Development Projects of Supercritical-water Cooled Power Reactor (SCPR) in JAPAN

Transcription

1 Development Projects of Supercritical-water Cooled Power Reactor (SCPR) in JAPAN Information Exchange Meeting on SCWR Development 1 November 19, 2002 The University of Tokyo Toshiba Corp. Hitachi, Ltd. Kyushu University Hokkaido University

2 Background SCPR s potential advantages Japanese R&D pioneered (in 1989) and lead by the Univ. of Tokyo A Joint Study among a Japanese utility and vendors( ) Technical feasibility verified Economical feasibility mainly dependent on outlet coolant temp. Flexible core design - thermal - fast System simplification/reduction - No recirculation system - No separators/dryers - No steam generators Improved thermal efficiency Applicability of existing technologies of LWRs & SCW fossil power plants 2

3 Studies of the University of Tokyo 3 Core design of thermal reactors Core design of fast reactors Plant heat balance, thermal efficiency Safety systems & criteria Transient and accidents analyses LOCA analyses, PSA Plant control, start-up & stability

4 SCPR Development Project Japanese SCPR R&D project proceeding from FY2000 through FY Plant conceptual design The design of the University of Tokyo referred Alternatives for optimizations Thermal-hydraulics of supercritical fluid Heat transfer tests of R22 (Steady state/transient) Heat transfer simulation by analyses Materials Material screening - Corrosion tests - Electron irradiation tests

5 Plant conceptual design CRD PCV SRV MSIV Turbine 5 Wet well Dry well RPV Core AFS Condenser Fuel assembly Demineralizer LPCI Suppres sion pool Lower dry well Condensate water tank Reference plant system Main feedwater pump Feedwater heater RPV

6 Core & fuel design 6 High coolant outlet temp.500 Low outlet coolant density (1/4 of BWR, 1/7 of PWR) many water rods in fuel subassembly axial power flattening by enrichment split and gadolinia Low core coolant flow rate (1/8 of BWR,1/12 of PWR) need to enhance coolant velocity in fuel channels No steam water separation adjusting power/flow ratio of fuel subassembly by orifice flattening subchannel flow distribution Water rods Control rod 30.12cm Fuel rod301

7 Thermal-hydraulics of supercritical fluid Supercritical fluid heat transfer including deterioration Lots of correlations from SCW FPP experiences Specific conditions for SCPR Small hydraulic diameter Multi-rods with grid-spacers Transient heat transfer tests Wall temperature T w C Heat transfer coefficient kw/(m 2 K) D = 4.4 mm P = 5.5 MPa G = 400 kg/(m 2 s) q kw/m T b h pc h pc T pc Bulk fluid enthalpy h b kj/kg Single-tube test results (Kyushu University) Dittus-Boelter 7

8 Heat Transfer Analysis by Numerical Simulations X Comparison between simulation and experiment Jones-Launder 2.33x10 5 W/m 2 heat flux -> heat transfer coeff. good agreement with experiment by Yamagata et al. 2 [W/m C] Dittus-Boelter 4.65x x10 5 Simulation provides conservative result Yamagata et al. (Experiment) Present calculation 2.0 H [J/kg] b 3.0 X 10 6

9 Material 9 Cladding material tests Screening from existing materials High-temp. strength Corrosion & SCC Irradiation Structural materials Existing materials Low cobalt Test results of SCC susceptibility

10 Project on Water Chemistry of SCW To understand water chemistry under SCW conditions 10 Project planned to be started in FY2002 through irrad. SCW loop (up to 600C, MPa) Radiolysis of Water G-values, rate constants... Radiation Effect at Interface corrosion under radiation field Behavior of Corrosion Products solubility measurement - thermodynamic analysis monitoring - electrochemical potential, ph... -potential measurement of crud and colloid

11 Candidate areas of collaborations Information exchange meetings 11 Thermal-hydraulic tests of SC fluids Different fluid tests Test matrix sharing Single tube to Full bundle Material tests Test matrix sharing Electron vs. neutron irradiation Others Water chemistry Safety (e.g. Safety analysis cross check)

12 Summary SCPR R&D projects proceeding in JAPAN 12 Major R&D items Plant conceptual design Thermal-hydraulics of SC fluid Materials Water chemistry Collaborative R&D Information exchange meetings Thermal-hydraulic tests of SC fluids Material tests Others