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;

D O I：

暂无

中图分类号：

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.

引用

页码：481 / 484

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