机构

• 近代物理研究所 [10]
• 合肥物质科学研究院 [1]

采集方式

• OAI收割 [11]

内容类型

• 期刊论文 [9]
• 会议论文 [2]

发表日期

• 2021 [3]
• 2018 [2]
• 2017 [1]
• 2015 [4]
• 2014 [1]

学科主题

筛选

浏览/检索结果: 共11条，第1-10条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择提交时间升序提交时间降序发表日期升序发表日期降序题名升序题名降序作者升序作者降序 Neutronics Analysis of the Stellarator-Type Fusion-Fission Hybrid Reactor Using Mesh Simplification 期刊论文  OAI收割 FUSION SCIENCE AND TECHNOLOGY, 2021, 页码: 10 作者:  Li, Jin-Yang;  Guo, Sheng-Miao;  Gu, Long;  Zhang, You-Peng;  Xu, Hu-Shan   |  收藏  |  浏览/下载：19/0  |  提交时间：2021/12/09 Stellarator-type FFHR  mesh oriented  computer-aided design  burnup  transmutation   Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 162, 页码: 8 作者:  Li, Jin-Yang;  Gu, Long;  Xu, Hu-Shan;  Zhang, You-Peng;  Dai, Yong   |  收藏  |  浏览/下载：26/0  |  提交时间：2021/12/08 Neutronics design  CAD  Stellarator  Fusion-Fission  TBR   Neutronics analysis of the stellarator-type fusion-fission hybrid reactor based on the CAD optimization method 期刊论文  OAI收割 ANNALS OF NUCLEAR ENERGY, 2021, 卷号: 150, 页码: 7 作者:  Li, Jin-Yang;  Gu, Long;  Xu, Hu-Shan;  Zhang, You-Peng;  Yao, Cun-Feng   |  收藏  |  浏览/下载：13/0  |  提交时间：2021/12/13 Stellarator-type FFHR  CAD  Low ploy  Neutronics analysis  Optimization   Neutronic study of a combined fast fission FFHR and thermal fission FFHR system using thorium bearing molten salt fuel 期刊论文  OAI收割 ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 112, 页码: 666-672 作者:  Xiao, S. C.;  Zhao, J.;  Zhou, Z.;  Yang, Y.   |  收藏  |  浏览/下载：17/0  |  提交时间：2018/05/31 Fast breeder  Thermal burner  U-233 breeding  Th-U cycle  Molten salt fuel   Neutronic Study of an Innovative Thorium-Uranium-Based Fusion-Fission Hybrid Energy Reactor with U-233 Breeding Enhancement by Using Dual-Coolant System 期刊论文  OAI收割 FUSION SCIENCE AND TECHNOLOGY, 2018, 卷号: 73, 页码: 559-567 作者:  Xiao, Sicong;  Zhao, Jing;  Zhou, Zhiwei;  Yang, Yongwei   |  收藏  |  浏览/下载：18/0  |  提交时间：2018/10/08 Fusion-fission hybrid reactor  uranium module  thorium module   Bi-level spatial subdivision based monte carlo ray tracing directly using CAD models 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2017, 卷号: 122, 期号: 无, 页码: 211-217 作者:  Yu, Shengpeng;  Wu, Bin;  Song, Jing;  Hao, Lijuan;  Zheng, Xiaolei   |  收藏  |  浏览/下载：11/0  |  提交时间：2019/02/28 Monte Carlo  Ray tracing  CAD  SuperMC   BURN UP STUDY OF AN INNOVATIVE NATURAL URANIUM-THORIUM FUELED REPROCESSING FREE FUSION-FISSION HYBRID REACTOR BLANKET WITH CLOSED THORIUM-URANIUM FUEL CYCLE 期刊论文  OAI收割 FUSION SCIENCE AND TECHNOLOGY, 2015, 卷号: 68, 页码: 566-572 作者:  Xiao, S. C.;  Zhao, Jing;  Heng, X.;  Sheng, X. Y.;  Zhou, Z.   |  收藏  |  浏览/下载：11/0  |  提交时间：2018/05/31 BURN UP STUDY OF AN INNOVATIVE NATURAL URANIUM-THORIUM FUELED REPROCESSING FREE FUSION-FISSION HYBRID REACTOR BLANKET WITH CLOSED THORIUM-URANIUM FUEL CYCLE 会议论文  OAI收割 作者:  Xiao, S. C.;  Zhao, Jing;  Heng, X.;  Sheng, X. Y.;  Zhou, Z.   |  收藏  |  浏览/下载：13/0  |  提交时间：2018/08/20 BURN UP STUDY OF AN INNOVATIVE NATURAL URANIUM-THORIUM FUELED REPROCESSING FREE FUSION-FISSION HYBRID REACTOR BLANKET WITH CLOSED THORIUM-URANIUM FUEL CYCLE 会议论文  OAI收割 作者:  Xiao, S. C.;  Zhao, Jing;  Heng, X.;  Sheng, X. Y.;  Zhou, Z.   |  收藏  |  浏览/下载：14/0  |  提交时间：2018/08/20 Neutronic Study of a Molten Salt Cooled Natural Thorium-Uranium Fueled Fusion-Fission Hybrid Energy System 期刊论文  OAI收割 JOURNAL OF FUSION ENERGY, 2015, 卷号: 34, 页码: 352-360 作者:  Xiao, S. C.;  Zhao, J.;  Zhou, Z.;  Yang, Y.   |  收藏  |  浏览/下载：11/0  |  提交时间：2018/07/05 Ffhr  U-233 Breeding  Energy Generation  Fast Fission