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NECP SCI文章总览

发布时间：2017-07-18 18:01:20    点击量：

​2018年
【1】Chen Zhao, Zhouyu Liu, Liang Liang, Jun Chen, Liangzhi Cao, Hongchun Wu. Improved leakage splitting method for the 2D/1D transport calculation[J].​ Progress in Nuclear Energy, 2018, 105:202-210.
【2】Jun Chen, Zhouyu Liu, Chen Zhao, Qingming He, Tiejun Zu, Liangzhi Cao, Hongchun Wu. A new high-fidelity neutronics code NECP-X[J]. Annals of Nuclear Energy, 2018, 116:417-428.
​【3】Qingming He, Liangzhi Cao, Hongchun Wu, Benoit Forget, Kord Smith. Predicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method[J]. Annals of Nuclear Energy, 2018, 111: 188-203.
​【4】Zhouyu Liu, Jun Chen, Liangzhi Cao, Chen Zhao, Qingming He, Hongchun Wu. Development and verification of the high-fidelity neutronics and thermal-hydraulic coupling code system NECP-X/SUBSC[J]. Progress in Nuclear Energy, 2018, 103: 114-125.
​【5】Zhouyu Liu, Qingming He, Xingjian Wen, Tiejun Zu, Linagzhi Cao, Hongchun Wu. Improvement and optimization of the pseudo-resonant-nuclide subgroup method in NECP-X[J]. Progress in Nuclear Energy, 2018, 103: 60-73.
​【6】Zhouyu Liu, Liang Liang, Jun Chen, Chen Zhao, Hongchun Wu. Accuracy and analysis of the iteratively coupling 2D/3D method for the three-dimensional transport calculations[J]. Annals of Nuclear Energy, 2018, 113: 130-138.
​【7】Zhouyu Liu, Qingming He, Tiejun Zu, Liangzhi Cao, Hongchun Wu, Qian Zhang. The pseudo-resonant-nuclide subgroup method based global-local self-shielding calculation scheme[J]. Journal of Nuclear Science and Technology, 2018, 55(2): 217-228.
2016年
【1】Tiejun Zu, Chao Yang, Liangzhi Cao, Hongchun Wu.Nuclear data uncertainty propagation analysis for depletion calculation in PWR and FR pin-cells.Annals of Nuclear Energy.2016,94：399-408.
【2】Tiejun Zu, Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen.Total uncertainty analysis for PWR assembly based on the statistical sampling method.Nuclear Science and Engineering.2016,183：371-386.
【3】Tiejun Zu, Qian Zhang, Hongchun Wu, Liangzhi Cao, Qingming He, Won Sik Yang.Heterogeneous Pseudo-Resonant Isotope Method for Resolved Resonance Interference Treatment in Resonance Self-Shielding Calculation.Nuclear Science and Engineering.2016,184：495-513.
【4】Baolin Liu, Liangzhi Cao, Hongchun Wu, et al..Pre-conceptual core design of a small modular fast reactor cooled by supercritical CO2.Nuclear Engineering and Design.2016,300：339-348.
【5】Zhifeng Li, Liangzhi Cao, Hongchun Wu，Qingming He.The impacts of thermal neutron scattering effect and resonance elastic scattering effect on FHRs.Annals of Nuclear Energy.2016,97：102-114.
【6】Zhifeng Li, Liangzhi Cao, Hongchun Wu, Qingming He, Wei Shen.On the improvements in neutronics analysis of the unit cell for the pebble-bed fluoride-salt-cooled high-temperature reactor.Progress in Nuclear Energy.2016,93：287-296.
【7】Kai Huang, Hongchun Wu, Liangzhi Cao, Yunzhao Li, Wei Shen.Improvements to the Transmutation Trajectory Analysis of depletion evaluation.Annals of Nuclear Energy.2016,87：637-647.
【8】Li, YZ; Gao, SN; Wu,HC;Cao,LZ; Shen, W.PWR few-group constants parameterization analysis.Progress in Nuclear Energy.2016,88：104-117.
【9】Yunzhao Li, Qingming He, Liangzhi Cao, Hongchun Wu, and Tiejun Zu.Resonance Elastic Scattering and Interference Effects Treatments in Subgroup Method .NUCLEAR ENGINEERING AND TECHNOLOGY .2016,48：339-350.
【10】Qingming He, Liangzhi Cao, Hongchun Wu, Tiejun Zu.Improved resonance calculation of fluoride salt-cooled high-temperature reactor based on subgroup method.Annals of Nuclear Energy.2016,88：204-217.
