自然通風型低レベル放射性廃棄物貯蔵施設の熱流動特性評価 Evaluation of Thermal Hydraulics Characteristics of Natural Cooling Low Level Radioactive Waste Storage System

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著者

    • 吉井 敏浩 YOSHII Toshihiro
    • (株)東芝 電力システム社 電力・社会システム技術開発センター Power and Industrial Systems Research and Development Center, Toshiba Corporation
    • 岩城 智香子 IWAKI Chikako
    • (株)東芝 電力システム社 電力・社会システム技術開発センター Power and Industrial Systems Research and Development Center, Toshiba Corporation
    • 碓井 伸彦 USUI Nobuhiko
    • (株)東芝 電力システム社 磯子エンジニアリングセンター Isogo Nuclear Engineering Center, Toshiba Corporation
    • 渡辺 久夫 WATANABE Hisao
    • (株)東芝 電力システム社 磯子エンジニアリングセンター Isogo Nuclear Engineering Center, Toshiba Corporation
    • 池田 達實 IKEDA Tatsumi
    • (株)東芝 電力システム社 電力・社会システム技術開発センター Power and Industrial Systems Research and Development Center, Toshiba Corporation
    • 池田 浩 IKEDA Hiroshi
    • (株)東芝 電力システム社 電力・社会システム技術開発センター Power and Industrial Systems Research and Development Center, Toshiba Corporation
    • 正木 嘉一 MASAKI Yoshikazu
    • (株)東芝 電力システム社 磯子エンジニアリングセンター Isogo Nuclear Engineering Center, Toshiba Corporation

抄録

  It is necessary to design a low level radioactive waste storage system so that the decay heat of radioactive waste does not breach the structural safety limit. Currently, this waste storage system is designed as a natural cooling system, which continuously cools the radioactive waste without an active device. It consists simply of a storage pit for radioactive waste and air inlet and outlet ducts. The radioactive waste is cooled by natural convective air flow, which is generated by the buoyancy of heated air due to the decay heat of radioactive waste. It is important to clarify the flow characteristics in the systems in order to evaluate the cooling performance. The air mass flow rate through the system is determined by the balance between the natural convective flow force and pressure loss within the system. Therefore, the pressure drop and flow pattern in the waste storage pit are important flow characteristics. In this study, the pressure drop and air temperature distribution, greatly influenced by the flow pattern in the pit, were measured using a 1/5 scale model and compared with the results obtained from CFD. Flow network analysis, which is a simple model that simulates the flow by nodes and junctions, was conducted and its validity was confirmed by experimental results and CFD.<br>

収録刊行物

  • 日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan

    日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan 11(1), 91-100, 2012-03-01

    一般社団法人 日本原子力学会

参考文献:  5件中 1-5件 を表示

各種コード

  • NII論文ID(NAID)
    10030136650
  • NII書誌ID(NCID)
    AA11643165
  • 本文言語コード
    JPN
  • 資料種別
    ART
  • ISSN
    13472879
  • NDL 記事登録ID
    023557415
  • NDL 請求記号
    Z74-C788
  • データ提供元
    CJP書誌  NDL  J-STAGE 
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