用于硼中子俘获治疗的医院中子照射器的反应堆光致缓发中子参数

Delayed Gamma-induced Neutron Parameters on Reactor of In-hospital Neutron Irradiator for Boron Neutron Capture Therapy

在介绍单群扩散方程基础上,引入堆芯和反射层的中子价值,根据考虑了光致缓发中子及其价值因素的点堆动态方程,建立了利用现有计算程序进行计算和分析的方法,分析了医院中子照射器光致缓发中子的特性参数,在原有6组缓发中子基础上增加了9组光致缓发中子,为进一步进行用于硼中子俘获治疗的医院中子照射器反应堆的点堆动力学研究提供了重要参数。

In order to analyze the influence on dynamics characteristics from delayed gamma-induced neutron for nuclear reactor of in-hospital neutron irradiator, which used to cure cancer with technology of boron neutron capture therapy （BNCT）, the dynamics equation of point-reactor included the quantity, worth and decay constant of gammainduced neutron was set by introducing neutron worth in reactor core and reflector in the one group diffusion equation. The calculation methods on generation rate of delayed gamma-induced neutron, the worth of neutrons generated from fission reaction or gamma-induced were also introduced. The total numerical calculation methods were studied with help of current calculation software and its sketch was shown. The mentioned parameters were calculated and analyzed for the nuclear reactor of in-hospital neutron irradiator. As a result, parameters of 9 groups delayed neutron were added to normal 6 groups. The tendency was analyzed and the good coincidence was verified with experiments from other research reactors which consist of beryllium in reactor complex.