Severe accident analysis with spatial discretized model by MAAP - (1) parametric study on Fukushima-daiichi Unit-2-

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

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

Abstract

Accident analyses of the Fukushima-Daiichi unit-2 nuclear power plant were performed with MAAP (Modular Accident Analysis Program) version 5.03. We assumed RCIC, SRV operation and alternative water injection in order to reproduce the measured pressure and temperature values in RPV and PCV. From parametric studies, it was found that the analysis results were in good agreement with the measured data. In this paper, the results of the parametric studies are reported. Furthermore, spatial discretization of compartments (such as rooms in the reactor building, etc.) into small parts successfully demonstrated the transient distribution and deposition of fission products (FPs) across the rooms. Such special discretization is particularly important for the forensic investigation of severe accidents and the deposited amount in the R/B might be estimated by using this detailed model.

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

Fingerprint

Accidents
Water injection
Fission products
Nuclear power plants
Temperature

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Kanda, K., Nishi, Y., Abe, K., Nishimura, S., Nakamura, K., Furuya, M., & Ui, A. (2018). Severe accident analysis with spatial discretized model by MAAP - (1) parametric study on Fukushima-daiichi Unit-2-. 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/ICONE26-82129

Severe accident analysis with spatial discretized model by MAAP - (1) parametric study on Fukushima-daiichi Unit-2-. / Kanda, Kenichi; Nishi, Yoshihisa; Abe, Kazuma; Nishimura, Satoshi; Nakamura, Koichi; Furuya, Masahiro; Ui, Atsushi.

Thermal-Hydraulics and Safety Analyses. American Society of Mechanical Engineers (ASME), 2018. (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 6B).

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

Kanda, K, Nishi, Y, Abe, K, Nishimura, S, Nakamura, K, Furuya, M & Ui, A 2018, Severe accident analysis with spatial discretized model by MAAP - (1) parametric study on Fukushima-daiichi Unit-2-. in Thermal-Hydraulics and Safety Analyses. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 6B, American Society of Mechanical Engineers (ASME), 2018 26th International Conference on Nuclear Engineering, ICONE 2018, London, United Kingdom, 18/7/22. https://doi.org/10.1115/ICONE26-82129
Kanda K, Nishi Y, Abe K, Nishimura S, Nakamura K, Furuya M et al. Severe accident analysis with spatial discretized model by MAAP - (1) parametric study on Fukushima-daiichi Unit-2-. In Thermal-Hydraulics and Safety Analyses. American Society of Mechanical Engineers (ASME). 2018. (International Conference on Nuclear Engineering, Proceedings, ICONE). https://doi.org/10.1115/ICONE26-82129
Kanda, Kenichi ; Nishi, Yoshihisa ; Abe, Kazuma ; Nishimura, Satoshi ; Nakamura, Koichi ; Furuya, Masahiro ; Ui, Atsushi. / Severe accident analysis with spatial discretized model by MAAP - (1) parametric study on Fukushima-daiichi Unit-2-. Thermal-Hydraulics and Safety Analyses. American Society of Mechanical Engineers (ASME), 2018. (International Conference on Nuclear Engineering, Proceedings, ICONE).
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