利用测热技术测量核反应堆中子通量密度

一种新型中子探测器被研究，其原理是利用带电离子在矿物中沉积的能量退火时会以热量的方式释放出来,通过测量释放的热量而确定中子通量密度。对新型中子探测器进行刻度，在反应堆内某位置测量的热中子通量密度为5.108×10¹¹ cm^-2?s^-1，与标定的热中子通量密度(5.000×10¹¹ cm^-2?s^-1)在2%内符合，说明该探测器可测量中子通量密度。本文方法制作的探测器体积小，可制作成不同形状，便于反应堆不同环境下的中子通量密度测量。选取相应中子能量反应截面较大的元素，该探测器还可测量不同中子能量的通量密度。

Measurement of Neutron Flux Density in Reactor with Thermal Analysis Method

One new neutron flux density detector was studied. Its principle was to measure annealing heat from mineral depositional energy to make sure neutron flux density. The new neutron detector was calibrated, the measuring neutron flux density of certain location in reactor was 5.108×10¹¹ cm^-2?s^-1, and the measuring value and calibrated neutron flux density (5.000×10¹¹ cm^-2?s^-1) were coincidence in the 2%. The results show that the new neutron detector can use to measure neutron flux density. This neutron detector has the advantages of small volume possession in nuclear reactor with required shape, and simplified multi-point measurement. The detector can measure different energy neutron flux densities if select element is sensitive for corresponding energy neutron.