Development Project of Supercritical-water Cooled Power Reactor

Transcription

1 Development Project of Supercritical-water Cooled Power Reactor 1 Information exchange meeting between US institutes and JP team June-July, 2002 K. Kataoka Toshiba Co.

2 Presentation overview 2 Potentials Four advantages On going R&D project Plant conceptual design Thermohydraulics Material & water chem. R&D steps; moving forward Black smoker Water depth: 2600 m Temperature: 300ºC

3 SCPR potentials 3 Improved power generation High thermal efficiency System simplification Compact, small volume No recirculation/separators steam generators Proven technologies LWRs, FBR, GCR SCW fossil plants Flexible core design SCW coolability Fast/thermal spectrum Supercritical-water Cooled Power Reactor

4 Improved power generation 4 SCPR Temperature ( C) BWR Thermal efficiency Pressure (MPa) Regenerative stages: 6 Condenser pressure: 5 kpa

5 System simplification 5 Reactor Steam-water separation system Pressurizer Steam generator Turbine/Generator Turbine/Generator Turbine/Generator Reactor Recirculation system Reactor SCPR ABWR PWR

6 Proven technologies 6 SCW turbine cross-sectional view Nanao-Ota #2 fossil power station 700 MWe, TCF4F40", 246 kg/cm 2 g, 593/593 C

7 Flexible core design 7 50 Specific heat (kj/kg/k) MPa 24 MPa SCW coolability (high heat capacity) Flexible core design (High/low moderation) Fast/thermal spectrum Temperature (ºC)

8 SCPR R&D steps Start Basic Viable Demonst -rative Goal U Tokyo National, utility joint project JP NERI International project CA, EU, JP, RU, US, etc. Demo plant construction

9 SCPR R&D project 9 Organization: U Tokyo, Kyushu U, Hokkaido U, Hitachi and Toshiba Hokkaido U Duration: FY2000-FY2004 Budget: max. 100 M /year Support: IAE (METI), Japan Study themes Plant conceptual design Nuclear boiler Safety systems Turbine islands, etc. Thermohydraulics R22 tests and analyses Material & water chemistry Cladding & structure material Kyushu U U Tokyo Toshiba Hitachi

10 Plant conceptual design Reference concept: SCLWR (U Tokyo) PCV CRD SRV MSIV Turbine 10 Wet well Dry well RPV Core AFS Condenser Fuel assembly Demineralizer LPCI Suppres -sion pool Lower dry well Condensate water tank Main feedwater pump Feedwater heater Reference plant system Reactor vessel

11 Thermohydraulics Test conditions & items Fluid Sys. P M flux H flux SCPR Water P pc = 22 MPa T pc = 647K 25 MPa (1.1P pc ) 1200 kg/m 2 /s (rated) 620 kw/m 2 (rated) Test R22 P pc = 5 MPa T pc = 369K 5.5 MPa (1.1P pc ) kg/m 2 /s kw/m 2 Single tube 11 Fluid channel Heated tube FY : Steady state tests FY2002: Transient tests Single rod Heated rod FY : Steady state tests Fluid channel Geometry Bundle Rod dia. = 8 mm Pitch = 9.5 mm Di=4.4 mm FY : Steady state tests

12 Thermohydraulics Test section & supercritical R22 loop 300 Upper flange Upper electric conductor Heater Lower electric conductor Active heating length: 2000 mm 700 Lower flange Upper power connecter Thermo -couples Inner dia : 4.4 mm Thickness : 0.8 mm Test section support Thermal insulator Lower power connecter Electric insulator 12

13 Thermohydraulics Single tube test results 13 Heat transfer deterioration Heat transfer deterioration D-13mm P=5.5MPa G=400 kg/(m 2 /s) q kw/m2 4.4 mm 13 mm

14 Thermohydraulics Heat transfer correlations mm 13 mm

15 Material & Water Chemistry Material screening STEP 1: Candidates 15 Fossil field SS, Ni alloys Waste field Ni, Ti alloys LMFBR field Ni alloys, SS STEP 2: Tests Simulated Irradiation Corrosion SCC Mechanical STEP 3: Material application Element additive Fine graining Mono crystallization Promising candidates

16 Material & Water Chemistry Candidate materials Stain -less steel N i a llo y Austen itic Ferritic Corrosion resistance Good Poor Excellent Radiation resistance Data lim ite d Data lim ite d Data lim ite d Hightem p. Good Good Good Ti alloy Excellent No data Poor Examples 16 SS304H SS310 SS316 SS316L 12Cr-1Mo1W VNb Mod. 12Cr-1Mo A llo y 690 A llo y 718 A llo y 800H A llo y 825 H a ste llo y C22 H a ste llo y C276 NCF600 NCF625 Ti-3A l-2.5v Ti-6A l-4v Ti-15V-3Al-3Sn- Ti-15Mo-5Zr-3Al

