首页|Post-LOCA ductility of Cr-coated cladding and its embrittlement limit
Post-LOCA ductility of Cr-coated cladding and its embrittlement limit
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NSTL
Elsevier
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.
Yook H.、Lee Y.、Shirvan K.、Phillips B.
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Department of Nuclear Engineering Seoul National University
Department of Nuclear Science and Engineering Massachusetts Institute of Technology
NSTL
Elsevier