【11】Yunlong Xiao, Hongchun Wu, Youqi Zheng, Kunpeng Wang.Neutronics studies on the feasibility of developing fast breeder reactor with flexible breeding ratio.Journal of Nuclear Science and Technology.2016,53：129-138.

2015年
【1】He, Mingtao; Wu, Hongchun; Zheng, Youqi; et al..Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport method .NUCLEAR ENGINEERING AND DESIGN .2015,295：489-499.
【2】Liangzhi Cao; Gerlach, A.; Yunlin Xu; Downar, T.; Lee, J.C..Neutronics modeling of the SPERT III E-Core critical experiments with MPACT and KENO.Annals of Nuclear Energy.2015,80：207-18.
【3】Zhuang, K (Zhuang, Kun) ; Cao, LZ (Cao, Liangzhi) ; Zheng, YQ (Zheng, Youqi); Wu, HC (Wu, Hongchun) .Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design.JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY.2015,52：251-263.
【4】Zhang, Q (Zhang, Qian) ; Wu, HC (Wu, Hongchun) ; Cao, LZ (Cao, Liangzhi) ; Zheng, YQ (Zheng, Youqi).An Improved Resonance Self-Shielding Calculation Method Based on Equivalence Theory.NUCLEAR SCIENCE AND ENGINEERING.2015,179：233-252.
【5】Yuan XB, Cao LZ, Wu HC.Pre-conceptual study of small modular PbBi-cooled nitride fuel reactor core characteristics.NUCLEAR ENGINEERING AND DESIGN.2015,285：23-30.
【6】Zhouyu Liu; Kochunas, B.; Collins, B.; Downar, T.; Yunlin Xu; Hongchun Wu.Model and analysis of performance for the method of characteristics direction probabilities with boundary averaging.Progress in Nuclear Energy.2015,80：110-18.
【7】Xunzhao Li, Shengcheng Zhou, Youqi Zheng, Kunpeng Wang, Hongchun Wu.Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale.Nuclear Engineering and Design.2015,292：57-68.
【8】Yunzhao Li, Yongping Wang, Boning Liang, Wei Shen.Partitioned-Matrix acceleration to the Fission-Source iteration of the Variational Nodal Method.Progress in Nuclear Energy.2015,85：640-647.
【9】Tiejun Zu, Hongchun Wu, Youqizheng, Liangzhi Cao.Economics analysis of fuel cycle cost of fusion–fission hybrid reactors based on different fuel cycle strategies.Fusion Engineering and Design.2015,90：119-126.
【10】Qingming He, Liangzhi Cao, Hongchun Wu, Tiejun Zu.Improved resonance calculation of fluoride salt-cooled high-temperature reactor based on subgroup method.Annals of Nuclear Energy.2015,88：204-217.
【11】Yong Liu, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Wei Shen.Eigenvalue implicit sensitivity and uncertainty analysis with the subgroup resonance-calculation method.Annals of Nuclear Energy.2015,79：18-26.
【12】Chenghui Wan, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Wei Shen.Code development for eigenvalue total sensitivity analysis and total uncertainty analysis.Annals of Nuclear Energy.2015,85：788-797.
【13】Yunzhao Li, E. E. Lewis, Micheal A. Smith, Hongchun Wu, Liangzhi Cao.Preconditioned Multigroup GMRES Algorithms for the Variational Nodal Method.Nuclear Science and Engineering.2015,179：42-58.
【14】Liu, Zhouyu, Collins Benjamin, Kochunas Brendan, Downar Thomas, Xu Yunlin, Wu Hongchun.Theory and analysis of accuracy for the method of characteristics direction probabilities with boundary averaging.ANNALS OF NUCLEAR ENERGY.2015,11：212-222.

2015年以前
【1】Zheng Zheng, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Hongbo Zhang.A deterministic and Monte Carlo coupling method for PWR cavity radiation streaming calculation.Annals of Nuclear Energy.2014,63：162-171.
【2】Lei He, Hongchun Wu, Liangzhi Cao, Yunzhao Li.Improvements of the subgroup resonance calculation code SUGAR.Annals of Nuclear Energy.2014,66：5-12.
【3】Chuanqi Zhao, Liangzhi Cao, Hongchun Wu, Youqi Zheng.Pre-conceptual core design of SCWR with annular fuel rods.Nuclear Engineering and Design.2014,267：23-33.
【4】Tiejun Zu, Hongchun Wu, Youqi Zheng, Liangzhi Cao. Burnup calculations of light water-cooled pressure tube blanket for a fusion-fission hybrid reactor.Fusion Engineering and Design.2014,89：793-799.
