Calculation of the reactor neutron time of flight spectrum by convolution technique  

作　　者：程金星 欧阳晓平 郑毅 张安慧 欧阳茂解 

机构地区：[1]Research Institute of Chemical Defence [2]Northwest Institute of Nuclear Technology [3]Academe of Chemical Defence

出　　处：《Chinese Physics B》2008年第8期2881-2884,共4页中国物理B（英文版）

摘　　要：It is a very complex and time-consuming process to simulate the nuclear reactor neutron spectrum from the reactor core to the export channel by applying a Monte Carlo program. This paper presents a new method to calculate the neutron spectrum by using the convolution technique which considers the channel transportation as a linear system and the transportation scattering as the response function. It also applies Monte Carlo Neutron and Photon Transport Code （MCNP） to simulate the response function numerically. With the application of convolution technique to calculate the spectrum distribution from the core to the channel, the process is then much more convenient only with the simple numerical integral numeration. This saves computer time and reduces some trouble in re-writing of the MCNP program.It is a very complex and time-consuming process to simulate the nuclear reactor neutron spectrum from the reactor core to the export channel by applying a Monte Carlo program. This paper presents a new method to calculate the neutron spectrum by using the convolution technique which considers the channel transportation as a linear system and the transportation scattering as the response function. It also applies Monte Carlo Neutron and Photon Transport Code （MCNP） to simulate the response function numerically. With the application of convolution technique to calculate the spectrum distribution from the core to the channel, the process is then much more convenient only with the simple numerical integral numeration. This saves computer time and reduces some trouble in re-writing of the MCNP program.

关 键 词：convolution technique neutron transportation time of flight response function time spectrum 

分 类 号：TL32[核科学技术—核技术及应用]