利用不可分辨区共振参数计算中子微观截面

CALCULATION OF NEUTRON MICRO CROSS SECTIONS USING UNSOLVED RESONANCE PARAMETERS

摘要: <正> 一、中子截面计算公式为了利用ENDF/B库所给出的不可分辨区的共振参数计算中子散射截面、俘获截面和裂变截面,同时,对于不同分摊慢化截面与不同温度作Doppler展宽,以适应实验数据处理、产生群截面的要求。为此,对考虑与不考虑Doppler展宽两种情况,中子截面具体的计算公式分别叙述如下:

Abstract: A method which calculates neutron scattering, capture and fission crosssection using unsolved resonance parameters in ENDF/B library is given. TheDoppler broadening is considered. The calculations are carried out for ~(235)U,~(238)U and ~(239)Pu in different temperatures and different scattering cross sections.The results are satisfactory.