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反应堆中子通量密度仿真研究 被引量:1

Simulation Research of Reactor Neutron Flux Density
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摘要 核电厂作为特殊企业,对职工的培训尤为重要,而培训中,仿真系统是必不可少的环节。如果用经典的点堆模型方程,仿真精度不够,不能实现物理仿真。本文利用因子分解方法解中子通量密度函数,在求解中子通量密度形状函数时,通过适当的模型简化,使其可以在一般的PC机上实现。模型采用三维直角坐标系,并引入两根可以随时上下移动的控制棒,实现对中子通量密度分布的瞬态分析。在进行数字仿真时,采用定步长四阶龙格_库塔(RungeKuta)法。用该方法对压水堆中子通量密度进行求解,取得了令人满意的结果,并已在核电厂仿真中得到应用。 As a special enterprise,nuclear power plant takes staff training as a very important aspect.Generally,point reactor model is used to simulate the system.But the precision is not satisfied.In the present paper,point reactor kinetic equation is adopted to substitute neutron flux density size function.Neutron flux density function factor resolution method is used to solve neutron diffusion equation in this paper.In order to realize it in a personal computer,neutron flux density shape function is simplified.A three dimensional rectangular coordinate system is used in present model and there are two control rods which can be moved up and down at any time.We can achieve transient analysis of neutron flux density through moving control rods and with Runge Kutta as a digital simulation method.The result is satisfied and this method has been applied in nuclear power plant simulation system.
作者 邓亮 邓琛
出处 《核动力工程》 EI CAS CSCD 北大核心 1999年第3期209-213,共5页 Nuclear Power Engineering
关键词 反应堆 中子通量密度 数字仿真 核电厂 Reactor Neutron flux density Digital simulation
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参考文献4

  • 1卡尔O奥特 等 郑福裕等(译).核反应堆动力学导论[M].北京:原子能出版社,1992.30.
  • 2谢仲生,核反应堆物理分析,1994年,23-26,325-328页
  • 3郑福裕(译),核反应堆动力学导论,1992年,298页
  • 4郑福裕(译),核反应堆动力学导论,1992年,30页

同被引文献2

  • 1The RELAP5 Code Development Team.RELAP5/MOD3 Code Manual[M].USA:Idaho National Engineering Laborary,1995.
  • 2AER benchmark Specification Sheet,AER-DYN-002,http://aerbench.kfki.hu/aerbench/Dyn002.doc

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