17 Material & Water Chemistry TEM observation after electron beam irradiation SUS nm 450 C, 550 C Void formation 100nm NCF nm NCF nm Little void 450 C, 550 C Dislocation loops

18 Material & Water Chemistry Evaluation test of corrosion resistance 18 General corrosion SCC susceptibility Ion exchange resin 20 mm 70 mm N 2 N 2 +O 2 Control Tank P DO µs Cooler Test specimen 20 mm Double U-bend test specimen Test section SSRT Max. temp.: 600 C Max. pres.: 30 MPa P Heat exchanger Heater

19 Material & Water Chemistry SCW chemistry & radiolysis Fundamental aspects of SCW at elevated temperature 19 Thermodynamics Electrochemistry Radiolysis Gathering information from variety of industries LWR technologies Fossil power plants Waste processing plants Earth science System development Clean up Chemical control Manned Research Submersible "SHINKAI 6500" Maximum operation depth: 6,500m

20 SCPR R&D steps; moving forward Start Basic Viable Demonst -rative Goal U Tokyo National, utility joint project JP NERI Role of of viable step: To To minimize costly-demonstrative R&D US, EU, JP, etc. International project Demo plant construction

21 R&D items in the viable step (Designs) Core design optimization FA, CR integrity, neutronics, thermohydraulics Reactivity coefficients/control, CR reliability RPV, internals structure & MS systems Thermal expansion/stress/fatigue & radiation damages Load, heat transfer (SRVs, suppression pools) Manufacturability, maintainability Turbine, startup systems Design optimization without reheating Cleanup, water chemistry control systems Safety systems (licensing) Safety criteria, system design, startup signals/logic Severe accident measures General arrangement, etc. 21 U Tokyo design D. advancing JP NERI to Demo. step Fast option International PJ H-T, P structure (H-T reactors') New JP NERI

22 R&D items in the viable step (Thermohydraulics) Heat transfer & pressure drop (develop equations) Geometric influences Bundle, spacer/grid, HT enhancers Flow direction Abnormal conditions Low-flow high-heat-flux P, T, flow transient conditions Peaking, stability, natural convection 22 Kyushu U tests JP NERI to Demo. step Large scale tests Code validation Performance demo. Orifice design, operation map Water rod/gap design Others Oversea facilities Int'l benchmark Critical flow (develop equations) Flushing during depressurization Fundamental Direct heat transfer in suppression pools Fuel ballooning during depressurization Universities System response Venders & inst.

23 R&D items in the viable step (Mat. & water chem.) Screening fuel cladding, reactor materials Many candidates SS, Ni alloys, Ti alloys Additive, surface treatment Various properties under wide range of conditions Mechanical strength, creep Corrosion, SCC Embitterment Radioactive transport CP, FP solubility in SCW G value Principle of SCW chemistry controlling, cleanup 23 Screening (JP NERI) Need more data Int'l collaboration Reactor tests Lack of data Radiolysis etc. Chemistry control methods/effects Filters, separators, etc. New JP PJ Int'l collaboration

24 R&D items in the demonstrative step Reactor irradiation tests in SCW Cladding materials Reactor structure materials SCW Radiolysis & mass transfer Full bundle SCW tests 24 Large PJ National PJ Utilities' PJ Validation of HT equations Flow distribution, HT enhancement System response under normal/transient conditions Systems/components performance/reliability tests CRD, safety systems Structures Water chemistry controlling Start-up systems, etc. Detail design & construction of a demo-plant Int'l PJ

25 Summary of our R&D scope Start Basic Viable Demonst -rative Goal 25 Current JP NERI JP NERI (H-T, P struct.) MEXT (Water chem.) --> Systems INERI (Mat. W chem.) --> Reactor tests INERI (T/H) --> Large bundle R&D Demo test, plant design, const.

26 R&D international collaboration R&D item Design (concept to basic) Thermal Fast H-T, P structure Materials, structure Manufacturing Thermohydraulics Fundamental System responses Mat. & Water Chem. Cladding, etc. Fundamental Systems Demo plant Detail design Construction, etc. RUSSIA IPPE RIAR Supporters Large T/H facilities Irradiation reactor JAPAN METI (IAE) MEXT University, institute JAERI U Tokyo Kyushu U Hokkaido U Utilities TEPCO (past) Venders Toshiba, Hitachi Int'l collaboration I-NERI Current JP NERI, new proposal on H-T, P structure Proposal on water chemistry Concept, T/H, Water chem. R22 tests Material study CANADA AECL Concept? EU EC (FP5&6) Institutes FZK Core design CEA, KFKI, PSI, VTT Venders ANP Utilities EdF Demo plant? USA DOE (NERI, Gen4) University, institute INEEL T/H, Irradiation reactor Demo plant? ANL Water chem. MIT Materials Michigan Materials Wisconsin Venders WH Concept Materials, T/H 26

27 Development Project of Supercritical-water Cooled Power Reactor 27 Thank you