燃烧等离子体实验托卡马克中杂质对关闭剂量率的影响

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Lin Kong , Xilong Tong , Xiaokang Zhang , Shanliang Zheng
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引用次数: 0

摘要

随着对核聚变能源需求的不断增长,了解实验托卡马克的辐射安全含义变得至关重要。结构材料杂质如钴(Co)通过长寿命放射性核素(如60Co)显著影响停机剂量率(SDDR),影响维修可行性和废物管理。目前使用接触剂量率(CDR)进行的评估往往忽略了复杂的几何效应,可能低估了辐射风险。本研究采用了一种综合的方法,将三维蒙特卡罗中子输运、FISPACT-II激活分析和NATF工具包集成在一起,来评估燃烧等离子体实验托卡马克中杂质的影响。结果表明,SDDR与Co含量呈强线性相关(p <;0.01),且具有统计学显著的线性相关性(p <;0.05)用于托卡马克以外的位置。几何效应导致SDDR和CDR之间的差异高达6.5倍。研究表明,将Co保持在0.05 wt. %以下,可以实现远程处理合规,同时强调了局部屏蔽对维护优化的必要性。本研究为中国设计的托卡马克提供了考虑几何因素的全装置SDDR映射,为聚变反应堆的材料规格和辐射防护策略提供了重要见解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
The implications of impurities on shutdown dose rates in the burning plasma experimental tokamak
With the growing demand for nuclear fusion energy, understanding radiation safety implications in experimental tokamaks becomes critical. Structural material impurities like cobalt (Co) significantly impact shutdown dose rates (SDDR) through long-lived radionuclides such as 60Co, affecting maintenance feasibility and waste management. Current assessments using contact dose rates (CDR) often overlook complex geometrical effects, potentially underestimating radiation risks. This study employs a comprehensive approach integrating 3D Monte Carlo neutron transport, FISPACT-II activation analysis, and the NATF toolkit to evaluate impurity impacts in a burning plasma experimental tokamak. The results reveal that SDDR exhibits strong linear correlations with Co content (p < 0.01) inside tokamak, and statistically significant linear correlations (p < 0.05) for locations outside the tokamak. Geometric effects cause up to 6.5-fold differences between SDDR and CDR. The work demonstrates that maintaining Co below 0.05 wt. % enables remote handling compliance while highlighting the necessity of localized shielding for maintenance optimization. This research provides the full-device SDDR mapping with geometric considerations for the Chinese-designed tokamak, offering crucial insights for material specification and radiation protection strategies in fusion reactors.
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来源期刊
Fusion Engineering and Design
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.
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