Analytical Functions and Development Status of the System Analysis Code for Nuclear Power Plants, AMAGI

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  • KANEKO Junichi
    Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R)
  • TSUKAMOTO Naofumi
    Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R)

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  • 原子炉システム解析コードAMAGIの解析機能と開発状況
  • ゲンシロ システム カイセキ コード AMAGI ノ カイセキ キノウ ト カイハツ ジョウキョウ

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<p>　Best-estimate evaluation with detailed models of complicated phenomena that occur during accidents has been introduced into the safety evaluation of nuclear power plants. A system analysis code, which has physical models for the realistic prediction of events during accidents, is necessary for the safety evaluation. The analysis code should also be validated for individual phenomena and their combined behaviors at the actual plant scale during accidents. In this study, the system analysis code “AMAGI”, which is applicable to the evaluation of events from anticipated operational occurrences to design extension conditions, has been developed from its basic design. The thermal hydraulic model, heat conduction model, control model, and thermal power model were implemented into AMAGI as primary analytical functions. By conducting analyses of experiments with AMAGI, its fundamental models were validated.</p>

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