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.
Received: 25 June 2007
Revised: 05 November 2007
Published: 20 August 2008
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
