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科研机构
西安交通大学 [8]
合肥物质科学研究院 [2]
近代物理研究所 [2]
上海应用物理研究所 [1]
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期刊论文 [12]
会议论文 [1]
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2022 [1]
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2020 [1]
2019 [1]
2018 [2]
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浏览/检索结果:
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Thermal-Mechanical Analysis of Beam Window and Beam Tube for ADS Granular Flow Target
期刊论文
NUCLEAR SCIENCE AND ENGINEERING, 2022, 页码: 11
作者:
Deng, Weiping
;
Zhang, Yanbin
;
Jia, Huan
;
Wan, Tao
;
Yang, Weifeng
收藏
  |  
浏览/下载:29/0
  |  
提交时间:2022/04/11
Spallation target
granular flow target
beam window
beam tube
thermal-mechanical analysis
An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing
期刊论文
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2021, 卷号: 2021, 页码: 16
作者:
Zhang, Qingyang
;
Peng, Tianji
;
Zhang, Guangchun
;
Liu, Jie
;
Guo, Xiaowei
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2021/12/08
Dynamic analysis for a 2 MW liquid-fueled molten salt reactor
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 126, 页码: -
作者:
Cui, Y
;
Cui, L
;
Xia, SP
;
Chen, JG
;
Cai, XZ
收藏
  |  
浏览/下载:34/0
  |  
提交时间:2021/09/06
DELAYED NEUTRON FRACTION
CYCLE
CODE
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
Blanket designs
CFETR
Coupled analysis
Hermo-mechanical
Neutronics
Thermal hydraulics
Development of neutronic-thermal hydraulic-mechanic-coupled platform for WCCB blanket design for CFETR
期刊论文
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 137, 期号: 无, 页码: 312-324
作者:
Jiang, Kecheng
;
Ding, Weiqiang
;
Zhang, Xiaokang
;
Li, Jia
;
Ma, Xuebin
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2020/03/31
Coupled platform
Neutronic-thermal hydraulic-mechanic
Fusion blanket
Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations
期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 114, 页码: 369-383
作者:
Zhou, Shengcheng
;
Yang, Won Sik
;
Park, Tongkyu
;
Wu, Hongchun
收藏
  |  
浏览/下载:1/0
  |  
提交时间:2019/11/26
Thermal feedback
Fuel cycle analysis code
Coupled neutronics and thermal-hydraulics
Depletion calculation
Molten salt reactor
Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor
会议论文
作者:
Ge, Jian
;
Zhang, Dalin
;
Tian, Wenxi
;
Qiu, Suizheng
;
Su, G. H.
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/11/26
Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY
期刊论文
ANNALS OF NUCLEAR ENERGY, 2017, 卷号: 109, 页码: 260-276
作者:
Hu, Tianliang
;
Cao, Liangzhi
;
Wu, Hongchun
;
Du, Xianan
;
He, Mingtao
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/11/26
OpenMC
Coupled neutronics and thermal-hydraulics analysis
Finite volume method
MSRs
OpenFOAM
Safety analyses of 10 MWth Forced Circulation LBE-cooled Fast Reactor during unprotected transients
期刊论文
ANNALS OF NUCLEAR ENERGY, 2016, 卷号: 88, 期号: 无, 页码: 112-117
作者:
Gu, Zhixing
;
Wang, Gang
;
Wang, Zhen
;
Song, Yong
;
Zhao, Zhumin
收藏
  |  
浏览/下载:13/0
  |  
提交时间:2018/01/25
Fclfr
Ntc
Transient Analysis
Coupled neutronics and thermal-hydraulics analysis of annular fuel assembly for SCWR
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2016, 卷号: 50, 页码: 1047-1053
作者:
Zhao, Chuan-Qi
;
Wang, Kun-Peng
;
Cao, Liang-Zhi
;
Wu, Hong-Chun
;
Zheng, You-Qi
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/11/26
Annular fuel
Diffusion calculation
Maximum cladding surface temperatures
Pin power distribution
Subchannel analysis
Supercritical water cooled reactors
Thermal hydraulics
Thermal Performance
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