Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions

doi:10.1088/1741-4326/abed84

	Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions
	Zhu,Qingjun 2; Chen,Wuhui 2; Bao,Jie 1; Du,Hua 2; Liu,Songlin 2; Huang,Kai 2
刊名	Nuclear Fusion
	2021-05-04
卷号	61
关键词	D–T neutrons blanket mock-up neutronics experiments WCCB blanket CFETR
ISSN号	0029-5515
DOI	10.1088/1741-4326/abed84
通讯作者	Liu,Songlin() ; Huang,Kai()
英文摘要	AbstractThe accurate assessment of tritium breeding parameters within fusion blankets is crucial for future magnet-confined fusion machines to realize fuel self-sufficiency. Such an assessment can be conducted using the simulation approach with nuclear data of high-fidelity and, most importantly, validated against experimental data. In this paper, we report neutronics experiment studies carried out on a mock-up of the water-cooled ceramic breeder blanket of the China fusion engineering test reactor (CFETR), irradiated at a deuterium–tritium (D–T) neutron source. The mock-up’s nuclear responses to 14?MeV neutrons, including tritium production rates (TPR) and neutron-induced reaction rates, are simulated and validated by experimental results. Redundant measurement techniques are used, including Li2TiO3 pellets for offline TPR measurements and the developed lithium glass detector with a significantly reduced size for online TPR measurements. The validation of the TPR value is complemented by the experimental evaluation of the neutron-induced reaction rates for Au and Zr foils. All experimental results are analyzed using the MCNP-4C code and FENDL-3.0 nuclear data library. The source term for the Monte Carlo simulation is built using a newly-developed method based upon the modeling of the depth profiling of tritium in the tritiated target. The experiments are in good agreement with the simulations; ratios of the calculation to experimental results (C/E) on TPR are found to be 0.97–1.08. The influence of the first wall tungsten armor on the mock-up nuclear responses is also studied.
语种	英语
出版者	IOP Publishing
WOS记录号	IOP:0029-5515-61-6-ABED84
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/122514]
专题	中国科学院合肥物质科学研究院
通讯作者	Liu,Songlin; Huang,Kai
作者单位	1.Department of Nuclear Physics, China Institute of Atomic Energy, Beijing 102413, China 2.Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui 230031, China
推荐引用方式 GB/T 7714	Zhu,Qingjun,Chen,Wuhui,Bao,Jie,et al. Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions[J]. Nuclear Fusion,2021,61.
APA	Zhu,Qingjun,Chen,Wuhui,Bao,Jie,Du,Hua,Liu,Songlin,&Huang,Kai.(2021).Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions.Nuclear Fusion,61.
MLA	Zhu,Qingjun,et al."Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions".Nuclear Fusion 61(2021).