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学者姓名:吴宏春

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< Page ,Total 45 >
Heterogeneous discontinuity factor treatment in Variational Nodal Method EI
期刊论文 | 2019 , 127 , 341-350 | Annals of Nuclear Energy
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Abstract :

To handle the control rod cusping effect in Pressurized Water Reactor (PWR) core calculation, the heterogeneous Variational Nodal Method (VNM) employed by the fuel management calculation code system NECP-Bamboo has been enhanced to treat heterogeneous discontinuity factor (DF) appearing on nodal interface. To solve the neutron-diffusion equations with heterogeneous DF, firstly, the functional in VNM is modified to contain the discontinuity of neutron flux in the surface integral term. Secondly, other than volumetric flux and surface partial currents, cross sections and surface DF are also expanded into the sum of orthogonal piece-wise polynomials to construct the nodal response matrixes. Four test problems in this paper including the CISE, Henry-Worley, HAFAS benchmark problems and the BEAVRS problems were employed to verify the method in treating heterogeneous DF. It has been demonstrated that the control rod cusping effect can be fully eliminated by the heterogeneous VNM with heterogeneous DF in terms of control rod differential worth and three-dimensional pin-power profile. © 2018 Elsevier Ltd

Keyword :

Bench-mark problems Core calculations Differential worth Discontinuity factor Neutron diffusion equations Partial currents Surface integrals Variational nodal method

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GB/T 7714 Li, Yunzhao , Liang, Boning , Wu, Hongchun et al. Heterogeneous discontinuity factor treatment in Variational Nodal Method [J]. | Annals of Nuclear Energy , 2019 , 127 : 341-350 .
MLA Li, Yunzhao et al. "Heterogeneous discontinuity factor treatment in Variational Nodal Method" . | Annals of Nuclear Energy 127 (2019) : 341-350 .
APA Li, Yunzhao , Liang, Boning , Wu, Hongchun , Li, Zhipeng , Yang, Jiewei . Heterogeneous discontinuity factor treatment in Variational Nodal Method . | Annals of Nuclear Energy , 2019 , 127 , 341-350 .
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Validation of SARAX for the China Fast Reactor with the extrapolated experimental data EI
期刊论文 | 2019 , 127 , 188-195 | Annals of Nuclear Energy
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Abstract :

The validation works have been implemented to a newly-developed code SARAX for China Fast Reactor (CFR) in this paper. Different with the conventional way to validate the code using the dedicated experimental data, a theoretical approach was proposed and implemented by using the existing similar experimental data. This theoretical approach is based on the technology of sensitivity/uncertainty analysis, similarity analysis and nuclear-data adjustment. In our previous works, detailed introduction towards sensitivity/uncertainty analysis and similarity analysis have been implemented to distinguish the existing experiments which are 'similar’ to the CFR's criticality characteristics. This paper focus on the method to extrapolate the 'similar’ experimental data to predict the best-estimate measurements of CFR with application of nuclear-data adjustment, providing reference values to validate the SARAX code. From the numerical results, it can be observed that through nuclear-data adjustment, the simulation results of the existing experiments can agree well with corresponding measurements, with the bias reduced notably to be within 25 pcm. Moreover, the nuclear-data adjustment can also improve the nuclear-data uncertainties notably, with the relative uncertainties of the reactor keff due to nuclear data having been reduced from the value exceeding 1.0% to the values about 0.15%. © 2018

Keyword :

Code validation Nuclear data Numerical results Reference values Relative uncertainty Sensitivity/uncertainty analysis Similarity analysis Theoretical approach

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GB/T 7714 Wan, Chenghui , Qiao, Liang , Zheng, Youqi et al. Validation of SARAX for the China Fast Reactor with the extrapolated experimental data [J]. | Annals of Nuclear Energy , 2019 , 127 : 188-195 .
MLA Wan, Chenghui et al. "Validation of SARAX for the China Fast Reactor with the extrapolated experimental data" . | Annals of Nuclear Energy 127 (2019) : 188-195 .
APA Wan, Chenghui , Qiao, Liang , Zheng, Youqi , Cao, Liangzhi , Wu, Hongchun . Validation of SARAX for the China Fast Reactor with the extrapolated experimental data . | Annals of Nuclear Energy , 2019 , 127 , 188-195 .
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The material-region-based 2D/1D transport method EI
期刊论文 | 2019 , 128 , 1-11 | Annals of Nuclear Energy
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The 2D/1D transport method is the dominant method for high-fidelity direct whole-core transport calculations, which attracts a lot of attention in recent decades. In the 2D/1D method, some sources of deviation are introduced, including spatial and angular approximation of leakage term and cross-section homogenization for 1D axial calculation. These approximations are analyzed and a material-region-based 2D/1D transport method with anisotropic leakage term, which avoids cross-section homogenization, as well as reduces spatially flat leakage approximation, are developed to improve accuracy at the expense of acceptable memory and efficiency loss. Finally, a BWR assembly case, the C5G7 benchmark and a rod-cluster assembly case are tested to verify the accuracy and performance of the material-region-based 2D/1D method. © 2018 Elsevier Ltd

