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Two types of a passive safety containment for a near future BWR with active and passive safety systems
Authors:Takashi Sato  Makoto Akinaga  Yoshihiro Kojima
Affiliation:Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama, Japan
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.
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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