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.
Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 2 — Parametric Study on Fukushima-Daiichi Unit-3
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Nishi, Y, Kanda, K, Abe, K, Nishimura, S, Nakamura, K, Furuya, M, & Ui, A. "Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 2 — Parametric Study on Fukushima-Daiichi Unit-3." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06BT08A019. ASME. https://doi.org/10.1115/ICONE26-82018
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