Coupling of neutronics and thermal-hydraulic of CANDU fuel management program and modification of time-averaged model

被引：0
|
作者：
Huo, Xiao-Dong [1 ]
Xie, Zhong-Sheng [1 ]
机构：
[1] Xi'an Jiaotong Univ., Xi'an 710049, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2004年 / 25卷 / 06期
关键词：
Computer software - Heavy water reactors - Nuclear power plants - Pressurized water reactors;
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学科分类号：
摘要：
In this paper, a nonlinear iteration semi-analytic nodal method to solve the diffusion equation and a steady-state single channel thermal-hydraulic code are developed and integrated in the package FMPHWR to realize the coupling of neutronics and thermal-hydraulic. Based on the experiences from PWR, a similar cross-section parameterized method to be used in CANDU is proposed to consider the feedbacks of local parameters. A modified time-averaged model is proposed on the basis of the traditional one. The numerical results show that FMPHWR has superior computational accuracy.
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页码：481 / 484
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