Published December 2015 | Version v1
Journal article

Measurement methods study on determining the 235U abundance in the fuel elements by fast neutron induced fission

  • 1. Nuclear and Radiation Safety Center, MEP, Beijing (China)
  • 2. China Institute of Atomic Energy, Beijing (China)

Description

Determining the 235U abundance ratio of fuel pins is a significant stage among quality control in safe operations of reactor. 88Rb, 107Rh, 135I were choosed as analytic target. Relationship graphics of fission yield ration Y-bar88Rb/Y-bar107Rh, Y-bar88Rb/Y-bar135I VS 235U were polted. The simulated fuel element samples of different reactor were analyzed by working curve, and carried on theoretical analysis and experimental research on affection of measurement result by fuel element cladding. In order to testify the accuracy of the method, the simulation sample of 3.03% was measured 5 times respectively, relative standard deviation(RSD) of all tests was less than 5%. (authors)

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
35
Journal Issue
4
Journal Page Range
p. 705-710
ISSN
0258-0918

Optional Information

Notes
3 figs., 7 tabs., 10 refs.