CORC

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CORC

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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
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
A best-estimated correlation for prediction of nucleation radius in sodium boiling 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 345, 页码: 40-46
作者:  Ma, Zaiyong;  Qiu, Suizheng;  Zhang, Luteng;  Bu, Shanshan;  Sun, Wan
收藏  |  浏览/下载：2/0  |  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 Investigation of Dryout Heat Flux and Heat Transfer Characteristics in Core Debris Bed of SFR After Severe Accident 期刊论文
Nuclear Science and Engineering, 2018
作者:  Zhang, Bin;  Zhang, Mengwei;  Peng, Cheng;  Shan, Jianqiang;  Yang, Baowen
收藏  |  浏览/下载：10/0  |  提交时间：2019/11/19
The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 108, 页码: 54-65
作者:  Yue, Nina;  Zhang, Dalin;  Chen, Jing;  Song, Ping;  Wang, Xin'an
收藏  |  浏览/下载：7/0  |  提交时间：2019/11/26
Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system 期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 121, 页码: 324-334
作者:  Du, Xianan;  Zheng, Youqi;  Cao, Liangzhi;  Wu, Hongchun
收藏  |  浏览/下载：2/0  |  提交时间：2019/11/26
Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 104, 页码: 327-341
作者:  Sun, R. L.;  Zhang, D. L.;  Liang, Y.;  Wang, M. J.;  Tian, W. X.
收藏  |  浏览/下载：3/0  |  提交时间：2019/11/26
Thermal-hydraulic design and analysis code development for steam generator of CFR600 期刊论文
ANNALS OF NUCLEAR ENERGY, 2016, 卷号: 90, 期号: [db:dc_citation_issue], 页码: 256-263
作者:  Sun, Peiwei;  Wang, Zi;  Zhang, Jianmin;  Su, Guanghui
收藏  |  浏览/下载：2/0  |  提交时间：2019/12/02
Thermal-hydraulic analysis of EBR-II Shutdown Heat Removal Tests SHRT-17 and SHRT-45R 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2015, 卷号: 85, 期号: [db:dc_citation_issue], 页码: 682-693
作者:  Yue, Nina;  Ma, Zaiyong;  Cal, Rong;  Hu, Benxue;  Su, G. H.
收藏  |  浏览/下载：3/0  |  提交时间：2019/12/02

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