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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
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  |  
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
Physical study of an ultra-long-life small modular fast reactor loaded with U-Pu-Zr fuel (vol 142, 107390, 2020)
期刊论文
ANNALS OF NUCLEAR ENERGY, 2021, 卷号: 154, 页码: 2
作者:
Gao, Yucui
;
Cao, Liangzhi
;
Yang, Yongwei
;
Zhao, Zelong
;
Zhou, Shengcheng
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  |  
浏览/下载:15/0
  |  
提交时间:2021/12/10
Sensitivity analysis and similarity evaluation of sodium-cooled fast reactor in large size
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 125, 页码: 283-290
作者:
Zheng, Youqi
;
Qiao, Liang
;
Wan, Chenghui
;
Cao, Liangzhi
;
Liu, Yong
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  |  
浏览/下载:13/0
  |  
提交时间:2019/11/19
Code validation
Mixed oxide
Similarity analysis
Similarity evaluation
Validation of SARAX for the China Fast Reactor with the extrapolated experimental data
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 127, 页码: 188-195
作者:
Wan, Chenghui
;
Qiao, Liang
;
Zheng, Youqi
;
Cao, Liangzhi
;
Wu, Hongchun
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  |  
浏览/下载:34/0
  |  
提交时间:2019/11/19
Code validation
Nuclear data
Numerical results
Reference values
Relative uncertainty
Sensitivity/uncertainty analysis
Similarity analysis
Theoretical approach
Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas
期刊论文
Progress in Nuclear Energy, 2019, 卷号: 110, 页码: 301-310
作者:
Xu, Jialong
;
Zu, Tiejun
;
Cao, Liangzhi
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  |  
浏览/下载:123/0
  |  
提交时间:2019/11/19
Anisotropic scattering
Fuel temperature
NECP-Atlas
Neutron energy spectrum
Resonance elastic scattering
Scattering effects
Scattering kernels
Scattering matrices
Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 124, 页码: 187-197
作者:
Zhuang, Kun
;
Tang, Xiaobin
;
Cao, Liangzhi
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  |  
浏览/下载:5/0
  |  
提交时间:2019/11/19
Deterministic methods
Group parameters
MSFR
Neutronics
Neutronics parameters
OpenMC
Thermal neutron scattering
Two dimensions (2D)
The material-region-based 2D/1D transport method
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 128, 页码: 1-11
作者:
Liu, Zhouyu
;
Zhao, Chen
;
Cao, Lu
;
Wu, Hongchun
;
Cao, Liangzhi
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  |  
浏览/下载:5/0
  |  
提交时间:2019/11/19
Cluster assembly
Efficiency loss
High-fidelity
Leakage terms
Material region
NECP-X
Transport method
Whole-core transport
Multi-group effective cross section calculation method for Fully Ceramic Micro-encapsulated fuel
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 125, 页码: 26-37
作者:
Yin, Wen
;
Zu, Tiejun
;
He, Qingming
;
Cao, Liangzhi
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  |  
浏览/下载:144/0
  |  
提交时间:2019/11/19
Absorption cross sections
Disadvantage factor
Double heterogeneity
Effective cross sections
Homogeneous materials
Hyperfines
One-dimensional model
Self shielding effect
NECP-Atlas: A new nuclear data processing code
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 123, 页码: 153-161
作者:
Zu, Tiejun
;
Xu, Jialong
;
Tang, Yongqiang
;
Bi, Huchao
;
Zhao, Fei
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  |  
浏览/下载:9/0
  |  
提交时间:2019/11/19
Advanced reactor design
Cross section
Multi band
NECP-Atlas
Resonance elastic scattering
Transport calculation
Transport simulation
Xi'an Jiaotong University
Evaluation of activated corrosion products in primary coolant circuit of AP-1000 under grid frequency stability mode
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 125, 页码: 138-147
作者:
Mahmood, Fiaz
;
Hu, Huasi
;
Cao, Liangzhi
;
Lu, Guichi
;
Ni, Si
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  |  
浏览/下载:9/0
  |  
提交时间:2019/11/19
Corrosion products
CPA-AP1000
Power transient
Primary coolant circuits
Specific activity
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