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Chin. Phys. B, 2008, Vol. 17(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

Zhang An-Huia, Ouyang Xiao-Pingb, Zheng Yic, Ouyang Mao-Jiec, Cheng Jin-Xingd
a Academe of Chemical Defence, Beijing 102205,China; b Northwest Institute of Nuclear Technology, Xi'an 710024, China; c Research Institute of Chemical Defence, Beijing 102205, China; d Research Institute of Chemical Defence, Beijing 102205, China;Northwest Institute of Nuclear Technology, Xi'an 710024, China
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.
Keywords:  time of flight      response function      time spectrum      convolution technique      neutron transportation  
Received:  25 June 2007      Revised:  05 November 2007      Published:  20 August 2008
PACS:  28.20.Gd (Neutron transport: diffusion and moderation)  
  29.25.Dz (Neutron sources)  

Cite this article: 

Cheng Jin-Xing, Ouyang Xiao-Ping, Zheng Yi, Zhang An-Hui, Ouyang Mao-Jie Calculation of the reactor neutron time of flight spectrum by convolution technique 2008 Chin. Phys. B 17 2881

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