Post-LOCA ductility of Cr-coated cladding and its embrittlement limit
Source abstract
Abstract
Post-Loss of Coolant Accident (LOCA) ductility assessments of Cr-coated Zircaloy cladding was conducted in compliance with the United States Nuclear Regulatory Commission (U.S.NRC)’s guidelines. The Equivalent Cladding Reacted (ECR) limit for Cr-coated cladding oxidized on both sides, representing the embrittlement process of an outer-side coated cladding near the burst hole followed by ballooning, is found to be 13.8% at steam oxidation temperature of 1204°C. Ring Compression Test (RCT) induces peak tensile stress at the inner surface of the cladding specimen at which the crack starts to propagate from the brittle phases (ZrO2 and α(O)-Zr). Such characteristic of RCT is responsible for the decrease in the ECR limit for the claddings coated on the external surface as its oxygen-affected brittle phases are developed at the inner cladding surface. Outer-side Cr-coated cladding gives approximately 10 minutes of extra accident coping time at the fixed steam oxidation temperature 1204°C before it reaches the cladding embrittlement limit.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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