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本文研究了一种堆芯中子通量測量数据的处理方法。依据两群中子扩散方程,采用低阶粗网格有限差分法,导出了一套由堆芯探测器活性测量数据計算堆芯功率分布的方法。快群通量节点值滿足标准的七点格式,由活性测量值作为非齐次源項,便于用迭代法或直接法求解。热群通量可根据快通量計算值及活性测量值經过簡单代数运算求出。整个計算程序很簡单,容易在反应堆堆芯通量测量系統中的小型数字,計算机上执行。本方法用零功率反应堆的測量数据作了检驗,結果是滿意的。
This paper studies a method of processing core neutron flux measurement data. Based on two groups of neutron diffusion equations, a low - order coarse grid finite difference method was used to derive a set of methods to calculate the core power distribution from the core detector activity measurement data. The fast group flux node value satisfies the standard seven-point format, and the active measurement value is used as the nonhomogeneous source term, so that it can be easily solved by the iterative method or the direct method. The heat flux can be calculated from the fast flux calculation and the activity measurement after a simple algebraic operation. The entire calculation procedure is simple and easy to implement on a small digital computer in a reactor core flow measurement system. The method was tested with zero-power reactor measurements and the results were satisfactory.