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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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.

Original languageEnglish
Title of host publicationThermal-Hydraulics and Safety Analyses
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9784888982566
DOIs
Publication statusPublished - 2018 Jan 1
Externally publishedYes
Event2018 26th International Conference on Nuclear Engineering, ICONE 2018 - London, United Kingdom
Duration: 2018 Jul 222018 Jul 26

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume6B

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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    Nishi, Y., Kanda, K., Abe, K., Nishimura, S., Nakamura, K., Furuya, M., & Ui, A. (2018). Severe accident analysis with spatial discretized model by MAAP - (2) parametric study on Fukushima-daiichi unit-3-. In Thermal-Hydraulics and Safety Analyses (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 6B). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE26-82018