【5】Shengcheng Zhou, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Kai Huang, Mingtao He,Xunzhao Li. LAVENDER: A steady-state core analysis code for design studies of accelerator driven subcritical reactors.Nuclear Engineering and Design.2014,278：434-444.
【6】Ammar Ahmad, Liangzhi Cao, Hongchun Wu, Chuanqi Zhao.Conceptual Design of pressure-tube super critical water reactor with inverted geometry.Nuclear Engineering and Design..2014,278：618-626.
【7】Ammar Ahmad, Liangzhi Cao, Hongchun Wu. Coupled Analysis and improvements for Canadian-SCWR core design.Nuclear Engineering and Design..2014,268：104-112.
【8】Kun Zhuang, Liangzhi Cao, Youqi Zheng, Hongchun Wu. Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design.Journal of Nuclear Science and Technology.2014,：-.
【9】Yuxiong Cheng, HongChun Wu,Liangzhi Cao, Youqi Zheng.Three-Dimensional Invere Transport Solver Based on Compressive Sensing Technique.Transport Theory and Statistical Physics.2014,42：345-363.
【10】Youqi Zheng, Hongchun Wu, Liangzhi Cao.Economic Evaluation on the MOX Fuel in the Closed Fuel Cycle.Science and Technology of Nuclear Installations.2013,：-.
【11】Youqi Zheng, Hongchun Wu, Liangzhi Cao.Stability analysis of CMFD acceleration for the wavelet expansion method of neutron transport equation.Nuclear Engineering and Design.2013,251：142-147.
【12】Yunzhao Li, Hongchun Wu, Liangzhi Cao. Unstructured triangular nodal-SP3 method based on an exponential function expansion.Nucl. Sci. Eng.,.2013,174：163-171.
【13】Tengfei Zhang, Hongchun Wu, YouqiZheng, Liangzhi Cao, Yunzhao Li.A 3d transport-based core analysis code for research reactors with unstructed geometry.Nuclear Engineering and Design..2013,：599-610.
【14】Guangchun Zhang, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Yunzhao Li, Zhouyu Liu.Study on three-dimensional heterogeneous calculation of ITER test blanket module with deterministic method.Fusion Engineering and Design.2013,88：413-420.
【15】Hongchun Wu,Tiejun Zu,Suizheng Qiu,Xinli Gao,Youqi Zheng,Liangzhi Cao,Wenxi Tian.A fusion-fission hybrid reactor with water-cooled pressure tube blanket for energy production.Progress in nuclear energy.2013,64：1-7.
【16】Tiejun Zu,Hongchun Wu,Youqi Zheng,Liangzhi Cao,Chao Yang.NAPTH:Neutronics analysis code system for the fusion-fission hybrid reactor with pressure tube tybe blanket. 88,170-176,2013.Fusion engineering and design.2013,88：170-176.
【17】Chuanqi Zhao,Liangzhi Cao,Hongchun Wu,Jue Yang,Yong Zhagn.Conceptual design of a supercritical water reactor with double-row-rod assembly.Progress in Nuclear Energy.2013,63：86-95.
【18】Chao Yang,Liangzhi Cao,Hongchun Wu,Youqi Zheng,Tiejun Zu.Neutronics analysis of minor actinides transmutation in a fusion-driven subcritical system..Fusion engineering and design.2013,：-.
【19】Kun Liu,Hongchun Wu,Liangzhi Cao,Youqi Zheng.Studies on LLFP transmutation in a pressurized water reactor.Journal of nuclear science and technology.2013,50：518-598.
【20】Kun Liu,Hongchun Wu,Liangzhi Cao,Youqi Zheng,Changhui Wang.A code development for LLFP transmutation analysis based on the whole Pin-Wise calculation in PWRs.Nuclear Engineering and design.2013,256：56-66.
【21】Youqi Zheng, Tiejun Zu, Hongchun Wu, Liangzhi Cao, Chao Yang.The neutronics studies of a fusion fission hybrid reactor using pressure tube blankets.Fusion Engineering and Design.2012,87：1589-1596.
【22】Youqi Zheng, Hongchun Wu, Liangzhi Wu. Application of the wavelet expansion method in spatial-angular discretization of the neutron transport equation.Annals of Nuclear Energy.2012,43：31-38.
【23】Yang P, Cao LZ, Wu HC, Wang CH.. Core design study on CANDU-SCWR with 3D thermal-hydraulics coupling.Nuclear Engineering and Design.2011,241：4714-4719.
【24】Wang Changhui, Wu Hongchun, Cao Liangzhi et al.. On-line Reconstruction of In-core Power Distribution by Harmonics Expansion Method.Nuclear Engineering and Design.2011,241：3042-3050.
