動力・エネルギー技術の最前線講演論文集 : シンポジウム
Online ISSN : 2424-2950
セッションID: C225
会議情報
C225 福島第1原子力発電所の非常用復水器の除熱能力評価(OS8 軽水炉・新型炉・原子力安全)
下江 知弘奈良林 直辻 雅司千葉 豪
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会議録・要旨集 フリー

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抄録
In this study, we aimed to quantitatively evaluate cooling capacity of isolation condenser (IC) for core cooling in Fukushima Daiichi Nuclear Plant Unit 1. In order to evaluate cooling capacity, we calculated decay heat which was emitted from core. We used the data of nuclear fuel and rated thermal power which is released by TEPCO. Analysis was conducted with TRAC code. We made an experiment in order to check input data for IC. Because analysis data was close to experimental data, we made sure of validity of input data. We analyzed IC under conditions which were recorded when IC started up and tsunami rushed toward plant. As a result of analysis, we confirmed that cooling capacity exceed decay heat under both conditions. In conclusion, IC had a capacity to prevent core meltdown accident in Fukushima Daiichi Nuclear Plant Unit 1.
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© 2012 一般社団法人 日本機械学会
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