Severe accident analysis with spatial discretized model by MAAP - (2) parametric study on Fukushima-daiichi unit-3-

Yoshihisa Nishi, Kenichi Kanda, Kazuma Abe, Satoshi Nishimura, Koichi Nakamura, Masahiro Furuya, Atsushi Ui

研究成果: Conference contribution

抄録

Accident analyses of unit 3 in the Fukushima-Daiichi nuclear power station were performed with MAAP (Modular Accident Analysis Program) 5.03. In the analysis, the operations of RCIC, HPCI, SRV were simulated and assuming the operation of alternative water injection to reproduce the measured pressure and temperature. As a result of parametric evaluation, analysis results consistent with measured values are obtained. In this paper, the results of the sensitivity analysis are reported. Simultaneously, attempts were made to analyze the transient and deposition amount of fission product (FP) in the reactor building (R/B) and a model dividing each room of R/B in detail was created to confirm the FP behavior. Based on these analyses, the deposition amount of the primary containment vessel (PCV) (drywell (D/W) and wetwell (W/W)) and R/B could be estimated using detailed model of the R/B dividing into nodes in the MAAP simulation.

本文言語English
ホスト出版物のタイトルThermal-Hydraulics and Safety Analyses
出版社American Society of Mechanical Engineers (ASME)
ISBN(印刷版)9784888982566
DOI
出版ステータスPublished - 2018 1 1
外部発表はい
イベント2018 26th International Conference on Nuclear Engineering, ICONE 2018 - London, United Kingdom
継続期間: 2018 7 222018 7 26

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
6B

Other

Other2018 26th International Conference on Nuclear Engineering, ICONE 2018
CountryUnited Kingdom
CityLondon
Period18/7/2218/7/26

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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