CANDU堆燃料管理程序的物理热工水力耦合和时均计算模型的改进  

Coupling of Neutronics and Thermal-Hydraulic of CANDU Fuel Management Program and Modification of Time-averaged Model

作　　者：霍小东[1] 谢仲生[1] 

机构地区：[1]西安交通大学,710049

出　　处：《核动力工程》2004年第6期481-484,504,共5页Nuclear Power Engineering

摘　　要：研制了非线性迭代半解析节块法的扩散程序和稳态单通道热工水力程序,并将二者联接形成了CANDU重水堆燃料管理软件包FMPHWR,实现了物理与热工水力的耦合。参考压水堆(PWR)的经验,提出了类似PWR的考虑局部参数变化的参数化截面方法。对原有的时均计算模型进行了修正,提出了考虑热工水力反馈的时均计算模型。通过数值计算表明:FMPHWR具有更高的计算精度。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.

关 键 词：CANDU 截面参数化 物理与热工水力的耦合 时均模型 

分 类 号：TL329[核科学技术—核技术及应用]