한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)
- 한국원자력학회 1999년도 춘계학술발표회요약집
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- Pages.279-279
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- 1999
Corrosion model for Zircaloy-4 Cladding in PWR
- Lee, Byung-Ho (Korea Atomic Energy Research Institute) ;
- Yoo, Yeon-Jong (Korea Atomic Energy Research Institute) ;
- Kook, Yang-Hyun (Korea Atomic Energy Research Institute) ;
- Sohn, Dong-Seong (Korea Atomic Energy Research Institute)
- 발행 : 1999.05.01
초록
To improve the corrosion model of the fuel performance analysis code COSMOS, a model was developed considering thermohydraulic phenomena and the effect of water chemistry and low Sn in the alloy composition on the corrosion behavior. It is assumed that the lithium enhancement factor influences the corrosion behavior only if the subcooled void is present in the coolant. The developed model was verified with the database obtained from Grohnde and Ringhals 3 reactors. Comparison of predicted oxide thickness with measured data showed the applicability of COSMOS code to analyze the cladding oxidation. In the future, the effect of the hydride in the cladding and the precipitate changes due to irradiation should be included.cluded.
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