Published August 2014 | Version v1
Journal article

Study on measurement method of 235U isotope abundance of fuel assembly for research reactor based on a compact neutron generator

  • 1. Nuclear and Radiation Safety Center, MEP, Beijing (China)

Description

Neutron activation analysis and mass spectrometry are used as 235U isotope abundance of fuel assembly. Neutron activation analysis and mass spectrometry can't be used as an effective measurement means of the 235U Isotope Abundance of Fuel Assembly. Meanwhile they aren't also used as a verification mean of 235U isotopic abundance the fuel assembly management and transportation because of their shortcomings of large measurement equipment and sampling. So based on a compact neutron generator, a rapid and portable measurement method for 235U Isotope Abundance of Fuel Assembly is significant. According to the linear correlation relating the ratio of average yield for the specific fissile nuclides to 235U Isotope Abundance, the samples whose 235U Isotope Abundance is 10%-90% are successfully measured. It provides the experimental basis for the verification of 235U Isotope Abundance of the fuel assembly for the research reactor. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
35
Journal Issue
4
Journal Page Range
p. 10-12
ISSN
0258-0926

Optional Information

Notes
3 figs., 2 tabs., 6 refs.