Two types of a passive safety containment for a near future BWR with active and passive safety systems |
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Authors: | Takashi Sato Makoto Akinaga Yoshihiro Kojima |
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Affiliation: | Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama, Japan |
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Abstract: | The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance. |
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Keywords: | ABWR, advanced boiling water reactor ACCS, advanced corium cooling system AFC, active fuel cladding AOT, allowable operable time BIPSS, build-in passive safety systems BWR, boiling water reactor CCFP, conditional containment failure probability CDF, core damage frequency CR, control rod CRD, control rod drive CV, containment vessel CRS, condensate return system D/G, diesel generator DBA, design basis accident DPV, depressurization valve DW, dry well ECCS, emergency core cooling system EPRI, Electric Power Research Institute, Inc. FP, fission product FW, feed water GDCS, gravity-driven cooling system GIRAFFE, gravity driven integral full-height test for passive heat removal HPCF, high-pressure core flooder HPFL, high-pressure flooder IC, isolation condenser ICSS, isolation and connection switching system IDHS, in-depth hybrid safety LOCA, loss of coolant accident LPFL, low-pressure flooder MCCI, molten core concrete interaction PCCS, passive containment cooling system PCCV, pre-stressed concrete containment vessel PCT, peak cladding temperature PCV, primary containment vessel PDS, passive dilution system PSA, probabilistic safety assessment RCCV, reinforced concrete containment vessel RCIC, reactor core isolation cooling system RCW, reactor cooling water system RHR, residual heat removal system RIP, reactor internal pump RPV, reactor pressure vessel SA, severe accident SBWR, simplified boiling water reactor SP, suppression pool SSCV, steel secondary containment vessel STUK, radiation and nuclear safety authority TAF, top of active fuel TSBWR, total safety boiling water reactor UHS, ultimate heat sink URD, utility requirement document USCV, upper secondary containment vessel WW, wet well |
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