原子能科学技术2016，Vol.50Issue(9)：1629-1633,5.DOI:10.7538/yzk.2016.50.09.1629
利用测热技术测量核反应堆中子通量密度
Measurement of Neutron Flux Density in Reactor with Thermal Analysis Method
摘要
Abstract
One new neutron flux density detector was studied .Its principle was to mea‐sure 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 . T his 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 .关键词
中子探测器/退火热量/热中子通量密度Key words
neutron detector/annealing heat/themal neutron flux density分类
数理科学引用本文复制引用
杨铜锁,史永谦,朱庆福,杨维平,张建祥,王藩,王团部,鲁瑾,李来冬..利用测热技术测量核反应堆中子通量密度[J].原子能科学技术,2016,50(9):1629-1633,5.基金项目
国家自然科学基金资助项目 （）
