核电厂退役截流件活化填料桶表面剂量率研究

IF 0.6 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Journal of Radiation Protection and Research Pub Date : 2020-12-30 DOI:10.14407/JRPR.2020.45.4.178

K. Park, Hae-Woong Kim, Heedong Sohn, Nam-Kyun Kim, Chung-Kyu Lee, Yun-Do Lee, Jihoon Lee, Young Hwan Hwang, Mi Hyun Lee, Dong Kyu Lee, Duk Woon Jung

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引用次数: 2

摘要

结果与讨论:通过中子活化分析，评估了退役RV和RVI生产的含断片桶的剂量率。对于RV截止点，桶表面的剂量率最大值为6.97 × 10-1 mSv/hr，距离桶2 m处的剂量率最大值为3.03 × 10-2 mSv/hr。对于RVI截止点，其表面为0.166 × 10-1 mSv/hr，距离其2 m处为1.04 × 10-1 mSv/hr。除离RVI桶面2 m处的剂量率外，各RV和RVI截止片的剂量率均低于限值。为了减小桶的厚度，需要调整桶中含有高放射性成分的内容物。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Study on Dose Rate on the Surface of Cask Packed with Activated Cut-off Pieces from Decommissioned Nuclear Power Plant

Results and Discussion: Through neutron activation analysis, dose rate is evaluated for the casks containing cut-off pieces produced from decommissioned RV and RVI. For RV cut-off ones, the highest value of dose rate on the surface of cask is 6.97 × 10-1 mSv/hr and 2 m from it is 3.03 × 10-2 mSv/hr. For RVI cut-off ones, on the surface of it is 0.166 × 10-1 mSv/hr and 2 m from it is 1.04 × 10-1 mSv/hr. Dose rates for various RV and RVI cut-off pieces distributed lower than the limit except the one of 2 m from the cask surface of RVI. It needs to adjust contents in cask which carries highly radioactive components in order to decrease thickness of cask.

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来源期刊

Journal of Radiation Protection and Research Physics and Astronomy-Radiation

CiteScore

1.00

自引率

0.00%

发文量