中国物理B ›› 2008, Vol. 17 ›› Issue (8): 2881-2884.doi: 10.1088/1674-1056/17/8/021
张安慧1, 欧阳晓平2, 郑 毅3, 欧阳茂解3, 程金星4
Cheng Jin-Xing(程金星)a)b)†, Ouyang Xiao-Ping(欧阳晓平)b), Zheng Yi(郑毅)a), Zhang An-Hui(张安慧)c), and Ouyang Mao-Jie (欧阳茂解)a)
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.
中图分类号: (Neutron transport: diffusion and moderation)