Home / Publications / Journals / Nuclear Technology / Volume 11 / Number 4
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 521-525
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30848
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A computer program with a combined analytical-numerical technique was developed to evaluate the distribution of cladding failure along and across a rod bundle or subassembly. The program, based on the statistical interpretation of experimental data, accounts for the spatial variations in the cladding and the fuel parameter that influence the ultimate site of cladding failure.