KSTAR设备分流器升级后的放射性废物分析和处理

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-08-12 DOI:10.1016/j.fusengdes.2025.115342

Hee-Soo. Kim , Young Seok Lee , Kaprai Park , Kwang-Woon Cho , Sung Ill Lee

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引用次数: 0

摘要

核聚变实验用托卡马克装置由多种结构组成。由于核聚变反应过程中产生的中子，真空容器内部的结构变得具有放射性。真空容器的主要成分是SS316L，当这种材料通过中子引起核反应时，产生的主要放射性物质是Mn-54、Co-58和Co-60。其中，Co-60的半衰期最长，为5.3年，对辐射剂量影响较大。在中子引起的核反应中，由每种结构产生的放射性物质根据其物理半衰期衰变并释放辐射。因此，在处置时，它们必须作为放射性废物处理，处置计划必须反映辐射剂量和数量。此外，石墨瓦含有核聚变反应过程中产生的氚，所以这一点也必须考虑在内。由于这对空间和成本有重大影响，因此本文根据KSTAR装置低分流器的更换情况，对废物分析和管理结果进行了分析，并计划将其用于未来的装置处置计划。

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Radioactive waste analysis and disposal following KSTAR device diverter upgrade

The tokamak device for nuclear fusion experiments consists of various structures. The structure inside the vacuum vessel becomes radioactive due to neutrons generated during the nuclear fusion reaction. The main component of the vacuum vessel is SS316L, and when this material causes a nuclear reaction by neutrons, the main radioactive substances generated are Mn-54, Co-58, and Co-60. Among them, Co-60, with a half-life of 5.3 years, has the longest half-life and greatly affects the radiation dose. In a nuclear reaction caused by neutrons, the radioactive material generated by each structure decays according to its physical half-life and releases radiation. Therefore, when disposed of, they must be treated as radioactive waste, and the disposal plan must reflect the radiation dose and quantity. In addition, graphite tiles contain tritium generated during the nuclear fusion reaction, so this must also be considered. Since this has a significant impact on space and cost, this paper analyzes the results of waste analysis and management according to the replacement of the low diverter of the KSTAR device and plans to utilize it for future device disposal plans.

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.