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CORC

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Numerical evaluation of hypothetical core disruptive accident in full- scale model of sodium-cooled fast reactor 期刊论文
NUCLEAR ENGINEERING AND TECHNOLOGY, 6, 2022, 卷号: 54, 页码: 2120
作者:  Guo ZH(郭志鸿);  Chen XD(陈晓东);  Hu GQ(胡国庆)
收藏  |  浏览/下载：14/0  |  提交时间：2022/10/23
Effect of Clearance of Rotor-Stator Cascade on Pressure Fluctuation in Secondary Circuit Coolant Pump for Sodium-Cooled Fast Reactor 期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2020, 卷号: 41, 期号: 1, 页码: 127-133
作者:  Yang, Congxin;  Liu, Man;  Wang, Xiuyong;  Yu, Hongchang;  Niu, Hongjun
收藏  |  浏览/下载：11/0  |  提交时间：2020/11/14
Experimental study of liquid sodium flow and heat transfer characteristics along a hexagonal 7-rod bundle 期刊论文
Applied Thermal Engineering, 2019, 卷号: 149, 页码: 578-587
作者:  Hou, Yandong;  Wang, Liu;  Wang, Mingjun;  Zhang, Kui;  Zhang, Xisi
收藏  |  浏览/下载：35/0  |  提交时间：2019/11/19
Experimental study and optimized design on electromagnetic pump for liquid sodium 期刊论文
Annals of Nuclear Energy, 2019, 卷号: 124, 页码: 426-440
作者:  Wang, Liu;  Hou, Yandong;  Shi, Leitai;  Wu, Yingwei;  Tian, Wenxi
收藏  |  浏览/下载：12/0  |  提交时间：2019/11/19
Numerical study on thermal deformation behaviors of the single subassembly in sodium-cooled fast reactors based on Euler-Bernoulli beam theory 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 345, 页码: 28-39
作者:  Ma, Zhenhui;  Ma, Zehua;  Wu, Yingwei;  Wang, Mingjun;  Su, G. H.
收藏  |  浏览/下载：146/0  |  提交时间：2019/11/19
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors 期刊论文
Progress in Nuclear Energy, 2019, 卷号: 110, 页码: 213-223
作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing
收藏  |  浏览/下载：31/0  |  提交时间：2019/11/19
Thermal-hydraulic analysis code development for sodium heated once-through steam generator 期刊论文
Annals of Nuclear Energy, 2019, 卷号: 127, 页码: 385-394
作者:  Xu, Rongshuan;  Zhang, Dalin;  Tian, Wenxi;  Qiu, Suizheng;  Su, G.H.
收藏  |  浏览/下载：11/0  |  提交时间：2019/11/19
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors 期刊论文
Progress in Nuclear Energy, 2019, 卷号: Vol.110, 页码: 213-223
作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing
收藏  |  浏览/下载：7/0  |  提交时间：2019/12/13
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: Vol.110, 页码: 213-223
作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing
收藏  |  浏览/下载：7/0  |  提交时间：2019/12/13
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors. 期刊论文
Progress in Nuclear Energy, 2019, 卷号: Vol.110, 页码: 213-223
作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing
收藏  |  浏览/下载：5/0  |  提交时间：2019/12/13

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