Published September 2016 | Version v1
Journal article

Measurement of neutron flux density in reactor with thermal analysis method

  • 1. Department of Statistics and Applied Science, Xijing University, Xi'an (China)
  • 2. Department of Reactor Engineering Research and Design, China Institute of Atomic Energy, Beijing (China)
  • 3. School of Ethic Education, Shanxi Normal University, Xi'an (China)

Description

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. (authors)

Additional details

Identifiers

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
50
Journal Issue
9
Journal Page Range
p. 1629-1633
ISSN
1000-6931

Optional Information

Notes
2 figs., 1 tab., 12 refs.; http://dx.doi.org/10.7538/yzk.2016.50.09.1629