【25】Hongbo Zhang, Hongchun Wu, Liangzhi Cao.An acceleration technique for 2D MOC based on Krylov subspace and domain decomposition methods.Annals of Nuclear Energy.2011,38：2742-2751.
【26】Liu Zhouyu, Wu Hongchun, Cao Liangzhi, Chen Qichang, Li Yunzhao.A new three-dimensional method of characteristics for the neutron transport calculation.Annals of Nuclear Energy.2011,38：447-454.
【27】Yang WY, Wu HC, Zheng YQ, Cao LZ. .Application of Wavelets Scaling Function Expansion Method in Resonance Self-shielding Calculation.Annals of Nuclear Energy.2010,37：653-663.
【28】Yunzhao Li, Hongchun Wu, Liangzhi Cao.FMSR: A code system for in-core fuel management calculation of aqueous homogeneous solution reactor.Nuclear Engineering and Design.2010,240：763-770.
【29】Youqi Zheng, Hongchun Wu, Liangzhi Cao, N. Z. Cho. .Daubechies' Wavelet Method for Angular Solution of the Neutron Transport Equation.Nuclear Science and Engineering.2010,164：87-104.
【30】Liu QJ, Wu HC, Cao LZ. .Solution of the Multiplying Binary Stochastic Media Based on L–P Equation in 1D Spherical Geometry.Nuclear Engineering and Design.2010,240：132-138.
【31】Youqi Zheng, Hongchun Wu, Liangzhi Cao.Wavelet-based angular dependence analysis of the heterogeneous calculation on MOX fuel lattice.Nuclear Engineering and Design.2009,239：1804-1810.
【32】Youqi Zheng, Hongchun Wu, Liangzhi Cao.An improved three-dimensional wavelet-based method for solving the first-order Boltzmann transport equation.Annals of Nuclear Energy.2009,36：1440-1449.
【33】Liangzhi Cao, Yoshiaki Oka, Yuki Ishiwatari, et.al.. Three-dimensional core analysis on a super fast reactor with negative local void reactivity.Nuclear Engineering and Design.2009,239：408-417.
【34】Qichang Chen, Hongchun Wu, Liangzhi Cao.Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD.Nuclear Engineering and Design.2008,23：2823-2933.
【35】Guoming Liu, Hongchun Wu, Liangzhi Cao.Transmission probability method for solving neutron transport equation in three-dimensional triangular-z geometry.Nuclear Engineering and Design.2008,238：2285-2291.
【36】Liangzhi Cao, Hongchun Wu, Youqi Zheng. Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretization.Nuclear Engineering and Design.2008,238：2292-2301.
【37】Liangzhi Cao, Yoshiaki Oka, Yuki Ishiwatari, et.al..Fuel, core design and subchannel analysis of a Super Fast Reactor.Journal of Nuclear Science and Technology.2008,45：138-148.
【38】Liangzhi Cao, Hongchun Wu. .A spherical harmonics—Finite element discretization of the self-adjoint angular flux neutron transport equation.Nuclear Engineering and Design.2007,237：2232-2239.
【39】Lu HL, Wu HC.. A nodal S-N transport method for three-dimensional triangular-z geometry.Nuclear Engineering and Design.2007,237：830-839.
【40】Ju HT, Wu HC, Zhou YQ, et al. .A least-squares finite-element S-n method for solving first-order neutron transport equation.Nuclear Engineering and Design.2007,237：823-829.
【41】Ju HT, Wu HC, Yao D, et al.. Least-squares finite-element S-N method for solving three-dimensional transport equation.Annals of Nuclear Energy.2007,34：527-532.
【42】Lu HL, Wu HC, Cao LZ, et al. .Two-dimensional nodal transport method for triangular geometry.Annals of Nuclear Energy.2007,34：424-432.
【43】Wu HC, Liu PP, Zhou YQ, et al. .Transmission probability method based on triangle meshes for solving unstructured geometry neutron transport problem.Nuclear Engineering and Design.2007,237：28-37.
【44】Cao Liangzhi, Wu Hongchun, .Spherical Harmonics Method for Neutron Transport Equation Based on Unstructured-meshes .Nuclear Science and Techniques.2004,15：335-330.
【45】Wu HC. .Pressurized water reactor reloading optimization using genetic algorithms.Annals of Nuclear Energy.2001,28：1329-1341.
【46】Wu HC, Sato D, Takeda T. .Minor actinides incineration by loading moderated targets in fast reactor.Journal of Nuclear Science and Technology.2000,37：380-386.