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論文

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

石川 淳; 玉置 等史; 杉山 智之; 丸山 結

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

Japan Atomic Energy Agency is pursuing the development and application of the integrated severe accident analysis code, THALES2/KICHE for analysis of severe accident progression and source term. The accident at the Fukushima Daiichi Nuclear Power Station (NPS) from units 1 to 3 were analyzed using THALES2/KICHE code for better understanding of the accident in the OECD/NEA BSAF2 project. This paper describes three week analysis for the accident at unit 3. The leakage through the drywell head flange and an equipment hutch was assumed in order to reproduce the tendency of drywell pressure history in addition to the intermittent activation of the containment vessel venting system via the suppression chamber. As for the source term analysis, the dominant chemical forms for cesium and iodine were assumed to be cesium iodine (CsI) and cesium molibdate (Cs$$_{2}$$MoO$$_{4}$$) based on the insights of the PHEBUS/FP experiments. The iodine chemical reaction kinetics in the containment aqueous phase, which were associated with the production of molecular iodine and organic iodide, were taken into consideration in the present analysis. The released iodine and cesium within three weeks after the earthquake were predicted to be approximately 3% and 6% of the initial inventory, respectively.

口頭

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

永瀬 文久; 吉田 啓之; 根本 義之; 天谷 政樹; 山下 真一郎

no journal, , 

福島第一原子力発電所での廃止措置を適切にかつ安全に進めるためには、事故の進展や炉内状況に関する推定精度を向上させる必要がある。また、既存の軽水炉についてもシビアアクシデント進展評価手法の改良を進めることが必要である。このため、シビアアクシデント条件下での炉内熱流動、燃料損傷及び崩落過程、構造材料及び圧力容器挙動、核分裂生成物の放出及び移行等に関し、原子力機構は基礎研究を実施している。本報告においては、それらの基礎研究の概要と最近の成果を報告する。

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