Keyword :

Cluster assembly Efficiency loss High-fidelity Leakage terms Material region NECP-X Transport method Whole-core transport

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GB/T 7714 Liu, Zhouyu , Zhao, Chen , Cao, Lu et al. The material-region-based 2D/1D transport method [J]. | Annals of Nuclear Energy , 2019 , 128 : 1-11 .
MLA Liu, Zhouyu et al. "The material-region-based 2D/1D transport method" . | Annals of Nuclear Energy 128 (2019) : 1-11 .
APA Liu, Zhouyu , Zhao, Chen , Cao, Lu , Wu, Hongchun , Cao, Liangzhi . The material-region-based 2D/1D transport method . | Annals of Nuclear Energy , 2019 , 128 , 1-11 .
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An improved fitting method for subgroup parameters based on the heterogeneous cells EI SCIE
期刊论文 | 2019 , 56 (2) , 179-192 | Journal of Nuclear Science and Technology
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An accurate subgroup parameters fitting method, where background cross sections obtained based on heterogeneous cells are used to fit the subgroup level and subgroup weight, is proposed in this paper. Due to the dependence of background cross section on the subgroup level, the calculation of the subgroup parameters is a nonlinear problem, which causes the iteration between fitting subgroup parameters and updating background cross sections. The cubic spline interpolation method is used to update the background cross sections to avoid frequently solving fixed source equations. In the fitting process, the negative subgroup parameters are often obtained, and the accuracy of the subgroup parameters is very sensitive to the iterative initial values of subgroup levels. To avoid these problems, additional constraints ensuring positive subgroup parameters and guaranteeing numerical stability are added to the optimization function. Penalty function method is used to convert the optimization problem with constraints into the one without constraints, making the problem easy to be solved. The proposed method is tested against the problems of pin cell, pressurized water reactor assemblies and plate-type assembly. The numerical results show that the self-shielded cross sections calculated by the proposed method agree well with those by Monte Carlo code. © 2018, © 2018 Atomic Energy Society of Japan. All rights reserved.

Keyword :

Cubic spline interpolation method Fitting method Nonlinear problems Optimization function Optimization problems Penalty function methods Subgroup method subgroup parameters

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GB/T 7714 Zu, Tiejun , Xia, Fan , Wu, Hongchun . An improved fitting method for subgroup parameters based on the heterogeneous cells [J]. | Journal of Nuclear Science and Technology , 2019 , 56 (2) : 179-192 .
MLA Zu, Tiejun et al. "An improved fitting method for subgroup parameters based on the heterogeneous cells" . | Journal of Nuclear Science and Technology 56 . 2 (2019) : 179-192 .
APA Zu, Tiejun , Xia, Fan , Wu, Hongchun . An improved fitting method for subgroup parameters based on the heterogeneous cells . | Journal of Nuclear Science and Technology , 2019 , 56 (2) , 179-192 .
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NECP-Atlas: A new nuclear data processing code EI Scopus SCIE
期刊论文 | 2019 , 123 , 153-161 | Annals of Nuclear Energy
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A new nuclear data processing code called NECP-Atlas is under development at Xi'an Jiaotong University in China. The motivation for the development is to establish a platform to carry out deeper researches on nuclear data processing methods to satisfy the demands on accurate cross sections in the fields of high-fidelity transport simulation and advanced reactor design. The present paper describes the methods used in the current version of NECP-Atlas and demonstrates the performance and accuracy of the code on a variety of benchmarks. At the present time, NECP-Atlas can process ENDF/B-VII.1, ENDF/B-VII.0, CENDL-3.1, JEFF-3.2 and JENDL-4.0 evaluations, and generate WIMS-D and ACE format libraries. The accuracy of the code is comparable with NJOY2016. NECP-Atlas is competent to provide cross sections for deterministic and Monte Carlo transport calculations. © 2018 Elsevier Ltd

Keyword :

Advanced reactor design Cross section Multi band NECP-Atlas Resonance elastic scattering Transport calculation Transport simulation Xi'an Jiaotong University

