Zhou Fei, Chen Xiaotong, Liu Haisheng, Feng Xinchun, Ma Tao, Zhang Zhenzhong
Environmental Technology Division, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China.
Division of Radiation Protection, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China.
J Hazard Mater. 2024 Sep 5;476:135120. doi: 10.1016/j.jhazmat.2024.135120. Epub 2024 Jul 5.
The decommissioning of nuclear reactors is a global concern, in part because of the generation of radioactive aerosols that can lead to internal radiation exposure. At present, radioactive aerosols generated during nuclear decommissioning have not been actively studied, and data collected from the actual decommissioning are limited. This paper presents a study of radioactive aerosols generated during the pre-decommission phase of an experimental shielding reactor. Among all the on-site operations, cutting resulted in the highest levels of radioactivity. Plasma arc cutting, in particular, had a maximum gross α and β radioactivity over 0.10 and 0.14 Bq/m, respectively. Assumed AMAD (activity median aerodynamic diameter) values are employed to assess the impact of particle size on the internal exposure dose resulting from the inhalation of Cs aerosols. This assessment is based on the Human Respiratory Tract Model of International Commission on Radiological Protection. When cutting stainless steel by plasma arc, the internal exposure dose caused by Cs aerosols with an AMAD of 0.1 µm is estimated to be nearly four times as that of aerosols with an AMAD of 10 µm. Results show that the internal exposure dose is highly dependent on the AMAD, implying the importance of measuring size-related parameters of radioactive aerosols in the future nuclear decommissioning. This study has revealed some characteristics of radioactive aerosols released in decommissioning operations, which can serve as a valuable reference for controlling and removing aerosols during the decommissioning of nuclear facilities.
核反应堆退役是一个全球关注的问题,部分原因是会产生可能导致内照射的放射性气溶胶。目前,核退役过程中产生的放射性气溶胶尚未得到积极研究,从实际退役中收集的数据也很有限。本文介绍了对一座实验性屏蔽反应堆退役前阶段产生的放射性气溶胶的研究。在所有现场操作中,切割产生的放射性水平最高。特别是等离子弧切割,其总α和β放射性最大值分别超过0.10和0.14贝克勒尔/米。采用假设的活度中值空气动力学直径(AMAD)值来评估粒径对吸入铯气溶胶所致内照射剂量的影响。该评估基于国际放射防护委员会的人类呼吸道模型。当用等离子弧切割不锈钢时,AMAD为0.1微米的铯气溶胶所致内照射剂量估计几乎是AMAD为10微米的气溶胶的四倍。结果表明,内照射剂量高度依赖于AMAD,这意味着在未来核退役中测量放射性气溶胶与尺寸相关参数的重要性。本研究揭示了退役操作中释放的放射性气溶胶的一些特性,可为核设施退役期间气溶胶的控制和去除提供有价值的参考。