
doi: 10.2172/10145870
A survey of the PITA-18 nonpoisonous spline program was conducted in conjunction with a study to determine the best method of eliminating the variability of axial flux on the fuel performance parameter, q. The results of this survey and the conclusions reached in the rupture coefficient study were found to be inter-dependent such that both are presented in this report. The data from the PITA-18 nonpoisonous spline program, as received, is the output of the NOLA-2 computer program. One quantity of interest is the rupture potential relative to a cosine, commonly referred to as the relative rupture potential. As programmed, the relative rupture potential, which was derived by applying the rupture model to individual fuel elements, might be expected to vary linearly with the rupture rate. The use of the relative rupture potential was studied over the period of July 1962 through December 1963. The results of this study are presented.
22 General Studies Of Nuclear Reactors, 570, Test, Neutron Flux, Research, Hanford Production Reactors, Production, 530, Computer Calculations 220600, Training, Irradiation, Ruptures, Fuel Elements, Materials Testing Reactors
22 General Studies Of Nuclear Reactors, 570, Test, Neutron Flux, Research, Hanford Production Reactors, Production, 530, Computer Calculations 220600, Training, Irradiation, Ruptures, Fuel Elements, Materials Testing Reactors
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