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反应性温度系数的计算方法
引用本文:钟文发,胡永明. 反应性温度系数的计算方法[J]. 清华大学学报(自然科学版), 1997, 0(5)
作者姓名:钟文发  胡永明
作者单位:清华大学核能技术设计研究院
基金项目:国家“八五”科技攻关项目
摘    要:
为了精确地计算反应性温度系数,采用动态规划的方法,求出了燃耗过程中控制棒的临界棒位。利用组件计算软件包TPFAP,计算慢化剂(或燃料)在不同温度下组件的宏观截面。用节块格林函数法,求解三维中子扩散方程,求得慢化剂(或燃料)反应性温度系数。对于200MW核供热堆在临界棒位下,作了三维反应性温度系数的计算,并与二维计算结果作了比较。结果表明,慢化剂温度系数的大小和控制棒插入有密切关系。二维无控制棒时计算的反应性温度系数比较接近三维带控制棒的计算结果,并且二维无控制棒的计算结果是一个保守的估值。

关 键 词:温度系数;控制棒;供热堆

Method for calculating the reactivity temperature coefficient
Zhong Wenfa,Hu Yongming Institute of Nuclear Energy Technology,Tsinghua University,Beijing. Method for calculating the reactivity temperature coefficient[J]. Journal of Tsinghua University(Science and Technology), 1997, 0(5)
Authors:Zhong Wenfa  Hu Yongming Institute of Nuclear Energy Technology  Tsinghua University  Beijing
Affiliation:Zhong Wenfa,Hu Yongming Institute of Nuclear Energy Technology,Tsinghua University,Beijing 100084
Abstract:
The critical rod position during burnup is calculated with dynamic programming, and the sections of assemblies with different moderator (and fuel) temperature are calculated by the assembly calculation software TPFAP, and the 3 dimensional neutron diffusion equation is calculated with nodal Green function method to gain the reactivity temperature coefficient for calculating the reactivity temperature coefficient exactly. The 3 dimensional reactivity temperature coefficient with critical rod position are calculated by this code for 200 MW nuclear heating reactor (NHR). The results show that the reactivity temperature coefficient calculated by 2 dimensional code without control rods is close to those calculated by 3 dimensional code with control rods, and the results calculated by 2 dimensional code without control rods are conservative approximations.
Keywords:temperature coefficient  control rod  nuclear heating reactors
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