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西安交通大学 [18]
近代物理研究所 [14]
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合肥物质科学研究院 [8]
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期刊论文 [50]
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Neutronics design optimization of a small modular fast reactor based on response surface methodology
期刊论文
Nuclear Engineering and Design, 2022, 卷号: 395
作者:
Gao, Yucui
;
Cao, Liangzhi
;
Ye, Wenlian
;
Yan, Xuesong
;
Chen, Liangwen
收藏
  |  
浏览/下载:26/0
  |  
提交时间:2022/08/09
Fast reactors
Structural design
Surface properties
Burnup reactivity swing
Core design
Design optimization
Modulars
Multi-objectives optimization
Neutronic design
Response-surface methodology
Small burnup reactivity swing
Small modular fast reactor
UN fuel
Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: Experimental validation of neutronic calculations
期刊论文
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2021, 卷号: 502, 页码: 1-9
作者:
Cui, Lijuan
;
Li, Jinyang
;
Gerstl, Stephan
;
Pouchon, Manuel
;
Dai, Yong
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2021/12/08
Quantitative APT analysis of transmutants
Validation of neutronic calculations
STIP irradiation experiments
FM steels
Neutronic analyses of Upper port ECRH antenna system for CFETR
期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 162
作者:
Wu, Qiuran
;
Lu, Peng
;
Zheng, Yu
;
Du, Hua
;
Xu, Kun
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  |  
浏览/下载:25/0
  |  
提交时间:2021/08/30
CFETR
ECRH
Neutronics
Shielding
TBR
Modeling of the source neutrons of D-T neutron generator based on in-situ depth profiling of tritium in the tritide target
期刊论文
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2020, 卷号: 982
作者:
Zhu, Qingjun
;
Bao, Jie
;
Chen, Wuhui
;
Huang, Kai
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2020/12/07
D-T neutron generator
Neutronic experiment
Tritium
Alpha spectra
Source neutrons
FreeCAD based Monte Carlo modeling approach for fusion reactor facilities
期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 155, 页码: 10
作者:
Li, Jin-Yang
;
Gu, Long
;
Xu, Hu-Shan
;
Dai, Yong
;
Zhang, You-Peng
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2022/01/18
FreeCAD
Monte Carlo method
MCNPX
fast ray-casting method
B-rep
CSG
Th-U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors
期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 8, 页码: -
作者:
He, LY
;
Xia, SP
;
Zhou, XM
;
Chen, JG
;
Liu, GM
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  |  
浏览/下载:15/0
  |  
提交时间:2021/09/06
THORIUM FUEL-CYCLE
ENRICHMENT
TRANSITION
Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode
期刊论文
ANNALS OF NUCLEAR ENERGY, 2020, 卷号: 138, 页码: -
作者:
Zou, CY
;
Yu, CG
;
Wu, JH
;
Cai, XZ
;
Chen, JG
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  |  
浏览/下载:33/0
  |  
提交时间:2021/09/06
PLUTONIUM TRIFLUORIDE
DESIGN
Core neutronic characterization of a large molten-salt cooled thorium-based solid fuel fast reactor
期刊论文
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020, 卷号: 44, 期号: 10, 页码: 8062-8073
作者:
Peng, Y
;
Zhu, GF
;
Zou, Y
;
Liu, SJ
;
Xu, HJ
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2021/09/06
DESIGN
SUSTAINABILITY
URANIUM
Deterministic simulation of the static neutronic characteristics for the lead core of VENUS-II facility
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 353, 页码: 10
作者:
Zhang, Lu
;
Yang, Yongwei
;
Ma, Fei
;
Zhou, Qi
;
Gu, Long
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2022/01/19
VENUS-II facility
Fast-thermal coupled lead core
Deterministic modeling
Static neutronic analyses
Development and preliminary verification of code IMPC-transient
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 350, 页码: 137-146
作者:
Chen, Kang
;
Gao, Qingyu
;
Yang, Yongwei
;
Gao, Yucui
收藏
  |  
浏览/下载:52/0
  |  
提交时间:2019/11/10
ADANES
IMPC-transient
System safety analysis code
EBR-II SHRT
DAISY
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