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《Chinese Journal of Nuclear Science and Engineering》 1993-01
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TECHNIQUE OF DIVISION OF THE THERMAL NEUTRONS IN NODAL METHOD

RUAN KEQIANG;XUE CHANGMIN China Institute of Atomic Energy  
In this paper a new approach to the decoupling of the two group diffusion equations is devised. The core thermal neutrons are divided into two parts. Thermal neutrons which never leave the core through the core boundary constitute the one part and the remainder thermal neutrons the other. By treating the two perts of thermal neotrons with different techniques, we get decoupled two group diffusion nodal e- quations, which are solved far more fast while preserving a very high accuracy.
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【Co-references】
Chinese Journal Full-text Database 10 Hits
1 Xie Zhongsheng;The Chebyshev Polynomial Extrapolation Technique for the Nodal Multigroups Neutron Diffusion Calculation[J];Nuclear Power Engineering;1988-05
2 Zhang Zongyao Li Datu Yao Dong Cheng Heping (Nuclear Power Institute of China, Chengdu, 610041) Xie Zhongsheng Yin Banghua (Xi'an Jiaotong University, 710049);TPFAP——a Code Package for LWR Fuel Assembly Calculation[J];Nuclear Power Engineering;1993-02
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4 ZHANG Ying 1 ,XIE Zhong-sheng 2 ,CHEN Da 1 ,JING Chun-yuan 1(1.Northwest Institute of Nuclear Technology,Xi'an710024,Chian;2.Nuclear Energy Department of Xi'an Jiaotong University,710049,China);Calculation of Flux Distribution in Hexagonal LWR Fuel Assembly by Interface Current Method[J];Nuclear Power Engineering;2002-02
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7 WANG Tao; ZHANG Ying; ZHANG Shao-hong; XIE Zhong-sheng; CHENG He-ping XI'an jiaotong University, XI'an of shaanxi Prov. 710049,China Northwest Institute of Nuclear Technology, XI'an of Shaanxi Prov. 710024, China Beijing Nuclear Engineering Institute, Beijing 100840, China;Verification of hexagonal assembly homogenization code TPFAP-HEX and its application to WWERs[J];Chinese Journal of Nuclear Science and Engineering;2004-01
8 HUO Xiao-dong 1, XIE Zhong-sheng 1, LIAO Cheng-kui 2(1. Xi’an Jiaotong University, Xi’an of Shaanxi Prov. 710049,Chin a;2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233 ,China);The application of nonlinear iteration semi-analytic nodal method in CANDU reactor fuel management[J];Chinese Journal of Nuclear Science and Engineering;2004-04
9 CHEN Chang-you (Beijing Institute of Nuclear Engineering, Beijing 100840, China);A numerical method of solving the point reactor neutron kinetics euations[J];Chinese Journal of Nuclear Science and Engineering;2005-01
10 ( China Institute of Atomic Energy) Keywords dynamic parameters delayed neutron mean generation time of neutrons neutronic calculation for FBR;CALCULATION OF DYNAMIC PARAMETERS IN HEXAGONAL NODAL PROGRAM LI ZEHUA[J];CHINESE JOURNAL OF NUCLEAR SCIENCE AND ENGINEERING;1997-03
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