aResearch Institute of Chemical Defence, Beijing 102205, China; b Northwest Institute of Nuclear Technology, Xi'an 710024, China; cAcademe of Chemical Defence, Beijing 102205, 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.
Received: 25 June 2007
Revised: 05 November 2007
Accepted manuscript online:
Cheng Jin-Xing(程金星), Ouyang Xiao-Ping(欧阳晓平), Zheng Yi(郑毅), Zhang An-Hui(张安慧), and Ouyang Mao-Jie (欧阳茂解) Calculation of the reactor neutron time of flight spectrum by convolution technique 2008 Chin. Phys. B 17 2881
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