Systematic source term analysis for level 3 PSA of a BWR with Mark-II type containment with THALES-2 code

Ishikawa, Jun; Muramatsu, Ken; Sakamoto, Toru*

JAERI-Research 2005-021, 133 Pages, 2005/09

JAERI-Research-2005-021.pdf:7.58MB

The THALES-2 code is an integrated severe accident analysis code in order to simulate the accident progression and transport of radioactive material for probabilistic safety assessment (PSA) of a nuclear power plant, a part of a level 3 PSA being performed at JAERI for a 1,100MWe BWR-5 with a Mark-II containment. Results and insights from the analyses were that (1) the calculated release fractions of CsI and CsOH to the environment were in the range of 0.01 to 0.1 for late containment overpressure failure cases, and the release fractions for the containment venting case were one order of magnitude smaller than that of over-pressure case and those for drywell spray recovery cases where no containment failure occurred were two orders of magnitude smaller than the containment venting cases, (2) the governing factors for source terms of Iodine and Cesium are different depending on whether the containment fails before core melt or not, (3) the containment venting, which is one of the accident management measures, can be expected to reduce source terms if suppression pool bypass is avoided.

Analysis of direct containment heating in a BWR Mark-II containment

*; Muramatsu, Ken; *; Sakamoto, Toru*

ANS Proc. of the 1992 National Heat Transfer Conf., p.386 - 400, 1993/00

no abstracts in English

Full-Scale Mark-II CRT Program Data Report,No.9; TEST1202

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JAERI-M 8961, 121 Pages, 1980/07

JAERI-M-8961.pdf:2.67MB

no abstracts in English

Reference Core Design Mark-III of the Experimental Multi-Purpose VHTR; Study of Nuclear and Thermohydraulic Characteristics for Design of main Core Parameters

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JAERI-M 8546, 107 Pages, 1979/11

JAERI-M-8546.pdf:2.5MB

no abstracts in English