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CORC

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Diffusion Characterization of Hydrogen Isotopes in Hastelloy N Alloy for the Application of Fluoride-Salt-Cooled High-Temperature Reactors (FHRs) 期刊论文
FUSION SCIENCE AND TECHNOLOGY, 2020, 卷号: 76, 期号: 4, 页码: 543-552
作者:  Zhang, DX;  Liu, W;  Liu, WG
收藏  |  浏览/下载：21/0  |  提交时间：2021/09/06
Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core 期刊论文
Applied Thermal Engineering, 2018, 卷号: 145, 页码: 48-57
作者:  Liu, Limin;  Zhang, Dalin;  Li, Linfeng;  Yang, Yicheng;  Wang, Chenglong
收藏  |  浏览/下载：4/0  |  提交时间：2019/11/19
Numerical Studies on Flow and Heat Transfer Characteristics of Fluoride Salt Cooled Pebble Bed Test Reactor 期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 001-005
作者:  Wei, Shiying;  Wang, Chenglong;  Tian, Wenxi;  Su, Guanghui;  Qiu, Suizheng
收藏  |  浏览/下载：14/0  |  提交时间：2019/11/26
Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 109, 期号: -, 页码: 171-179
作者:  Sun, KC;  Wilson, J;  Hauptman, S;  Ji, RM;  Dave, AJ
收藏  |  浏览/下载：16/0  |  提交时间：2019/12/17
The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2017, 卷号: 101, 期号: -, 页码: 199-208
作者:  Peng, Y;  Zhu, GF;  Zou, Y;  Liu, YF;  Yu, XH
收藏  |  浏览/下载：11/0  |  提交时间：2018/08/30
A specialized code for operation transient analysis and its application in fluoride salt-cooled high-temperature reactors 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2017, 卷号: 28, 期号: 8, 页码: -
作者:  Ruan, J;  Xu, B;  Li, MH;  Yang, Y;  Zou, Y
收藏  |  浏览/下载：18/0  |  提交时间：2018/08/30
Fhr  
Infiltration of graphite by molten 2LiF-BeF2 salt 期刊论文
JOURNAL OF MATERIALS SCIENCE, 2017, 卷号: 52, 期号: 19, 页码: 11346-11359
作者:  Tang, H;  Qi, W;  He, ZT;  Xia, HH;  Huang, Q
收藏  |  浏览/下载：16/0  |  提交时间：2018/08/30
Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2017, 卷号: 28, 期号: 11, 页码: -
作者:  Peng, Y;  Zhu, GF;  Zou, Y;  Liu, SJ;  Xu, HJ
收藏  |  浏览/下载：9/0  |  提交时间：2018/08/30
Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward 期刊论文
NUCLEAR TECHNOLOGY, 2017, 卷号: 197, 期号: 2, 页码: 119-139
作者:  Forsberg, CW;  Lam, S;  Carpenter, DM;  Whyte, DG;  Scarlat, R
收藏  |  浏览/下载：17/0  |  提交时间：2017/12/08

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