration of S-CO 2 Brayton and gas Brayton cycles at sufficiently large scale is needed Slide 12
System Integration & Assessment (SIA) Project Objectives Integration of the results of R&D Projects Performance of design and safety studies Assessment of the SFR System against the goals and criteria set out in the Gen IV Technology Roadmap Status Provisional PMB prepared Project Arrangement which will be under signature process after Amended Safety and Operations Project Arrangement completes its signature process Slide 13
System Steering Committee WP 3 SRP WP 1 SIA Project Maintain and refine SFR system options in System Research Plan (SRP) Contribute trade studies in support of system specification Specify R&D needs in technical PMBs Review PPs to ensure the needs are met WP 2 Primary Roles of SIA Project and Its Relation to Technical Projects Assess & Integrate R&D results Contribution as BPI/ Voluntary (JSFR, ESFR, KALIMER, SMFR) Concept Developer Concept Developer Concept Developer Self-assessment Design Concept Study Integrate R&D results Entire set of R&Ds Technical PMBs (AF, GACID, CDBOP and SO) Slide 14
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 and Design Tracks Loop Pool Small 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 Slide 15
Key Design Parameters of Design Tracks Design Parameters JSFR KALIMER SMFR ESFR Power Rating, MWe 1,500 600 50 1,500 Thermal Power, MWt 3,570 1,500 125 3,600 Plant Efficiency, % 42 40 ~38 ~42 Core outlet coolant temperature, o C 550 545 ~510 545 Core inlet coolant temperature, o C 395 390 ~355 395 Main steam temperature, o C 503 503 480 490 Main steam Pressure, MPa 16.7 16.5 20 18.5 Cycle length, years 1.5 2.2 1.1 30 1.25 Fuel reload batch, batches 4 5 1 5 Core Diameter, m 5.1 4.2 1.75 4.9 Core Height, m 1.0 0.89 1.0 1.0 Fuel Type MOX(TRU bearing) Metal(U-TRU- 10%Zr Alloy), Metal(U-TRU- 10%Zr Alloy), MOX(TRU bearing) Cladding Material ODS HT9M HT9 ODS Pu enrichment (Pu/HM), % 13.8 25.2 15.0 15.2 Burn-up, GWd/t 150 139 ~87 155 (max) Breeding ratio 1.0 1.2 0.74 1.0 1.0-1.2 Slide 16
Advanced Fuel (AF) Project Objective Development of high burn-up MA bearing fuel(s), cladding and wrapper withstanding high neutron doses and temperatures» Fuels: Oxide, Metal, Nitride, Carbide, Heterogeneous targets» Core materials: F/M and ODS steels Project Status Discussion is on-going in order to include China and Russia as new members Slide 17
Advanced Fuel Project Plan - Original 2007 : Identification of advanced fuel options 2010 : Primary selection of advanced fuel(s) 2015 : Final selection of advanced fuel 2006 07 10 15 Preliminary evaluation of advanced fuels MA fuels evaluation High burnup fuel behavior evaluation Definition of advanced fuel options Candidates of advanced fuel options : Decisions Primary selection of advanced fuel candidates Demonstration and application Final selection of advanced fuel candidates Preliminary evaluation of (U, Pu) fuel continued until 2009 in order to utilize more databases MA fuel evaluation needs to be extended until 2015, considering status of national programs of the PMB members Slide 18
Advanced Fuel Project Plan - Revised 2009 : Identification of advanced fuel options 2015 : Primary selection of advanced fuel(s) 2020 : Final selection of advanced fuel 2009 2015 2020 Preliminary evaluation of advanced fuels Preliminary evaluation Identification of advanced fuel options MA fuels evaluation MA fuels evaluation Primary selection of advanced fuel(s) High burnup fuel behavior evaluation High burnup fuel behavior evaluation Final selection of advanced fuel Demonstration and application Carbide fuel and heterogeneous MA recycling have been added as new tasks Revision of the Project Plan has been prepared by the PMB members and will be submitted to System Steering Committee (SSC) for approval Slide 19
GACID Project Objective: to demonstrate, using Joyo and Monju, that FR s can transmute MA s (Np/Am/Cm) and thereby reduce the concerns of HL radioactive wastes and proliferation risks. A phased approach in three steps. Material properties and irradiation behavior are also studied and investigated. GACID overall schedule Step-1 Np/Am pin irrad. test Step-2 Np/Am/Cm pin irrad. test Step-3 Np/Am/Cm bundle irrad. test Joyo Joyo Planning Monju Test fuel fabrication Monju MA-bearing MOX fuel pellets Fuel pin fabrication Monju (Final Goal) Tri-lateral collaboration in GACID pin-scale tests. Monju Irradiation test GACID: Global Actinide Cycle International Demonstration MA raw material preparation The Project is being conducted by CEA, USDOE and JAEA as a GIF/SFR Project, covering the initial 5 years since Sep. 27, 2007. Slide 20
