Abstract In this study, a dismantling scenario was developed, and the internal dose of a worker was estimated during bio-shield dismantling of Kori nuclear power plant unit#1 for radiological safety assessment internal exposure of workers to bio-shield dismantling. The internal dose was estimated from the analysis of radioactivity concentration of five main radionuclides (including 3H, 55Fe, 60Co, 152Eu, and 154Eu) of radioactive concrete using MCNP and the cutting scenario of a dismantling worker was designed. The internal dose of a worker during Diamond Wire Saw(DWS) cutting was calculated as 1.44 mSv for dry cutting and 5.03 μSv for wet cutting. The cutting time for dry cutting was 1.43 times higher and the air release fraction was approximately 200 times larger compared to wet cutting. Most of the calculated exposures were based on work conducted in a highly contaminated area; this work is expected to be completed within 2000 h. Therefore, the estimated results could be directly compared to the annual dose limits. The results of this study would be useful for the preparation of dismantling work procedures of the bio-shield of Kori nuclear power plant unit#1 in accordance with radiation safety measures.

中文翻译：

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古里核电站#1机组生物防护罩拆除过程中职业内照射计算

摘要 本研究开发了一个拆除情景，估算了古里核电站#1 号机组生物防护罩拆除过程中工人的内剂量，以评估工人在生物防护罩拆除过程中的放射安全内照射。使用MCNP对放射性混凝土的5种主要放射性核素（包括3H、55Fe、60Co、152Eu和154Eu）的放射性浓度进行分析，估算了内剂量，并设计了拆除工人的切割场景。金刚石线锯 (DWS) 切割过程中工人的内部剂量计算为干切割为 1.44 mSv，湿切割为 5.03 μSv。干切削的切削时间是湿切削的 1.43 倍，空气释放率大约是湿切削的 200 倍。大多数计算出的暴露量是基于在高度污染区域进行的工作；这项工作预计将在 2000 小时内完成。因此，估计结果可以直接与年剂量限值进行比较。本研究结果对按照辐射安全措施制定古里核电站#1机组生物防护罩拆除工作程序具有重要意义。