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

• 来源期刊: 中国物理B(英文版)
• 关键词: convolution technique neutron transportation time of flight response function time spectrum
• 年，卷（期）: 2008,（8）
• 页码范围: 2881-2884
• 页数: 4页
• 语种: 英文

摘要

It is a very complex and tlme-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 thespectrum 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.