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GB/T 7714 Zu, Tiejun , Xu, Jialong , Tang, Yongqiang et al. NECP-Atlas: A new nuclear data processing code [J]. | Annals of Nuclear Energy , 2019 , 123 : 153-161 .
MLA Zu, Tiejun et al. "NECP-Atlas: A new nuclear data processing code" . | Annals of Nuclear Energy 123 (2019) : 153-161 .
APA Zu, Tiejun , Xu, Jialong , Tang, Yongqiang , Bi, Huchao , Zhao, Fei , Cao, Liangzhi et al. NECP-Atlas: A new nuclear data processing code . | Annals of Nuclear Energy , 2019 , 123 , 153-161 .
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Development and Application of Angle and Ray Parallel in NECP-X EI Scopus CSCD PKU
期刊论文 | 2018 , 52 (3) , 405-411 | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology
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Long computing time and abundant memory requirement are two most critical issues for the method of characteristics (MOC) when applied for the three-dimensional whole-core transport calculation. The massive parallel is an effective method to solve these problems. The traditional parallel strategy based on space decomposition is limited by its degree of parallelism when solving the smaller size problem, which means it can not take full advantage of parallel resources. In this paper, a multilevel parallel of angle and characteristic ray was developed based on the space parallel implemented in the high-fidelity neutronics code NECP-X. To get good load balance of angle parallel, a greedy algorithm was applied, and to save memory in the ray parallel, a dynamic scheduling feature within shared memory architectures was used. The numerical results show that the parallel efficiency of the angle and characteristic ray in NECP-X is high. And it further expands the parallel degree based on the special decomposition parallelism. © 2018, Editorial Board of Atomic Energy Science and Technology. All right reserved.

Keyword :

Angle parallel Characteristic ray parallel Greedy algorithms Load balance Method of characteristics Multilevel parallel

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GB/T 7714 Ma, Dangwei , Liu, Zhouyu , Zhao, Chen et al. Development and Application of Angle and Ray Parallel in NECP-X [J]. | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (3) : 405-411 .
MLA Ma, Dangwei et al. "Development and Application of Angle and Ray Parallel in NECP-X" . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology 52 . 3 (2018) : 405-411 .
APA Ma, Dangwei , Liu, Zhouyu , Zhao, Chen , Chen, Jun , Cao, Liangzhi , Wu, Hongchun et al. Development and Application of Angle and Ray Parallel in NECP-X . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (3) , 405-411 .
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Improvement of Multi-group Cross Section Data Library of Bamboo-Lattice Code EI Scopus CSCD PKU
期刊论文 | 2018 , 52 (8) , 1367-1373 | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology
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Abstract :

Based on the ENDF/B-Ⅶ.0 nuclear evaluation data library, an improved multi-group cross section data library NECL2.0 was produced for Bamboo-Lattice code by using the nuclear data processing code NJOY and LATTICE_PRE. The results based on benchmark and numerical analysis show that the calculation results of infinite multiplication factor kinf, fission rate distribution and few-group homogenized cross section by using NECL2.0 library agree well with the corresponding reference values. Considering the resonance of Ag-In-Cd can increase accuracy of kinf by 1 000 pcm. Compared with reference values, the maximum relative deviation of fission rate reduces from -0.97% to -0.53%. Considering the resonance of zirconium in cladding can improve the accuracy of kinf by about 60 pcm. © 2018, Editorial Board of Atomic Energy Science and Technology. All right reserved.

Keyword :

Calculation results Cross section data Data library Fission rates Lattice codes Multiplication factor Reference values Relative deviations

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GB/T 7714 Wang, Dongyong , Wu, Hongchun , Li, Yunzhao et al. Improvement of Multi-group Cross Section Data Library of Bamboo-Lattice Code [J]. | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (8) : 1367-1373 .
MLA Wang, Dongyong et al. "Improvement of Multi-group Cross Section Data Library of Bamboo-Lattice Code" . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology 52 . 8 (2018) : 1367-1373 .
APA Wang, Dongyong , Wu, Hongchun , Li, Yunzhao , He, Qingming . Improvement of Multi-group Cross Section Data Library of Bamboo-Lattice Code . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (8) , 1367-1373 .
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Study on Three-Dimensional Neutron Diffusion Heterogeneous Variational Nodal Method and Flat Source Acceleration Method EI Scopus CSCD PKU
期刊论文 | 2018 , 39 (2) , 86-89 | Hedongli Gongcheng/Nuclear Power Engineering
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Abstract :

As a foundation of three-dimensional whole-core heterogeneous transport calculation, a 3D heterogeneous variational nodal method is proposed, which employs iso-parametric finite elements within each node and piecewise constants along nodal interfaces to explicitly describe the pin-resolved heterogeneous geometry. This means full elimination of the homogenization approximation. Meanwhile, the flat source acceleration method is proposed accordingly to reduce the computational costs. Numerical results show that the method is accurate and the flat source region acceleration method can effectively decrease the memory storage and computational time without degrading the accuracy. © 2018, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

