摘要
为了确定岷江试验堆(简称MJTR)堆芯铍反射层内中子能量E >1.0MeV的快中子注量率,采用一组中子探测片测量了岷江试验堆内第一层铍反射层外Q15孔道内的快中子注量率谱,并由测量谱求得各阈能探测片的快中子反应的谱平均截面和该孔道测量点位置的快中子注量率。结果表明,铍反射层内快中子(E>1.0MeV)注量率为1.985×1012 cm-2·s-1,MJTR每运行一段,铍反射层内快中子(E>1.0MeV)积分注量最大可达1.54×1018cm-2。通过本次试验研究,为更好的开发利用MJTR提供了试验依据。
To confirm fast-neutron flux above 1.0 MeV in beryllium reflector of Minjiang Test Reactor (MJTR), a group of neutron dosimeters were used to measure fast-neutron flux spectra in Q15-tube outside of the first cycle beryllium reflector of MJTR. Spectral-averaged cross sections of fast-neutron reaction of threshold dosimeters and fast-neutron flux of the place of Q15-tube were obtained from the measured neutron spectra. The result of fast-neutron flux by measurement is 1.985×1012 cm-2·s-1. So the maximum fast-neutron fluence should be 1.54×1018 cm-2 in beryllium reflector per operation cycle of MJTR. Through this investigation, the experiment support is provided for the better utilization of MJTR.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2003年第4期395-397,400,共4页
Nuclear Power Engineering
