Current Activities on the 4S Reactor Deployment

Transcription

1 PSN Number: PSN Document Number: AFT rev.000(1) Current Activities on the 4S Reactor Deployment The 4th Annual Asia-Pacific Nuclear Energy Forum on Small and Medium Reactors: Benefits and Challenges June 18 and 19, 2010 Berkeley, CA, California Kazuo Arie Senior Manager Advanced System Design & Engineering Department Isogo Nuclear Engineering Center Toshiba Corporation 1

2 Outline 1. 4S Design Overview 2. Technology Development 3. Economics 4. Licensing 5. Concluding Remarks 2/30

3 1. 4S Design Overview 2. Technology Development 3. Economics 4. Licensing 5. Concluding Remarks 3/30

4 4S (Super-Safe, Small & Simple) Sodium-cooled pool type fast reactor Versions 10 MWe (30MWt) 50 MWe (135MWt) Main features Refueling interval 10 MWe: 30 years 50 MWe: 10 years Passive safety Minimal moving parts Security and safeguards designed in R/B located below grade Reactor Turbine/ Generator Steam Generator Co-developer: CRIEPI Developing partners: ANL, WEC 4/30

5 4S Reactor System Metallic fuel core (U-10%Zr) Reactivity control by movable reflectors Shutdown system by reflectors and a shutdown rod Passive shutdown by metallic fuel properties during ATWS Electromagnetic pumps have no moving parts EM Pumps Shutdown rod IHX Core Reflector ATWS: Anticipated Transient Without Scram 5/30

6 Heat Transport System IRACS cooling system Passive cooling by RVACS Helical-coil type double-wall steam generator Integrated assembly of IHX and EM pumps RVACS: Reactor Vessel Auxiliary Cooling System 6/30

7 Electro-Magnetic Pump (EM Pump) Electromagnetic pump in primary system No rotating parts Immersed Type Iron core Coil Duct Sodium EM Pump 7/30

8 Double Wall Steam Generator (DWSG) Double-wall helical coil type with 30 MWt capacity Inner tube leak detection Moisture detection in helium between inner and outer tubes Outer tube leak detection Helium detection in the intermediate sodium circuit Sodium flow Water flow Inner tube Wire mesh and helium Outer tube Development Study of a Wire Mesh Filled Double Wall Tube for FBR Steam Generators I.Ohshima et.al. Transactions of the Atomic Energy Society of Japan, Vol.36, Sodium No.9 (1994) 8/30

9 Reactor Building Ground level Steam generator Reactor assembly Lead plug Flange Rubber Horizontal Seismic seismic isolator 9/30

10 Passive Decay Heat Removal Natural air draft & natural circulation RVACS : Natural air draft outside the guard vessel IRACS : Natural circulation of sodium and air draft at air cooler Air outlet Air outlet Air inlet IRACS (Air Cooler) Sodium flow Temperature ( ) Primary temperature(~260,000sec) Core-inlet Core-outlet Air inlet Guard Vessel RVACS SG , , , , ,000 Time (s) Core temperature during loss-of-power only with natural circulation Air flow pass RVACS: Reactor Vessel Auxiliary Cooling System, IRACS : Intermediate Reactor Auxiliary Cooling System 10/30

11 Applications Electricity Remote area Mining Seawater desalination etc. Steam supply (process heat) Oil sands/oil shale recovery Hydrogen production etc. Potential customers Alaska, Texas, Hawaii, others (US) Nunavut, oil sands, mining sites (Canada) Middle East, Mongoria, etc. 11/30

12 1. 4S Design Overview 2. Technology Development 3. Economics 4. Licensing 5. Concluding Remarks 12/30

13 Status of Verification Tests Design Feature Verification Item Required Testing Status Long cylindrical core with small diameter Reflector controlled core Nuclear design method of reflector controlled core with metallic fuel Critical experiment Done High volume fraction metallic fuel core Reflector RVACS Confirmation of pressure drop in fuel subassembly Reflector drive mechanism fine movement Heat transfer characteristics between vessel and air Fuel hydraulic test Test of reflector drive mechanism Heat transfer test of RVACS Done Ongoing Done EM pump/flowmeter Steam generator (Double wall tubes) Structural integrity Stable characteristics Structural integrity Heat transfer characteristics Leak detection Sodium test of EM pump/flowmeter Sodium test of steam generator Leak detection test Ongoing Ongoing Seismic isolation Applicability to nuclear plant Test of seismic isolator Done 13/30

14 Reflector Controlled Core Critical experiment for 4S core has been successfully performed. Shutdown rod Core Reflector Photo ; FCA (offered by JAEA) Reflector controlled core R&D has been performed by CRIEPI in collaboration with JAEA as a part of Innovative Nuclear Energy System Technology (INEST) Development Projects under sponsorship of MEXT (JAPAN). 14/30

