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Measurement and analysis of in-vessel component activation and $$gamma$$ dose rate distribution in Joyo

「常陽」原子炉容器内構造物の放射化量と$$gamma$$線量率分布の測定評価

前田 茂貴  ; 内藤 裕之; 伊藤 主税  ; 青山 卓史 

Maeda, Shigetaka; Naito, Hiroyuki; Ito, Chikara; Aoyama, Takafumi

ナトリウム冷却型高速炉の炉内構造物の放射化量評価、及び原子炉容器内の観察に供するファイバースコープの放射線劣化評価に資するため、冷却材ナトリウムをドレンした状態で、「常陽」原子炉容器内の$$gamma$$線量率分布を測定評価した。実機で想定される広域の線量率をカバーし、約200$$^{circ}$$Cの高温環境に耐える$$gamma$$線量率測定装置を製作し、$$^{60}$$Co校正照射施設で$$gamma$$線検出器の校正曲線及び温度特性を確認した。測定の結果、原子炉容器内の主要構造物の線源強度と$$gamma$$線量率分布を把握できた。実測した$$gamma$$線量率を点減衰核積分法計算コードQAD-CGGP2による計算値と比較した結果、C/E:1.3$$sim$$2.7が得られ、放射化計算及び遮へい計算の精度を確認した。

In-vessel $$gamma$$ rate measurements have been conducted in the experimental fast reactor Joyo to obtain experimental data and to verify the analysis method. The in-vessel $$gamma$$ dose with cooling times of 500 and 700 days after reactor shutdown was measured in Joyo which had been operated for approximately 30 years. The $$gamma$$ dose was calculated using QAD code with the $$gamma$$ source obtained by ORIGEN2 code. The ratios between the calculated and experimental value was ranged 1.3 and 2.7. The accuracy of analys method for the amount and distribution of radioactive products and $$gamma$$ ray dose inside reactor vessel was confirmed for the in-vessel inspection or repair.

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