CORC

在结果中检索

CORC

浏览/检索结果: 共187条，第1-10条 帮助

限定条件                
已选(0)清除 条数/页：   排序方式：
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
Foreword: Selected papers from the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) 期刊论文
Nuclear Science and Engineering, 2019, 卷号: 193, 页码: 3-4
作者:  Yang, Bao-Wen;  Ninokata, Hisashi;  Hassan, Yassin;  Sun, Xiaodong
收藏  |  浏览/下载：20/0  |  提交时间：2019/11/19
Conceptual design and coupled neutronic/thermal-hydraulic/mechanical research of the supercritical water cooled ceramic blanket for CFETR 期刊论文
Fusion Engineering and Design, 2019, 卷号: 138, 页码: 272-281
作者:  Cheng, Jie;  Wu, Yingwei;  Cui, Shijie;  Su, G.H.;  Chen, Yi-tung
收藏  |  浏览/下载：20/0  |  提交时间：2019/11/19
Selected papers from the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) Foreword 期刊论文
NUCLEAR TECHNOLOGY, 2019, 卷号: 205, 页码: V-VI
作者:  Yang, Bao-Wen;  Ninokata, Hisashi;  Hassan, Yassin;  Cheung, Fan-Bill
收藏  |  浏览/下载：12/0  |  提交时间：2019/11/19
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
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
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
Development of neutronics and thermal-hydraulics coupled code for accelerator driven subcritical systems 会议论文
作者:  Luo, Run;  Wang, Pengfei;  Wei, Xinyu;  Revankar, Shripad T.;  Zhao, Fuyu
收藏  |  浏览/下载：9/0  |  提交时间：2019/11/19
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:  Song, Jian;  An, Weijian;  Wu, Yingwei;  Tian, Wenxi
收藏  |  浏览/下载：13/0  |  提交时间：2019/11/19
Experimental studies on the thermal-hydraulics of dowtherm a through the pebble bed with internal heat generation 会议论文
作者:  Liu, Limin;  Zhang, Dalin;  Li, Linfeng;  Yang, Yichen;  Wang, Chenglong
收藏  |  浏览/下载：8/0  |  提交时间：2019/11/19

©版权所有 ©2017 CSpace - Powered by CSpace