中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design

文献类型:期刊论文

作者Yan, Qiang1; Chen, Zhongwen1; Wang, Zhijun1; Kong, Defeng3; Wang, Xiang4; Gou, Fujun1,2; Zhang, Kun1,2
刊名JOURNAL OF FUSION ENERGY
出版日期2020-07-22
关键词Wall tritium recycling Tungsten Plasma material interaction Fusion energy
ISSN号0164-0313
DOI10.1007/s10894-020-00247-4
通讯作者Gou, Fujun(gfujun@scu.edu.cn) ; Zhang, Kun(kzhang@scu.edu.cn)
英文摘要The recycling of tritium from plasma facing wall is an important neutral fuel source (in atomic and molecular form) for plasma confinement and particle control. In this study, the recycling process at tungsten wall based on current CFETR design was modeled. Monte Carlo code SRIM was used to model the implantation of energetic tritium ions into pure tungsten and to get back-scattering fraction of ions and the distribution of implanted tritium ions. The diffusion process of atoms in materials, with recombination at surface as boundary condition, was simulated using numerical approach for both stead and transient state. The total recycling ratio was contributed by fast process (implantation and back scattering) and slow process (diffusion and recombination) and its value nearly equals to 1 for stead state. Temporal dependence of total recycling ratio mainly depended on the slow process and was limited by diffusion coefficient in the bulk near surface and existence of traps in material. For tungsten material with good surface condition, the time of 90% recycling was characterized as 1 ms and affected by temperature, recombination coefficient and concentration of traps while the thickness of material had less affection. Isotope effect that recycling ratio of tritium was larger than that of deuterium at the same situation was also found in the simulation and this effect may affect particle balance and fueling in D-T plasma operation. A collection of theoretical models to estimate the recycling ratio and its time dependence were also summarized and validated by the simulation results.
WOS关键词PLASMA-FACING MATERIALS ; HYDROGEN ISOTOPE RETENTION ; DEUTERIUM RETENTION ; FUSION ; TEMPERATURE
资助项目National Natural Science Foundation of China[11805043] ; Natural Science Foundation of Heilongjiang Province, China[QC2017049] ; National Key Research and Development Program of China[2017YFE0300500] ; National Key Research and Development Program of China[2017YFE0300501]
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000551023000001
出版者SPRINGER
资助机构National Natural Science Foundation of China ; Natural Science Foundation of Heilongjiang Province, China ; National Key Research and Development Program of China
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/102947]  
专题中国科学院合肥物质科学研究院
通讯作者Gou, Fujun; Zhang, Kun
作者单位1.Chengdu Univ, Inst Adv Study, 2025 Chengluo Ave, Chengdu 610106, Peoples R China
2.Sichuan Univ, Inst Nucl Sci & Technol, Chengdu 610064, Peoples R China
3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
4.Harbin Engn Univ, Coll Nucl Sci & Technol, Harbin 150001, Peoples R China
推荐引用方式
GB/T 7714
Yan, Qiang,Chen, Zhongwen,Wang, Zhijun,et al. Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design[J]. JOURNAL OF FUSION ENERGY,2020.
APA Yan, Qiang.,Chen, Zhongwen.,Wang, Zhijun.,Kong, Defeng.,Wang, Xiang.,...&Zhang, Kun.(2020).Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design.JOURNAL OF FUSION ENERGY.
MLA Yan, Qiang,et al."Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design".JOURNAL OF FUSION ENERGY (2020).

入库方式: OAI收割

来源:合肥物质科学研究院

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