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Journal Articles

Analysis for the accident at Unit 3 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 project

Ishikawa, Jun; Tamaki, Hitoshi; Sugiyama, Tomoyuki; Maruyama, Yu

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.536 - 547, 2019/08

Oral presentation

Fundamental studies to improve analysis of accident progression at Fukushima Daiichi NPP

Nagase, Fumihisa; Yoshida, Hiroyuki; Nemoto, Yoshiyuki; Amaya, Masaki; Yamashita, Shinichiro

no journal, , 

In order to conduct decommissioning of the Fukushima-Daiichi NPP properly and reliably, increase of accuracy is required in estimation of the accident progress and status inside the reactors. It is also required to improve analytical methods to estimate severe accident progression in the existing light water reactors. Therefore, JAEA conducts fundamental studies in terms of thermal hydraulic behaviour in reactor, fuel damage and degradation process, behaviour of structural materials and pressure vessel, release and migration of fission products, and so on under severe accident conditions. The present paper reports overview of the fundamental studies and recent results.

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