LOCA Burst Correlation

Published: 23 July 2026| Version 1 | DOI: 10.17632/smpfv3cdrc.1
Contributor:
Ralph Meyer

Description

Empirical correlations to be used in calculations of fuel behavior during loss-of-coolant accidents (LOCAs) in nuclear power plants. The correlations are equations that give fuel-rod cladding burst temperatures as a function of stress on the cladding, cladding heatup rate, and the cladding's hydrogen content. The stress values and heatup-rate values come from the analysts system code while the hyrogen content must be giiven to the analyst for the fuel-rod cladding under consideration.

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Nuclear Fuel

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