Keyword :

Acceleration method Heterogeneous geometry Homogenization approximation Iso-parametric Neutron diffusion Piece-wise constants Transport calculation Variational nodal method

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GB/T 7714 Zhang, Tengfei , Wu, Hongchun , Cao, Liangzhi et al. Study on Three-Dimensional Neutron Diffusion Heterogeneous Variational Nodal Method and Flat Source Acceleration Method [J]. | Hedongli Gongcheng/Nuclear Power Engineering , 2018 , 39 (2) : 86-89 .
MLA Zhang, Tengfei et al. "Study on Three-Dimensional Neutron Diffusion Heterogeneous Variational Nodal Method and Flat Source Acceleration Method" . | Hedongli Gongcheng/Nuclear Power Engineering 39 . 2 (2018) : 86-89 .
APA Zhang, Tengfei , Wu, Hongchun , Cao, Liangzhi , Li, Yunzhao , Xiong, Jinbiao , Liu, Xiaojing . Study on Three-Dimensional Neutron Diffusion Heterogeneous Variational Nodal Method and Flat Source Acceleration Method . | Hedongli Gongcheng/Nuclear Power Engineering , 2018 , 39 (2) , 86-89 .
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Subgroup Resonance Calculation Method under Rim Effect in Fuel Rod EI Scopus CSCD PKU
期刊论文 | 2018 , 52 (8) , 1374-1380 | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology
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Abstract :

Pseudo-resonant-nuclide subgroup method (PRNSM) is capable to treat spatially self-shielding effect in fuel rod. However, it requires the number densities of resonance nuclides to be constant throughout the whole fuel region, so the spatial distributions of resonance nuclides' densities caused by rim effect cannot be taken into account. To solve this problem, a new method was proposed on the base of improved pseudo-resonant-isotope-theory. Numerical results show that this method solves the limit of PRNSM on rim effect and has higher accuracy than Bondarenko iteration method and resonance interference factor method. © 2018, Editorial Board of Atomic Energy Science and Technology. All right reserved.

Keyword :

Fuel rods Interference factor Iteration method Number density Numerical results Self shielding effect Self-shielding Subgroup method

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GB/T 7714 Zhang, Qian , Li, Song , Zhao, Qiang et al. Subgroup Resonance Calculation Method under Rim Effect in Fuel Rod [J]. | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (8) : 1374-1380 .
MLA Zhang, Qian et al. "Subgroup Resonance Calculation Method under Rim Effect in Fuel Rod" . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology 52 . 8 (2018) : 1374-1380 .
APA Zhang, Qian , Li, Song , Zhao, Qiang , Song, Peitao , Cao, Liangzhi , Wu, Hongchun . Subgroup Resonance Calculation Method under Rim Effect in Fuel Rod . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (8) , 1374-1380 .
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Feasibility Study of Heterogeneous Resonance Integral Table of 238U EI Scopus CSCD PKU
期刊论文 | 2018 , 52 (7) , 1174-1180 | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology
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As the complexity and accuracy requirement increase of neutronics calculation of the next generation reactor, it is necessary to introduce the heterogeneous resonance integral table into the multi-group cross section library replacing the homogeneous resonance integral table. The accuracy of embedded self-shielding calculation using heterogeneous resonance integral tables of 238U prepared in different schemes was analyzed. The results show that the density of the moderator and the concentration of boron are crucial in the practical application of heterogeneous resonance integrals. Based on the analysis results, the current scheme of the 2D heterogeneous resonance integral table was improved by a 4D interpolation table to cover all possible operating conditions of PWR. Numerical results show that the improved heterogeneous resonance integral table enhances the accuracy of resonance calculation and improves the applicability of the multi-group library. © 2018, Science Press. All right reserved.

Keyword :

Cross-section library Feasibility studies Heterogeneous systems Multi-group Numerical results Operating condition Resonance integral Self-shielding calculation

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GB/T 7714 Zhang, Qian , Li, Song , Zhao, Qiang et al. Feasibility Study of Heterogeneous Resonance Integral Table of 238U [J]. | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (7) : 1174-1180 .
MLA Zhang, Qian et al. "Feasibility Study of Heterogeneous Resonance Integral Table of 238U" . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology 52 . 7 (2018) : 1174-1180 .
APA Zhang, Qian , Li, Song , Zhao, Qiang , Wu, Hongchun , Zhuang, Kun . Feasibility Study of Heterogeneous Resonance Integral Table of 238U . | Yuanzineng Kexue Jishu/Atomic Energy Science and Technology , 2018 , 52 (7) , 1174-1180 .
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