Measurement of Neutron Flux Density in Reactor with Thermal Analysis Method

作者:YANG Tong suo; SHI Yong qian; ZHU Qing fu; YANG Wei ping; ZHANG Jian xiang; WANG Fan; WANG Tuan bu; LU Jin; LI Lai dong
来源:原子能科学技术, 2016, 50(9).
DOI:10.7538/yzk.2016.50.09.1629

摘要

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 .

  • 单位
    西京学院

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