Basic Properties and Numerical Simulations of the Radioactive Noble Gas Removal System from the Primary Coolant in PWR Nuclear Power Plant

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  • Kamishima Naoyuki
    Chemical Laboratory, Takasago Research and Development Center, Mitsubishi Heavy Industries, Ltd.
  • Nishio Hiroki
    Nuclear Plant Systems Engineering Department, Nuclear Plant Engineering Division, Nuclear Energy Systems, Mitsubishi Heavy Industries, Ltd.
  • Nishimoto Shohei
    Nuclear Plant Systems Engineering Department, Nuclear Plant Engineering Division, Nuclear Energy Systems, Mitsubishi Heavy Industries, Ltd.
  • Miyamoto Hitoshi
    Department of Environmental Engineering, Faculty of Engineering, Osaka Institute of Technology
  • Minemoto Masaki
    Department of Chemical Engineering, Faculty of Engineering, Kyushu University

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  • 加圧水型原子力プラントにおける１次冷却材からの放射性ガス除去設備の基礎特性と動特性評価
  • カアツスイガタ ゲンシリョク プラント ニ オケル 1ジ レイキャクザイ カラ ノ ホウシャセイ ガス ジョキョ セツビ ノ キソ トクセイ ト ドウトクセイ ヒョウカ

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Abstract

In the PWR nuclear power plant, radioactive gas continuously extracted from the primary coolant is reduced by decay in the long-term storage tank before being discharged into the environment. A new radioactive waste gas treatment system using a charcoal bed is expected to reduce the amount of radioactivity released and simplify the system, while improving system reliability, operation and maintenance. A charcoal bed-type of radioactive gas removal system has been designed and built based on fundamental test data, and the system gradually introduced into new plants has been operated stably. This paper introduces an outline of the system, together with an outline of the fundamental test results and dynamic simulations.

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