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| Content Provider | The American Society of Mechanical Engineers (ASME) Digital Collection |
|---|---|
| Author | Nishi, Yoshihisa Kanda, Kenichi Abe, Kazuma Nishimura, Satoshi Nakamura, Koichi Furuya, Masahiro Ui, Atsushi |
| Copyright Year | 2018 |
| 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. |
| Sponsorship | Nuclear Engineering Division |
| File Format | |
| ISBN | 9780791851494 |
| DOI | 10.1115/ICONE26-82018 |
| Volume Number | Volume 6B: Thermal-Hydraulics and Safety Analyses |
| Conference Proceedings | 2018 26th International Conference on Nuclear Engineering |
| Language | English |
| Publisher Date | 2018-07-22 |
| Publisher Place | London, England |
| Access Restriction | Subscribed |
| Subject Keyword | Containment vessels Temperature Sensitivity analysis Japan 2011 Fukushima nuclear disaster Pressure Transients (dynamics) Simulation Nuclear power stations Underground injection Nuclear fission Accidents |
| Content Type | Text |
| Resource Type | Article |
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