Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design

doi:10.1007/s10894-020-00247-4

HFCAS OpenIR

	Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design
	Yan, Qiang 1; Chen, Zhongwen 1; Wang, Zhijun 1; Kong, Defeng 3; Wang, Xiang 4; Gou, Fujun 1,2; Zhang, Kun 1,2
	2020-07-22
发表期刊	JOURNAL OF FUSION ENERGY
ISSN	0164-0313
通讯作者	Gou, Fujun(gfujun@scu.edu.cn) ; Zhang, Kun(kzhang@scu.edu.cn)
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.
关键词	Wall tritium recycling Tungsten Plasma material interaction Fusion energy
DOI	10.1007/s10894-020-00247-4
关键词[WOS]	PLASMA-FACING MATERIALS ; HYDROGEN ISOTOPE RETENTION ; DEUTERIUM RETENTION ; FUSION ; TEMPERATURE
收录类别	SCI
语种	英语
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]
项目资助者	National Natural Science Foundation of China ; Natural Science Foundation of Heilongjiang Province, China ; National Key Research and Development Program of China
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000551023000001
出版者	SPRINGER
引用统计
文献类型	期刊论文
条目标识符	http://ir.hfcas.ac.cn:8080/handle/334002/102948
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).