Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW

doi:10.1109/TPS.2021.3110583

	Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW
	Li, Jie 1,2; Zhang, Jie 1; Liu, Changle 1; Liu, Xiaogang 1; Gao, Xiang 1
刊名	IEEE TRANSACTIONS ON PLASMA SCIENCE
	2021-10-01
卷号	49
关键词	Neutrons Plasmas Solid modeling Inductors Production Optimization Loading China Fusion Engineering Test Reactor (CFETR) neutronics study neutron wall loading (NWL) tritium breeding ratio (TBR) water-cooled ceramic breeder (WCCB)
ISSN号	0093-3813
DOI	10.1109/TPS.2021.3110583
通讯作者	Zhang, Jie(jzhang@ipp.ac.cn)
英文摘要	China Fusion Engineering Test Reactor (CFETR) is a new test tokamak device in China, which is to bridge the scientific and technical gaps between ITER and DEMO. One of the main missions of CFETR is to achieve tritium self-sufficiency with a tritium breeding ratio (TBR) of no less than 1.05. In addition, the neutron shielding evaluation is also a significant issue, which could provide a significant reference for the water-cooled ceramic breeder (WCCB) blanket modification and improvements. In this work, a 3-D simplified neutronics model containing the WCCB blanket is developed and the neutronics performance is calculated based on the 1.5 GW fusion power. The nuclear analyses are carried out by the Monte Carlo N-particle (MCNP) transport code, including the TBR, neutron wall loading (NWL), fast neutron flux on inboard side, and nuclear heating deposition on main in-vessel components. It is found that the net TBR reaches 1.23, which meets the condition of tritium self-sufficiency. Moreover, it is found that the peak NWL of inboard and outboard occurs in the equatorial plane. The inboard peak NWL is 1.89 MW/m(2) and the outboard peak NWL is 1.97 MW/m(2). In addition, the fast neutron flux and nuclear heating deposition at the inboard midplane in toroidal field coil (TFC) are obtained. According to the radiation limits of the CFETR TFC referring to ITER, the results show the nuclear responses of the TFC meet the limit criteria.
资助项目	National MCF Energy Research and Development Program[2019YFE03090200] ; National Natural Science Foundation of China[11975230]
WOS关键词	BREEDER BLANKET ; PHYSICS
WOS研究方向	Physics
语种	英语
出版者	IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC
WOS记录号	WOS:000707442700029
资助机构	National MCF Energy Research and Development Program ; National Natural Science Foundation of China
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/125577]
专题	中国科学院合肥物质科学研究院
通讯作者	Zhang, Jie
作者单位	1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230026, Peoples R China 2.Univ Sci & Technol China, Sci Isl Branch, Grad Sch, Hefei 230031, Peoples R China
推荐引用方式 GB/T 7714	Li, Jie,Zhang, Jie,Liu, Changle,et al. Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW[J]. IEEE TRANSACTIONS ON PLASMA SCIENCE,2021,49.
APA	Li, Jie,Zhang, Jie,Liu, Changle,Liu, Xiaogang,&Gao, Xiang.(2021).Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW.IEEE TRANSACTIONS ON PLASMA SCIENCE,49.
MLA	Li, Jie,et al."Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW".IEEE TRANSACTIONS ON PLASMA SCIENCE 49(2021).