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

It is a very complex and time-consuming process to simulate thenuclear reactor neutron spectrum from the reactor core to the exportchannel by applying a Monte Carlo program. This paper presents a newmethod to calculate the neutron spectrum by using the convolutiontechnique which considers the channel transportation as a linearsystem 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 applicationof convolution technique to calculate the spectrum distribution fromthe core to the channel, the process is then much more convenient only withthe simple numerical integral numeration. This saves computer timeand reduces some trouble in re-writing of the MCNP program.