Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR

doi:10.1016/j.fusengdes.2020.111501

	Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR
	Huang, Kai 1; Zhao, Xueli 1,2; Ma, Xuebin 3; Liu, Songlin 1
刊名	FUSION ENGINEERING AND DESIGN
	2020-04-01
卷号	153
关键词	Tritium transport System level WCCB blanket CFETR
ISSN号	0920-3796
DOI	10.1016/j.fusengdes.2020.111501
通讯作者	Huang, Kai(huangkai@ipp.ac.cn)
英文摘要	Tritium is the fuel for the future D-T magnetic-confined fusion devices such as the China Fusion Engineering Test Reactor (CFETR). Accurate assessment of the tritium transport behaviors within the reactor is essential to the fulfillment of fuel self-sustainability and public safety concerns. Due to the radioactive nature of this hydrogen isotope, numerical simulations are often used as a more convenient and realizable approach to provide data and insights regarding the evaluation of overall tritium distribution, permeation, and inventory. In this work, we developed an in-house tritium transport analysis code for the water-cooled ceramic breeder (WCCB) blanket for CFETR at the system level. The math-physics models applied incorporate the multi-physical processes required in the full functional description of macroscopic tritium transport. The code extends the capability of the existing, pioneering OD codes in this area to take care of the varying configurations of different blanket modules within a fusion reactor. The code developed is applied as a first attempt to evaluate the overall tritium transport behaviors in the WCCB blanket system for CFETR. Preliminary simulation results are reported and discussed. It suggests that the in-homogeneity effect introduced by the geometric and material configurations varying across blanket modules can bring a marked impact on the tritium transport performance, thus is desirable to be taken into account in system-level codes to improve the prediction results.
资助项目	National Key R&D Program of China[2017YFE0300502] ; National Natural Science Foundation of China[11775256]
WOS关键词	BREEDER BLANKET ; MODEL ; PERMEATION ; HCLL
WOS研究方向	Nuclear Science & Technology
语种	英语
出版者	ELSEVIER SCIENCE SA
WOS记录号	WOS:000518408500010
资助机构	National Key R&D Program of China ; National Natural Science Foundation of China
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/103791]
专题	中国科学院合肥物质科学研究院
通讯作者	Huang, Kai
作者单位	1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China 2.Univ Sci & Technol China, Hefei 230037, Anhui, Peoples R China 3.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China
推荐引用方式 GB/T 7714	Huang, Kai,Zhao, Xueli,Ma, Xuebin,et al. Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR[J]. FUSION ENGINEERING AND DESIGN,2020,153.
APA	Huang, Kai,Zhao, Xueli,Ma, Xuebin,&Liu, Songlin.(2020).Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR.FUSION ENGINEERING AND DESIGN,153.
MLA	Huang, Kai,et al."Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR".FUSION ENGINEERING AND DESIGN 153(2020).