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Abstract

Described herein are methods for analyzing an operating envelope of a nuclear reactor. An example method includes obtaining operating envelope parameters associated with a first reactor core by performing a plurality of thermo-hydraulic and thermo-mechanical calculations for the first reactor core, where the first reactor core includes a first fuel-cladding material and has a first fuel pin geometry; obtaining operating envelope parameters associated with a second reactor core by performing a plurality of thermo-hydraulic and thermo-mechanical calculations for the second reactor core, where the second reactor core includes a second fuel-cladding material and has a second fuel pin geometry; and assessing an expandable operating envelope by comparing the respective operating envelope parameters associated with the first reactor core and the second reactor core, where the first and second fuel-cladding materials are different materials. The example method can include iteratively performing the steps described herein.

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First Claim