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.

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

Analytical method for solving fluid-structure interactions in BWR pressure suppression pool

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Nucl.Eng.Des., 75, p.5 - 11, 1982/00

https://doi.org/10.1016/0029-5493(83)90072-9

no abstracts in English

Full-Scale MarkII CRT Program Data Report No.12 (TEST 1205)

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JAERI-M 9405, 121 Pages, 1981/03

JAERI-M-9405.pdf:3.02MB

no abstracts in English

Full-Scale Mark II CRT Program Data Report No.10 (TEST 1203)

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JAERI-M 9403, 122 Pages, 1981/03

JAERI-M-9403.pdf:2.78MB

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

MarkII Containment 1/6-Scale Pressure Suppression Test Program: Data Report No.3 Fourier Analysis of Pressure Oscillations; Runs214-218,276-282

JAERI-M 8667, 128 Pages, 1980/02

JAERI-M-8667.pdf:3.12MB

no abstracts in English

Full-Scale MarkII CRT Program:Data Report N0.1; TEST 0002

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JAERI-M 8598, 104 Pages, 1979/12

JAERI-M-8598.pdf:2.36MB

no abstracts in English