Component Design (CD) and BOP Project Objective Enhancement of SFR system performance through» Development of advanced components and technologies to enhance economic competitiveness of the plant» R&D on Advanced Energy Conversion Systems such as supercritical CO 2 Brayton cycle system» Innovation in Rankine cycle Steam Generator design to enhance robustness against sodium/water reaction as well as efficiency Project Status Signature process has begun for amended PA with Euratom as a new signatory All signatories of the original PA agreed on new signatory s access to previous deliverables Slide 21
CD&BOP Project Plan - Original 2007 : Viability study of proposed concepts 2010 : Performance tests for detailed design specification 2015 : Assessment of system performance Various innovative inspection technologies have been developed Studies have been actively conducted for S-CO 2 Brayton cycle systems: testing of small-scale heat exchangers, compressors, sodium- CO 2 interactions, CO 2 corrosion, analyses of SFRs incorporating S-CO 2 Brayton cycles, plant dynamic analyses for SFRs with S-CO 2 cycles Slide 22
CD&BOP Project Plan - Revised 2012 : Viability study of proposed concepts 2015 : Performance tests for detailed design specification 2016 : Assessment of system performance Euratom was added as a new signatory of the amended PA Inspection technologies and S-CO 2 Brayton cycle system will be developed until 2016 Development of SG tube inspection technologies, and assessment & development of Rankine-type SG concepts have been added as new tasks Slide 23
Safety and Operation (SO) Project Objectives Analyses and experiments that support safety approaches and validate specific safety features Development of computational tools useful for such studies Acquisition of reactor operation technology, as determined largely from experience and testing in operating SFR plants Project Status China, Russia and Euratom have been added as new signatories and the amended PA is now under signature process Initial signatories unanimously decided that new signatories can have access to 2009-2011 deliverables Slide 24
Safety and Operation Project Plan - Original 2008 : Review of safety provisions and systems 2010 : Performance assessment, Model validation 2015 : Safety qualification and Optimization Basic safety provisions and systems have been fully investigated Performance assessment needs to be continued Slide 25
Safety and Operation Project Plan - Revised 2010 : Innovative safety concepts, Basic safety studies 2015 : Model development and Performance assessment 2016 : Safety qualification and Optimization Project Plan has been modified to provide more flexible framework for R&D activities Slide 26
Summary of SFR Project Activities Project 07~ 10 11 Deliverables Deliverables 11 Annual Tech. & Financial Report 12 Annual Work Plan Activities SIA NA NA NA NA PA is ready for signature AF 99 18 Prepared Prepared GACID 10 In preparation In preparation CD& BOP 57 16 Prepared Prepared SO 32 11 Prepared Prepared Participation of China and Russia is under discussion Two year extension of PA to 2014 was agreed Amended PA with Euratom as a new member is under signature process Signature process is ongoing for amended PA with new memberships of China, Russia and Euratom Slide 27
Application of GIF Methodologies Detailed design information is required to apply assessment methodologies, and results of self assessment by concept developers are solicited under the SIA Project Economics Methodology Self assessment of JSFR using G4-ECONS will be conducted Risk and Safety Methodology Whitepaper was prepared to facilitate application of the methodology ISAM will be applied to JSFR There has been limited application of Integrated Safety Assessment Methodology (ISAM) to SFR design tracks Proliferation Resistance and Physical Protection Methodology Whitepaper was prepared Slide 28
Challenging Technology Gaps Development of remote fabrication technologies and demonstration of high burnup irradiation performance of minor actinide bearing fuels: AF Project Large-scale demonstration of S-CO 2 Brayton cycle system: CD&BOP Project Development of passive safety measures available at design extension conditions and validation of its performance: SO Project Slide 29
Summary Various collaborative activities are being conducted in the areas of Advanced Fuels, Transmutation of MAs, Component Design and Balance-of-Plant, and Safety and Operation Efforts were made to conduct R&D activities consistent with key priority objectives and there is a need to update schedules Project Arrangements are now being amended through evaluation of achievements, consideration of changes in national programs, and participation of new members There has been limited application of GIF methodologies Challenging technology gaps were identified and R&D tasks have been developed by PMBs Slide 30