研究堆退役处置用过滤器的放射化学分析

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-12-30 DOI:10.7733/jnfcwt.2022.035

Kyungwon Suh, Jung Bo Yoo, K. Choi, Gi-Yong Kim, Si-duk Oh, Kanghyun Yoo, Kwang Eun Lee, S. Lee, Young Sang Lee, Hyeju Lee, Junhyuck Kim, K. Jung, Sora Choi, T. Park

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引用次数: 1

摘要

核设施的退役会产生各种受放射性污染的废物。此外，拆解活动，包括在设施现场切割、包装和清理，会产生二次放射性废物，如过滤器、树脂、塑料和衣服。确定这种废物的放射性核素含量是确定包括分类和处置在内的适当管理战略的重要步骤。在这项工作中，我们对韩国研究堆(KRRs) 1和2退役期间使用的过滤器的放射性核素活性进行了放射化学表征。结果表明:过滤样品主要含有3 H (500 ~ 3600 Bq·g−1)、14 C (7.5 ~ 29 Bq·g−1)、55 Fe (1.1 ~ 7.1 Bq·g−1)、59 Ni (0.60 ~ 1.0 Bq·g−1)、60 Co (0.74 ~ 70 Bq·g−1)、63 Ni (0.60 ~ 94 Bq·g−1)、90 Sr (0.25 ~ 5.0 Bq·g−1)、137 Cs (0.64 ~ 8.7 Bq·g−1)和152 Eu (0.19 ~ 2.9)

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Radiochemical Analysis of Filters Used During the Decommissioning of Research Reactors for Disposal

The decommissioning of nuclear facilities produces various types of radiologically contaminated waste. In addition, dismantlement activities, including cutting, packing, and clean-up at the facility site, result in secondary radioactive waste such as filters, resin, plastic, and clothing. Determining of the radionuclide content of this waste is an important step for the determination of a suitable management strategy including classification and disposal. In this work, we radiochemically characterized the radionuclide activities of filters used during the decommissioning of Korea Research Reactors (KRRs) 1 and 2. The results indicate that the filter samples contained mainly 3 H (500–3,600 Bq·g −1 ), 14 C (7.5–29 Bq·g −1 ), 55 Fe (1.1– 7.1 Bq·g −1 ), 59 Ni (0.60–1.0 Bq·g −1 ), 60 Co (0.74–70 Bq·g −1 ), 63 Ni (0.60–94 Bq·g −1 ), 90 Sr (0.25–5.0 Bq·g −1 ), 137 Cs (0.64–8.7 Bq·g −1 ), and 152 Eu (0.19–2.9

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来源期刊

Journal of Nuclear Fuel Cycle and Waste Technology Energy-Fuel Technology

CiteScore

0.80

自引率

25.00%

发文量