Variations of a passive safety containment for a BWR with active and passive safety systems |
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| Authors: | Takashi Sato Yoshihiro Kojima |
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| Affiliation: | aToshiba Corporation, IEC, Gen-SS, 8, Shinsugita-Cho, Isogo-Ku, Yokohama, Japan |
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| Abstract: | The paper presents variations of a certain passive safety containment for a near future BWR. It is tentatively named Mark S containment in the paper. It uses the operating dome as the upper secondary containment vessel (USCV) to where the pressure of the primary containment vessel (PCV) can be released through the upper vent pipes. One of the merits of the Mark S containment is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. Another merit is the capability to submerge the PCV and the reactor pressure vessel (RPV) above the core level by flooding water from the gravity-driven cooling system (GDCS) pool and the upper pool. The third merit is robustness against external events such as a large commercial airplane crash owing to the reinforced concrete USCV. The Mark S containment is applicable to a large reactor that generates 1830 MW electric power. The paper presents several examples of BWRs that use the Mark S containment. In those examples active safety systems and passive safety systems function independently and constitute in-depth hybrid safety (IDHS). The concept of the IDHS is also presented in the paper. |
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| Keywords: | ABWR, advanced boiling water reactor ABWR-II, advanced boiling water reactor-II AC, alternating current ACR, advanced CANDU reactor AFC, active fuel cladding ALWR, advanced light water reactor AOT, allowable operable time ASD, adjustable speed drive BWR, boiling water reactor CCFP, conditional containment failure probability CDF, core damage frequency CFR, code of federal regulations CR, control rod CRD, control rod drive CV, containment vessel D/G, diesel generator DBA, design basis accident DW, dry well ECCS, emergency core cooling system EDF, Electricité de France EPRI, Electric Power Research Institute Inc. EUR, European utility requirements for LWR nuclear power plants FMCRD, fine motion control rod drive FP, fission product FW, feed water GDCS, gravity-driven cooling system GIRAFFE, gravity driven integral full-height test for passive heat removal HCU, hydraulic control unit HPCF, high-pressure core flooder HPFL, high-pressure flooder HVAC, heating ventilation and air conditioning IC, isolation condenser ICSS, isolation and connection switching system IDHS, in-depth hybrid safety IORV, inadvertent openings of safety relief valves LOCA, loss of coolant accident LPFL, low-pressure flooder LWR, light water reactor NRC, Nuclear Regulatory Commission PCCS, passive containment cooling system PCCV, pre-stressed concrete containment vessel PCT, peak cladding temperature PCV, primary containment vessel PSA, probabilistic safety assessment R/B, reactor building RCCV, reinforced concrete containment vessel RCIC, reactor core isolation cooling system RCW, reactor coolant water system RHR, residual heat removal system RIP, reactor internal pump RPV, reactor pressure vessel RSW, reactor sea water system RWCU, reactor water clean up system SBWR, simplified boiling water reactor SGTS, standby gas treatment system SP, suppression pool SSE, safe shutdown earthquake TAF, top of active fuel TMI 2, Three Mile Island 2 TSBWR, total safety boiling water reactor USCV, upper secondary containment vessel WW, wet well |
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