Lin Kong , Xilong Tong , Xiaokang Zhang , Shanliang Zheng
{"title":"燃烧等离子体实验托卡马克中杂质对关闭剂量率的影响","authors":"Lin Kong , Xilong Tong , Xiaokang Zhang , Shanliang Zheng","doi":"10.1016/j.fusengdes.2025.115285","DOIUrl":null,"url":null,"abstract":"<div><div>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 <sup>60</sup>Co, 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.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115285"},"PeriodicalIF":2.0000,"publicationDate":"2025-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"The implications of impurities on shutdown dose rates in the burning plasma experimental tokamak\",\"authors\":\"Lin Kong , Xilong Tong , Xiaokang Zhang , Shanliang Zheng\",\"doi\":\"10.1016/j.fusengdes.2025.115285\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>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 <sup>60</sup>Co, 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.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"219 \",\"pages\":\"Article 115285\"},\"PeriodicalIF\":2.0000,\"publicationDate\":\"2025-06-21\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625004818\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625004818","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
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.
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.