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福島第一原子力発電所廃炉のためのプラント内線量率分布評価と水中デブリ探査に係る技術開発,5; 格納容器内の線量率分布予測

Technology development to evaluate dose rate distribution and to search for fuel debris submerged in water for decommissioning of Fukushima Daiichi Nuclear Power Station, 5; Prediction of dose rate distribution in primary containment vessel

奥村 啓介 ; Riyana, E. S. ; 佐藤 若英*; 前田 裕文*; 片倉 純一*

Okumura, Keisuke; Riyana, E. S.; Sato, Wakaei*; Maeda, Hirobumi*; Katakura, Junichi*

燃料の燃焼計算及び構造材放射化計算、並びに、IRIDによる内部調査及び事故進展解析の結果に基づき、PHITSコードを用いて福島第一原子力発電所1号機の格納容器内の3次元線量率分布を予測した。

Based on the results of fuel burn-up calculations and activation calculations for structural materials and on those of severe accident progression analyses and internal investigations by IRID, we predicted a three-dimensional dose rate distribution in the containment vessel of Unit 1 at the Fukushima Daiichi Nuclear Power Station.

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