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西安交通大学 [12]

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期刊论文 [7]

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	Unstructured coarse mesh finite difference method to accelerate k-eigenvalue and fixed source neutron transport calculations 期刊论文 ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 120, 页码: 367-377 作者: Zhou, Shengcheng; Wu, Hongchun; Cao, Liangzhi; Zheng, Youqi 收藏 \| 浏览/下载：7/0 \| 提交时间：2019/11/19 Acceleration Unstructured coarse mesh finite difference k-Eigenvalue neutron transport Fixed source neutron transport
	Transport Correction Method of PWR Anisotropic Scattering 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2017, 卷号: 51, 页码: 1599-1605 作者: Tian, Chao; Zheng, You-Qi; Li, Yun-Zhao; Yu, Ying-Rui; Liu, Kun 收藏 \| 浏览/下载：3/0 \| 提交时间：2019/11/26 Anisotropic scattering Calculation accuracy Correction method Diffusion calculation Group constant Homogenization parameters Neutron transport calculations Transport calculation
	Variational nodal method Fission-Source iteration acceleration using the Partitioned-Matrix technique 会议论文作者: Li, Yunzhao; Liang, Boning; Wu, Hongchun; Cao, Liangzhi 收藏 \| 浏览/下载：3/0 \| 提交时间：2019/11/26 Acceleration ratio Computational effort Discontinuity factor Floating point operations Integration techniques Neutron transport calculations Orthogonal basis function Variational nodal method
	Total sensitivity and uncertainty analysis code development for neutron-physics calculations 会议论文作者: Zu, Tiejun; Wan, Chenghui; Cao, Liangzhi; Wu, Hongchun; Shen, Wei 收藏 \| 浏览/下载：2/0 \| 提交时间：2019/11/26 Microscopic cross sections Multigroup cross sections Neutron transport calculations Nuclear data Relative sensitivity coefficients Relative uncertainty Sensitivity and uncertainty analysis Statistical sampling
	Development of NECP-SARAX1.0 code for fast reactor physics calculation 期刊论文 Hedongli Gongcheng/Nuclear Power Engineering, 2014, 卷号: 35, 期号: [db:dc_citation_issue], 页码: 116-118 作者: Zheng, Youqi; Wu, Hongchun 收藏 \| 浏览/下载：9/0 \| 提交时间：2019/12/03 Continuous energy Core calculations Cross-section library MCNP calculations Neutron transport Numerical results Perturbation method Unstructured-mesh models
	Development of neutronics analysis code system for accelerator driven subcritical reactor 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 卷号: 47, 期号: [db:dc_citation_issue], 页码: 458-462 作者: Zhou, Sheng-Cheng; Wu, Hong-Chun; Cao, Liang-Zhi; Zheng, You-Qi 收藏 \| 浏览/下载：2/0 \| 提交时间：2019/12/03 Accelerator driven subcritical systems Accelerator-driven subcritical reactors External neutron sources Micro-depletion Neutron transport calculations Neutronics Reactor analysis methods Two step method
	Benchmark problems and results for verifying resonance calculation methodologies 会议论文作者: Wu, Hongchun; Yang, Weiyan; Qin, Yulong; He, Lei; Cao, Liangzhi 收藏 \| 浏览/下载：11/0 \| 提交时间：2019/12/10 Bench-mark problems Complicated geometry Comprehensive comparisons Different geometry Neutron transport calculations Neutron transport equation Reactor concepts Ultra fine groups
	The wavelet function expansion method for solving the neutron transport equation 会议论文作者: Wu, Hongchun; Cao, Liangzhi; Zheng, Youqi; Yang, Weiyan 收藏 \| 浏览/下载：2/0 \| 提交时间：2019/12/10 Angular discretization Discrete ordinates Discretization scheme Discretizations Neutron transport Neutron transport calculations Neutron transport equation Wavelet function
	Study on acceleration method for wavelets scaling function expansion resonance calculation 期刊论文 Hedongli Gongcheng/Nuclear Power Engineering, 2010, 卷号: 31, 期号: [db:dc_citation_issue], 页码: 16-20 作者: Zu, Tie-Jun; Wu, Hong-Chun; Cao, Liang-Zhi; Yang, Wei-Yan; Liu, Guo-Ming 收藏 \| 浏览/下载：3/0 \| 提交时间：2019/12/10 Acceleration method Calculation efficiency Complex resonances Neutron transport calculations Neutron transport equation Probability methods Scaling functions Self-shielding calculation
	Application of wavelets scaling function expansion to continuous-energy neutron transport calculation 期刊论文 Hedongli Gongcheng/Nuclear Power Engineering, 2009, 卷号: 30, 期号: SUPPL. 1, 页码: 18-22+38 作者: Yang, Wei-Yan; Wu, Hong-Chun; Cao, Liang-Zhi; Zheng, You-Qi 收藏 \| 浏览/下载：2/0 \| 提交时间：2019/12/18 Continuous energy Energy distributions Neutron transport Neutron transport calculations Neutron transport equation Self-shielding calculation Thermal neutron energy Wavelet

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