QQ客服 官方微博 反馈留言

浏览/检索结果: 共18条，第1-10条 帮助 限定条件 发表日期：2018     已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Development of neutronic-thermal hydraulic-mechanic-coupled platform for WCCB blanket design for CFETR 期刊论文 FUSION ENGINEERING AND DESIGN, 2018, 卷号: 137, 期号: 无, 页码: 312-324 作者:  Jiang, Kecheng;  Ding, Weiqiang;  Zhang, Xiaokang;  Li, Jia;  Ma, Xuebin 收藏  |  浏览/下载：4/0  |  提交时间：2020/03/31 Coupled platform  Neutronic-thermal hydraulic-mechanic  Fusion blanket   FreeCAD based modeling study on MCNPX for accelerator driven system 期刊论文 PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 107, 页码: 100-109 作者:  Li, Jin-Yang;  Gu, Long;  Xu, Hu-Shan;  Korepanova, Nadezda;  Sheng, Xin 收藏  |  浏览/下载：27/0  |  提交时间：2018/07/16 FreeCAD  MCNPX  ADS  Hierarchical tree  Ray-casting technology  Markov chain   Analysis of Dogleg Duct Experiments With 14-MeV Neutron Source Using TRIPOLI-4 Monte Carlo Transport Code 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1180-1185 作者:  Lei, Mingzhun;  Peneliau, Yannick;  Lee, Yi-Kang;  Song, Yuntao 收藏  |  浏览/下载：9/0  |  提交时间：2019/06/04 Benchmark  Monte Carlo  neutron transport  TRIPOLI-4  variance reduction   Current Status and Progress on the Shielding Blanket of CFETR 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1417-1421 作者:  Liu, Changle;  Yang, Hao;  Zhang, Jie;  Zhang, Jianzhong;  Li, Lei 收藏  |  浏览/下载：9/0  |  提交时间：2019/08/23 Chinese fusion engineering test reactor (CFETR)  demonstration reactors (DEMO)  neutronics  shielding blanket (SB)   Neutronics Analysis of Helium Cooled Ceramic Breeder Blanket with S-shaped Lithium Zone and Cooling Plate for CFETR 期刊论文 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：9/0  |  提交时间：2019/08/23 China fusion engineering test reactor (CFETR)  helium cooled ceramic breeder (HCCB)  shielding performance  tritium breeding ratio (TBR)   Steady Analysis of Graphite-moderator Molten Salt Reactor Based on MOREL2.0 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2018, 卷号: 52, 页码: 1774-1779 作者:  Zhuang, Kun;  Cao, Liangzhi;  Tang, Xiaobin 收藏  |  浏览/下载：13/0  |  提交时间：2019/11/19 Delayed Neutron Precursor  Inlet fuel temperatures  Molten fluoride salts  Neutronics  Reactivity loss  Steady-state analysis  Thermal hydraulics  Thorium molten salts   Constrastive Analysis of Core Characteristics for Sodium Cooled Traveling Wave Reactor and Standing Wave Reactor 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2018, 卷号: 52, 页码: 397-404 作者:  Zheng, Meiyin;  Chen, Ping;  Li, Quan;  Zhang, Dalin;  Tian, Wenxi 收藏  |  浏览/下载：10/0  |  提交时间：2019/11/19 Contrastive analysis  Neutronics  Standing wave  Thermal hydraulics  Traveling wave   Numerical analysis analysis on the dynamic behaviors of a graphite-moderated molten salt reactor based on MOREL2.0 code 期刊论文 ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 117, 页码: 3-11 作者:  Zhuang, Kun;  Cao, Liangzhi 收藏  |  浏览/下载：7/0  |  提交时间：2019/11/19 Neutronics  Dynamics  Thermal-hydraulics  TMSR-LF  Molten salt reactor   Neutronics and thermal hydraulics analysis of a conceptual ultra-high temperature MHD cermet fuel core for nuclear electric propulsion 期刊论文 Frontiers in Energy Research, 2018, 卷号: 6 作者:   收藏  |  浏览/下载：13/0  |  提交时间：2019/11/19 Cermet fuels  MHD generator  Neutronics  Reactor designs  Space reactors  Thermal hydraulics