著者

小林 健介 堀井 英雄 石神 努 千葉 猛美

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.27, no.1, pp.56-65, 1985-01-30 (Released:2009-04-21)

参考文献数

10

被引用文献数

1 1

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A sensitivity analysis of thermal hydraulic response in containment during a 'station blackout' (the loss of all AC power) accident at Browns Ferry unit one plant was performed with the computer code MARCH 1.0. In the analysis, the plant station batteries were assumed to be available for 4h after the initiation of the accident. The thermal hydraulic response in the containment was calculated by varying several input data for MARCH 1.0 independently and the deviation among calculated results were investigated.The sensitivity analysis showed that (a) the containment would fail due to the overtemperature without any operator actions for plant recovery, which would be strongly dependent on the model of the debris-concrete interaction and the input parameters for specifying the containment failure modes in MARCH 1.0, (b) a core melting temperature and an amount of water left in a primary system at the end of the meltdown were identified as important parameters which influenced the time of the containment failure, and (c) experimental works regarding the parameters mentioned above could be recommended.

著者

小林 健介 石神 努 浅香 英明 秋元 正幸

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.27, no.12, pp.1093-1101, 1985-12-30 (Released:2009-04-21)

参考文献数

23

著者

石神 努 小林 健介

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.35, no.6, pp.549-560, 1993-06-30 (Released:2010-04-19)

参考文献数

7

被引用文献数

1 1

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As a part of the preparation of the database of calculated results on severe accident sequences for emergency preparedness at nuclear power plants, steam generator tube rupture initiated severe accident sequences at a reference two-loop PWR plant have been analyzed using the THALES/ART computer code. Estimation were made of the times of key events such as core uncovery, core melt and reactor vessel melt-through, and an amount of fission products released to the environment. The effects of recovery action on core integrity and the amount of environmental fission products released were studied with regard to the discussion on mitigation of or recovery from the accident by the feed and/or bleed operation in the primary and/or the secondary system. The analysis showed that (1) the ECCS has adequate capability of maintaining core integrity, and (2) the bleed operation in the primary system is effective to suppress the environmental fission products released even if the ECCS did not function.

著者

梅本 通孝 熊谷 良雄 小林 健介 石神 努 渡辺 実 室崎 益輝 大西 一嘉

出版者

地域安全学会

雑誌

地域安全学会論文報告集

巻号頁・発行日

no.7, pp.228-233, 1997-11

被引用文献数

1

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The Great Hanshin-Awaji Earthquake Disaster caused an LPG leak incident at a plant in Higashinada ward, Kobe city. Kobe municipal authorities announced evacuation recommendation to 72,000 inhabitants. A questionnaire was conducted to know when, where and how the inhabitants received the information of evacuation recommendation. Results of the questionnaire are as follows : ・In the day the evacuation order was announced, 9.9% of inhabitants in the recommendation area concerned did not receive the information of the recommendation. ・The farther from the plant where the incident happened, the more lately inhabitants received the information of the recommendation. ・Though about 80% of people who received the information of the recommendation become aware of the cause of it, many of them didn't know the further information.