Home / Publications / Journals / Nuclear Technology / Volume 46 / Number 2
Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 213-219
Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32319
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The results of power ramp tests and associated cladding failure calculations performed as part of FRAP-T4 independent assessment studies have been analyzed. The 90 ramp tests considered are characterized in terms of relevant fuel design and operating parameters for Zircaloy-clad UO2 fuel rods. The use of alternative gap closure and fuel deformation models strongly affects results of the current stress-dependent failure probability model. The influence of both mechanical and chemical failure mechanisms can be separated to some extent by interpreting the concurrent effects of both the ramp-induced stress levels and the relative amounts of retained fission gas available for promoting stress corrosion. A relatively simple modeling approach can meet the basic mechanistic requirements for calculating pellet-cladding interaction failure probability.