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. Measurement of Neutron Flux Density in Reactor with Thermal Analysis Method[J]. Atomic Energy Science and Technology, 2016, 50(9): 1629-1633. DOI: 10.7538/yzk.2016.50.09.1629
Citation: 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. Measurement of Neutron Flux Density in Reactor with Thermal Analysis Method[J]. Atomic Energy Science and Technology, 2016, 50(9): 1629-1633. DOI: 10.7538/yzk.2016.50.09.1629

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.
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