15 Toshiba Sodium Test Loop Facility Max temperature Sodium inventory Sodium flow rate 600 o C 8 ton 0 12 m 3 /min 4S full-scale EM pump Mother loop area EM pump test area 15/30

16 Full-scale Test of EM Pump Toshiba Test Facility Full-scale EM Pump The performance of the EM pump has been demonstrated for the rated power condition of 4S in February, 2010 (This study is a part of Development of high temperature electromagnetic pump with large diameter and a passive flow coast compensation power supply to be adapted into medium and small reactors of GNEP funded by METI.) 16/30

17 Electromagnetic Flow-Meter magnetic core exciting coil electrode outer duct annular flow area channnel sodium inner duct Configuration of EMF Full sector test model Test Apparatus Sector test model Electromagnetic flow-meter (EMF) for 4S EM pump was fabricated, and will be tested using sodium this year. (This study is a part of Development of a new EMF in Sodium-cooled Fast Reactor funded by MEXT.) 17/30

18 DWSG Technology Manufacturing technologies of double-wall tube have been established in (funded by METI) Welded portion of inner tube Section view 10 meter-long double-wall tube with wire mesh Laser welding machine for inner tube Tube inspection technology has been established in Double-wall tube Indirect field Assumed defect Eddy current Direct field Small defect (1.0 mmφ) on outer tube surface has been successfully detected by Remote-Field Eddy Current Technology. Exciter coil Detector coil 18/30

19 Sodium Tests Schedule JFY2008 JFY2009 JFY2010 Pre-operation Na Test (Internal funding) EM flow meter Design and Fabrication (MEXT) Na Test (Internal funding) Design and Fabrication Installation Na Test 10.6m 3 /min EM pump (METI) Design and Fabrication Installation Na Test Reflector cavity Design and Fabrication Na Test (Internal funding) Key technologies for 4S will be established by the end of this fiscal year. 19/30

20 1. 4S Design Overview 2. Technology Development 3. Economics 4. Licensing 5. Concluding Remarks 20/30

21 Economics Target cost with mass production 10 MWe 4S : competitive with diesel power plant at remote area 50 MWe 4S : slightly higher than large LWRs To achieve the target, Reduce on-site construction work by shop fabrication Mass production Reduce O&M cost by low maintenance requirements Simplified spent fuel handling system by long refueling interval To reduce initial financial cost & risk, Small reactor Flexibility to meet increased demand by modular plant deployment scheme 21/30

22 Shop Fabrication Construction at site Reactor (Shop fabrication) Building (Shop fabrication) Steel concrete composite Site construction Barge Shop fabrication reduces site work and its duration 22/30

23 Modular Concept (example) Initial phase 1st unit 4S-135 MWt T/G Electricity Multiple phase shared auxiliary facilities 2nd unit 4S-135 MWt T/G Electricity Nth unit 4S-135 MWt T/G Electricity Low initial costs & risk Cost reduction by plant standardization and shared facilities for multiple phases 23/30

24 1. 4S Design Overview 2. Technology Development 3. Economics 4. Licensing 5. Concluding Remarks 24/30

25 Licensing Schedule Pre-application Review Design Approval Design Description Long Life Metallic Fuel Seismic Base Isolation Safety Analysis PIRT I (Design Base Accident) Principle Design Criteria Technical Reporting Plan Emergency Planning Core Design Analysis Submitted Aircraft Hazard Plan I&C PIRT II (Beyond Design Base Accident) Safety design Prevention of Severe Accidents Plant Dynamics Analysis code ANS54.1 WG Toshiba and WEC are participating in the ANS54.1 WG 25/30

26 Development of 4S Principal Design Criteria CRBR SER 10CFR50 App. A ANSI/ANS-54.1 PRISM PSER 4S design concept Evaluate Accept, modify, or add new criteria Passive LWR licensing 4S PDC CRBR: Clinch River Breeder Reactor, FSER: Final Safety Evaluation Report, PRISM: Power Reactor Innovative Small Module, PSER: Preliminary Safety Evaluation Report 26/30

27 Experiences on NRC Pre-review Process No other critical issue in developing 4S PDC based on LWR GDC has been identified except sodium-related matters. GDC for sodium-cooled reactors should be established. Also, no critical issue has been identified in Regulatory Guides applicability except sodium-cooled reactor matters (not specific to 4S). The 4S design conformance to the Policy Statement on Regulation of Advanced Nuclear Power Plants has been confirmed. We are actively participating in ANS 54.1 WG. 27/30

28 1. 4S Design Overview 2. Technology Development 3. Economics 4. Licensing 5. Concluding Remarks 28/30

29 Concluding Remarks 4S design incorporates feature such as longrefueling interval, passive safety, low maintenance requirements, and high security. 4S has advantages of ease of operation and maintenance, and flexibility. 10 MWe-4S is now in progress of the pre-application review by USNRC. Toshiba is participating in the activity to establish the LMR regulatory framework. The DA application of 4S to USNRC in 2012 is planned. 29/30

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