中国物理B ›› 2008, Vol. 17 ›› Issue (8): 2881-2884.doi: 10.1088/1674-1056/17/8/021

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

张安慧1, 欧阳晓平2, 郑 毅3, 欧阳茂解3, 程金星4   

  1. (1)Academe of Chemical Defence, Beijing 102205,China; (2)Northwest Institute of Nuclear Technology, Xi'an 710024, China; (3)Research Institute of Chemical Defence, Beijing 102205, China; (4)Research Institute of Chemical Defence, Beijing 102205, China;Northwest Institute of Nuclear Technology, Xi'an 710024, China
  • 收稿日期:2007-06-25 修回日期:2007-11-05 出版日期:2008-08-20 发布日期:2008-08-20

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

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)   

  1. a Research Institute of Chemical Defence, Beijing 102205, China; b Northwest Institute of Nuclear Technology, Xi'an 710024, China; c Academe of Chemical Defence, Beijing 102205, China
  • Received:2007-06-25 Revised:2007-11-05 Online:2008-08-20 Published:2008-08-20

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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.

关键词: convolution technique, neutron transportation, time of flight, response function, time spectrum

Abstract: 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.

Key words: convolution technique, neutron transportation, time of flight, response function, time spectrum

中图分类号:  (Neutron transport: diffusion and moderation)

  • 28.20.Gd
29.25.Dz (Neutron sources)