中国科学院机构知识库网格系统: 检索

中国科学院机构知识库网格

Chinese Academy of Sciences Institutional Repositories Grid

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	Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW 期刊论文 OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021, 卷号: 49 作者: Li, Jie; Zhang, Jie; Liu, Changle; Liu, Xiaogang; Gao, Xiang \| 收藏 \| 浏览/下载：76/0 \| 提交时间：2021/11/15 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)
	Investigation on the Effect of Tritium Breeding Ratio Using Temperature Control Mechanism for DEMO Blanket 期刊论文 OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 6, 页码: 2277-2280 作者: Qiu, Yang; Zhang, Jie; Liu, Changle; Yao, Damao; Gao, Xiang \| 收藏 \| 浏览/下载：23/0 \| 提交时间：2019/11/12 Breeding blanket demonstrate power plant (DEMO) temperature control mechanism (TCM) tritium breeding ratio (TBR)
	Neutronics Analysis of Helium Cooled Ceramic Breeder Blanket with S-shaped Lithium Zone and Cooling Plate for CFETR 期刊论文 OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1471-1476 作者: Lu, Yudong; Xu, Kun; Ye, Minyou; Lei, Mingzhun; Mao, Shifeng \| 收藏 \| 浏览/下载：18/0 \| 提交时间：2019/08/23 China fusion engineering test reactor (CFETR) helium cooled ceramic breeder (HCCB) shielding performance tritium breeding ratio (TBR)