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DOE OSTI · 1907631

Graphite Degradation Modeling and Analysis

Bass, Joseph Louis
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Abstract

A graphite component in a nuclear reactor core is subjected to variety of stresses and can experience degradation during normal and off-normal operation. Understanding how a graphite component will behave in service is essential to ensuring core structural stability and safe reactor operation. This report summarizes a graphite modeling tool currently under development at Idaho National Laboratory. The model incorporates several of the anticipated stresses during service and includes the effects of oxidation and irradiation prior to turnaround. This tool is intended to be used to help assess the design of graphite components by utilizing design code rules found in Section III, Division 5 of the American Society of Mechanical Engineering Boiler and Pressure Vessel Code. Specifically, the tool uses the methodologies found within the Full and Simplified assessments from Article HHA-3000 to verify that a graphite component has an acceptably low probability of failure.

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36 MATERIALS SCIENCE42 ENGINEERINGASME AssessmentGraphiteGraphite modelingGraphite oxidation

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Bass, Joseph Louis. 2022-08-04. Graphite Degradation Modeling and Analysis. https://www.osti.gov/biblio/1907631

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