基于中子等效均匀扩散理论的反应堆建模仿真研究

系统仿真学报 ›› 2016, Vol. 28 ›› Issue (7): 1593-1600.

基于中子等效均匀扩散理论的反应堆建模仿真研究

马进, 刘志宾, 王兵树, 段新会

华北电力大学自动化系,北京 102206

收稿日期:2015-01-22 修回日期:2015-04-14 出版日期:2016-07-08 发布日期:2020-06-04
作者简介:Biography: Ma Jin (1971-), Male, Hebei, China, PHD, associate professor, nuclear simulation; Liu Zhibin (1980-), male, Shijiazhuang, China, PHD, Engineer, nuclear reactor simulation; Wang Bingshu(1950-), male, Shijiazhuang, China, graduate, professor, electric simulation.

Research on Reactor Modeling Simulation Based on Neutron Equivalence Homogeneous Theory

Ma Jin, Liu Zhibin, Wang Bingshu, Duan Xinhui

Department of Automation North China Electric Power University, Beijing 102206, China

Received:2015-01-22 Revised:2015-04-14 Online:2016-07-08 Published:2020-06-04

摘要/Abstract

摘要： 建立了稳态的和动态的CANDU核反应堆轴向功率分布模型。通过研究中子扩散和输运方程：以有限的粗网节点为模型,基于两群中子扩散方程和空间离散化,一般等效均匀化方法;通过定义核反应堆参数(吸收和裂变截面,扩散系数等)建立了CANDU核反应堆热功率分布模型。仿真得到390个燃料通道的轴向热功率。搭建以LINUX环境,通过与实际运行数据比对进行验证,其与实际反应堆数据误差在5%以内。所建模型及仿真结果解决了传统体积权重方法和有限差分方法的计算误差偏大、计算过程冗长及参数计算不准确等问题,对于核反应堆燃耗管理软件的研究和优化有重要的参考价值。

关键词: CANDU堆, 等效理论, 均匀化参数, 核反应堆, 建模仿真

Abstract: A mathematical nuclear CANada Deuterium Uranium (CANDU) reactor steady and transient modelling simulation is built to get the axial thermal power distribution. With a relatively small number of nodes (100-500 nodes) to present the core, based upon two energy group Neutron Diffusion Formulation and a typical spatial discretization, according to equivalence theory and homogeneous method, this is accomplished by properly defining the nuclear properties (absorption and fission cross sections, diffusion coefficient, etc.) characterizing each of the nodes finished. The 390 channels thermal power distribution is calculated under Linux language environment. The thermal power difference is within 5% error with IAEA database. The proposed modeling simulation can solve the large error and big redundant in comparison with the Flux-Volume-Weighted (FVW) method and Finite Difference Method (FDM), there is an important meaning for nuclear reactor fuel management research and optimization.

Key words: canada deuterium uranium (CANDU), equivalence theory, homogeneous parameters, nuclear reactor power, modelling

中图分类号:

TP391.9

马进, 刘志宾, 王兵树, 段新会. 基于中子等效均匀扩散理论的反应堆建模仿真研究[J]. 系统仿真学报, 2016, 28(7): 1593-1600.

Ma Jin, Liu Zhibin, Wang Bingshu, Duan Xinhui. Research on Reactor Modeling Simulation Based on Neutron Equivalence Homogeneous Theory[J]. Journal of System Simulation, 2016, 28(7): 1593-1600.

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