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

LOCA steam condensation loads in BWR mark II pressure suppression containment system

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Nucl.Eng.Des., 102, p.225 - 228, 1987/00

https://doi.org/10.1016/0029-5493(87)90256-1

no abstracts in English

The LOCA air-injection loads in BWR mark II pressure suppression containment systems

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Nucl.Eng.Des., 77, p.117 - 129, 1984/00

https://doi.org/10.1016/0029-5493(84)90172-9

no abstracts in English

Evaluation of Primary Blowdown Flow Rate and In-Vent Steam Mass Flux (Tests 0002、0003、0004、1101、2101、3101、 and 3102) - Full-Scale Mark II CRT Program Test Evaluation Report No.1 -

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JAERI-M 83-185, 44 Pages, 1983/10

JAERI-M-83-185.pdf:1.02MB

no abstracts in English

The Noncondensable gas effects on loss-of-coolant accident steam condensation loads in BWR pressure suppression pool

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Nuclear Technology, 63, p.337 - 346, 1983/00

https://doi.org/10.13182/NT83-A33292

no abstracts in English

Chugging desynchronization effects on multivent pressure suppression pool loads

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Transactions of the American Nuclear Society, 41, p.695 - 696, 1982/00

no abstracts in English

Full-scale MarkII CRT Program Data Report No.11 (TEST 1204)

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JAERI-M 9404, 121 Pages, 1981/03

JAERI-M-9404.pdf:2.99MB

no abstracts in English

State of JAERI full-scale mark II CRT program

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Proc.Int.Specialist Meeting on BWR Pressure Suppression Containment Technology, p.23 - 42, 1981/00

no abstracts in English

Full-Scale Mark-II CRT Program Data Report,No.8; TEST 1201

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JAERI-M 8887, 132 Pages, 1980/06

JAERI-M-8887.pdf:3.8MB

no abstracts in English