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《Chinese Journal of Nuclear Science and Engineering》 2008-04
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Development of PWR in-core fuel management code system——GLORY

HUANG Hao1,WANG Tao1,JIANG Xiao-feng1,TANG Chun-tao1,LIANG Guan-qun2,ZHANG Shao-hong1, KONG De-ping3,LIAO Ze-jun3,WU Xi-feng3,WANG Shi-wei3(1.School of Nuclear Science and Engineering,Shanghai Jiaotong University,Shanghai 200240,China;2.Department of Computer Science and Engineering,Shanghai Jiaotong University,Shanghai 200240,China;3.Qinshan Nuclear Power Company Limited,Haiyan of Zhejiang Prov.314300,China)  
A code system——GLORY is developed based the modern "two-step" core analysis methodology with its capability to perform PWR in-core fuel management,including core tracking and preliminary loading pattern design.This paper gives an introduction to the main models,both physical and numerical ones that are adopted in GLORY.The results for its verification against these measurement data for multiple fuel cycles will be provided in another paper.
【CateGory Index】: TL329
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【Citations】
Chinese Journal Full-text Database 1 Hits
1 HUANG Hao,ZHANG Shao-hong,LI Zhi-yong(School of Nuclear Science and Engineering,Shanghai Jiaotong University,Shanghai 200240,China);Developing a fuel assembly homogenized parameter representation method based on tabulation[J];核科学与工程;2008-03
【Co-citations】
Chinese Journal Full-text Database 5 Hits
1 YANG Wei-yan;TANG Chun-tao;BI Guang-wen;YANG Bo;Shanghai Nuclear Engineering Research & Design Institute;;Development of Few Group Cross Section Calculation Model for Core Nuclear Design Code CYCAS[J];原子能科学技术;2016-05
2 ZHANG Han1,2,ZHAO Qiang2,LI Fu1(1.Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China; 2.National Key Discipline Laboratory of Nuclear Safety and Simulation Technology, Harbin Engineering University,Harbin 150001,China);Cross Section Expression Based on Neural Network Algorithm[J];原子能科学技术;2013-S1
3 WANG Cong1,CAN Xin-rong2(1.Wuhan 2nd Ship Design and Research Institute,Wuhan 430000,China; 2.College of Nuclear Science and Technology,Harbin Engineering University,Harbin 150001,China);Sensitivity Study of Feedback Parameters for Thermal-Hydraulic Coupling Code[J];原子能科学技术;2013-S1
4 LIU Tai-li,WU Fan,SHAN Ye-yu,WANG Jiang(China Nuclear Power Simulation Technology Co.,Ltd,Beijing 100094,China);Development and Application of Neutron Cross Section Pre-procedure in Nuclear Power Simulator[J];计算机仿真;2013-05
5 HUANG Hao1,WANG Tao1,JIANG Xiao-feng1,TANG Chun-tao1,LIANG Guan-qun2,ZHANG Shao-hong1, KONG De-ping3,LIAO Ze-jun3,WU Xi-feng3,WANG Shi-wei3(1.School of Nuclear Science and Engineering,Shanghai Jiaotong University,Shanghai 200240,China;2.Department of Computer Science and Engineering,Shanghai Jiaotong University,Shanghai 200240,China;3.Qinshan Nuclear Power Company Limited,Haiyan of Zhejiang Prov.314300,China);Development of PWR in-core fuel management code system——GLORY[J];核科学与工程;2008-04
【Secondary Citations】
Chinese Journal Full-text Database 2 Hits
1 XIE SHAOLIN SHEN WEI ZHU XINGUAN (Shanghai Nuclear Engineering Research & Design Institute) Keywords Qinshan Nuclear Power Plant fuel management cross section;INTERFACE METHODOLOGY AND USAGE OF IN CORE THREE DIMENSIONAL FUEL MANAGEMENT PROGRAM XSEC/3D 5[J];核科学与工程;1997-01
2 Zhao Wei;Liu Xudong (Nuclear Power Institute of China,Chengdu,610041);Treatment Program of Fuel Assembly Cross Section parameter──FITLINK[J];核动力工程;1995-03
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