B135 非常用復水器を用いた原子炉減圧・冷却システム(OS3 軽水炉・新型炉・原子力安全(3))

• 奈良林 直

  北大

• 下江 知弘

  北大

• 千葉 豪

  北大

• 辻 雅司

  北大

• 坂下 弘人

  北大

• 秋本 肇

  JAEA

書誌事項

タイトル別名

• B135 Evaluation on Decay Heat Removal Capability of Isolation Condenser for Depressurization iand Cooling System

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, decay heat emitted from fuels in reactor core was calculated. We used the data of nuclear fuel and rated thermal power which is released by TEPCO. We analyzed IC with TRAC code. We made an experiment in order to check IC's input data. Because analysis data is close to experimental data, we made sure validity of input data. We analyzed IC under conditions which are 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 capability to prevent core meltdown accident in Fukushima Daiichi Nuclear Plant Unit 1.

収録刊行物

• 動力・エネルギー技術の最前線講演論文集 : シンポジウム

  動力・エネルギー技術の最前線講演論文集 : シンポジウム 2014.19 (0), 73-74, 2014

  一般社団法人 日本機械学会

キーワード

• Isolation Condenser
• TRAC code
• Fukushima Daiichi Nuclear Plant Unit 1
• core cooling

詳細情報

• CRID: 1390282680861759232
• NII論文ID: 110009960227
• DOI: 10.1299/jsmepes.2014.19.73
• ISSN: 24242950
• Web Site: https://www.jstage.jst.go.jp/article/jsmepes/2014.19/0/2014.19_73/_pdf
• 本文言語コード: ja
• データソース種別:
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  • Crossref
  • CiNii Articles
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