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.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5149-4
PROCEEDINGS PAPER
Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 1 — Parametric Study on Fukushima-Daiichi Unit-2
Satoshi Nishimura,
Satoshi Nishimura
CRIEPI, Yokosuka-shi, Japan
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Koichi Nakamura,
Koichi Nakamura
CRIEPI, Yokosuka-shi, Japan
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Masahiro Furuya,
Masahiro Furuya
CRIEPI, Yokosuka-shi, Japan
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Atsushi Ui
Atsushi Ui
CRIEPI, Yokosuka-shi, Japan
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Kenichi Kanda
CRIEPI, Tokyo, Japan
Yoshihisa Nishi
CRIEPI, Tokyo, Japan
Kazuma Abe
CRIEPI, Tokyo, Japan
Satoshi Nishimura
CRIEPI, Yokosuka-shi, Japan
Koichi Nakamura
CRIEPI, Yokosuka-shi, Japan
Masahiro Furuya
CRIEPI, Yokosuka-shi, Japan
Atsushi Ui
CRIEPI, Yokosuka-shi, Japan
Paper No:
ICONE26-82129, V06BT08A031; 6 pages
Published Online:
October 24, 2018
Citation
Kanda, K, Nishi, Y, Abe, K, Nishimura, S, Nakamura, K, Furuya, M, & Ui, A. "Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 1 — Parametric Study on Fukushima-Daiichi Unit-2." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06BT08A031. ASME. https://doi.org/10.1115/ICONE26-82129
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