Published October 2017 | Version v1
Journal article

Analysis of physical and thermal characteristics of damaged fuel assemblies after repairment

  • 1. Nuclear Safety Technology Center, Suzhou Nuclear Power Research Institute, Suzhou (China)

Description

This report takes CPR1000 unit with AFA3G fuel assembly as the research object, and analyzes the physical characteristics and power distribution of normal fuel assembly and damaged fuel assembly after repairment. It can be found that the effect on the fuel assembly reactivity is about -0.03% for the fuel assembly replaced with a stainless steel rod, and the effect can be ignored. The relative power of fuel rods near the stainless steel rod increases about 5.6%. The stainless steel rod replaced in the fuel assembly has effect on the relative power of fuel assembly about 0.1372% to 0.2698%, on burnup about 0.11%, core moderator temperature coefficient about 2%, and these effects can be ignored. The stainless steel rod replaced in the fuel assembly has no effect on the reactor core power peak factor, core critical boron concentration, core shutdown margin, fuel assembly outlet moderator temperature and core outlet coolant temperature. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
38
Journal Issue
5
Journal Page Range
p. 119-122
ISSN
0258-0926

Optional Information

Notes
9 figs., 3 tabs., 4 refs.