Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D-T neutron irradiation conditions
Zhu, Qingjun2; Chen, Wuhui2; Bao, Jie1; Du, Hua2; Liu, Songlin2; Huang, Kai2
刊名NUCLEAR FUSION
2021-06-01
卷号61
关键词D– T neutrons blanket mock-up neutronics experiments WCCB blanket CFETR
ISSN号0029-5515
DOI10.1088/1741-4326/abed84
通讯作者Liu, Songlin(slliu@ipp.ac.cn) ; Huang, Kai(huangkai@ipp.ac.cn)
英文摘要The 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.
资助项目China National Magnetic Confined Fusion Science Program[2015GB108002] ; National Natural Science Foundation of China[11705230] ; National Special Project for Magnetic Confined Nuclear Fusion Energy of China[2017YFE0301601] ; National Special Project for Magnetic Confined Nuclear Fusion Energy of China[2017YFE0301604]
WOS关键词PEBBLE BED ; DESIGN
WOS研究方向Physics
语种英语
出版者IOP PUBLISHING LTD
WOS记录号WOS:000648117600001
资助机构China National Magnetic Confined Fusion Science Program ; National Natural Science Foundation of China ; National Special Project for Magnetic Confined Nuclear Fusion Energy of China
内容类型期刊论文
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/122412]  
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.China Inst Atom Energy, Dept Nucl Phys, Beijing 102413, Peoples R China
2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R 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).
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