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Journal Articles

Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants

Kubo, Kotaro; Jang, S.*; Takata, Takashi*; Yamaguchi, Akira*

Journal of Nuclear Science and Technology, 59(3), p.357 - 367, 2022/03

 Times Cited Count:5 Percentile:64.12(Nuclear Science & Technology)

Dynamic probabilistic risk assessment (PRA), which handles epistemic and aleatory uncertainties by coupling the thermal-hydraulics simulation and probabilistic sampling, enables a more realistic and detailed analysis than conventional PRA. However, enormous calculation costs are incurred by these improvements. One solution is to select an appropriate sampling method. In this paper, we applied the Monte Carlo, Latin hypercube, grid-point, and quasi-Monte Carlo sampling methods to the dynamic PRA of a station blackout sequence in a boiling water reactor and compared each method. The result indicated that quasi-Monte Carlo sampling method handles the uncertainties most effectively in the assumed scenario.

Journal Articles

The Analysis for Ex-Vessel debris coolability of BWR

Matsumoto, Toshinori; Iwasawa, Yuzuru; Ajima, Kohei*; Sugiyama, Tomoyuki

Proceedings of Asian Symposium on Risk Assessment and Management 2020 (ASRAM 2020) (Internet), 10 Pages, 2020/11

The probability of ex-vessel debris coolability under the wet cavity strategy is analyzed. The first step is the uncertainty analyses by severe accident analysis code MELCOR to obtain the melt condition. Five uncertain parameters which are relating with the core degradation and transfer process were chosen. Input parameter sets were generated by LHS. The analyses were conducted and the conditions of the melt were obtained. The second step is the analyses for the behavior of melt under the water by JASMINE code. The probabilistic distribution of parameters are determined from the results of MELCOR analyses. Fifty-nine parameter sets were generated by LHS. The depth of water pool is set to be 0.5, 1.0 and 2.0 m. Debris height were compared with the criterion to judge the debris coolability. As the result, the success probability of debris cooling was obtained through the sequence of calculations. The technical difficulties of this evaluation method are also discussed.

JAEA Reports

A Probabilistic assessment code system for derivation of clearance levels of radioactive materials; PASCLR user's manual

Takahashi, Tomoyuki*; Takeda, Seiji; Kimura, Hideo

JAERI-Data/Code 2000-041, 108 Pages, 2001/01

JAERI-Data-Code-2000-041.pdf:4.86MB

no abstracts in English

Journal Articles

An Importance quantification technique in uncertainty analysis for computer models

Ishigami, Tsutomu; Homma, Toshimitsu

Proc. of lst Int. Symp. on Uncertainty Modeling and Analysis, p.398 - 403, 1990/12

no abstracts in English

JAEA Reports

Current status of uncertainty analysis methods for computer models

Ishigami, Tsutomu

JAERI-M 89-190, 66 Pages, 1989/11

JAERI-M-89-190.pdf:1.5MB

no abstracts in English

JAEA Reports

An importance quantification technique in uncertainty analysis for computer models

Ishigami, Tsutomu; Homma, Toshimitsu

JAERI-M 89-111, 27 Pages, 1989/09

JAERI-M-89-111.pdf:0.68MB

no abstracts in English

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