Nuclear Engineering and Technology
- 제26권4호
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- Pages.526-535
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- 1994
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- 1738-5733(pISSN)
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- 2234-358X(eISSN)
KMRR 핵연료 알루미늄 피복재의 부식 거동 평가
Evaluation of the Corrosion Behavior of the Aluminum Cladding in the KMRR Fuel
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Lee, Chan-Bock
(Korea Atomic Energy Research Institute) ;
- Sohn, Dong-Seong (Korea Atomic Energy Research Institute)
- 발행 : 1994.12.01
초록
KMRR(다목적 연구용원자로) 핵연료의 알루미늄 피복재의 부식거동을 평가하기 위해, 부식 예측치와 노내 부식 실측치의 비교를 통해 유도된 열속인자를 도입한 수정된 Griess 경험식을 유도하였다. KMRR 핵연료의 건전성이 유지되는 부식의 설계기준으로써는 산화층의 박리 방지가 보수적으로 설정되었으며, 산화층의 박리는 산화층에서의 온도차이가 114
For the evaluation of the corrosion behavior of the aluminum cladding in the KMRR(Korea Multipurpose Research Reactor) fuel, a modified Griess correlation was derived by introducing a heat flux factor derived from the comparison of the measured in-reactor corrosion data with the prediction of the Griess correlation. As a design criterion on the corrosion to maintain the KMRR fuel integrity, prevention of the oxide spallation was conservatively selected, which is conservatively assumed to occur when the temperature difference across the oxide layer exceeds 114
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