Korean Journal of Materials Research (한국재료학회지)

Materials Research Society of Korea (한국재료학회)
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Analysis of Irradiation Growth Behavior for the Zircaloy-4 Cladding used in the KOFA Fuel

국산 핵연료에 사용되는 Zircaloy-4 피복관의 조사성장 거동 해석

  • Published : 1994.05.01
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Abstract

The irradiation growth of the Zircaloy-4 cladding in the KOFA fuel loaded in the Kori-2 nuclear plant was measured to evaluate the irradiation growth behavior and to be compared with that of the Siemens cladding having different manufacturing process. Due to the partial recrystallization by final heat treatment, the KOFA Zircaloy-4 cladding showed a two step irradiation growth behavior such as the growth saturation and the accerlation which is typical of the fully annealed Zircaloy cladding. The difference in the measured irradiation growth rate between the KOFA and the Siemens cladding could be explained by the difference in the cladding texture which depends on the manufacturing process. From the measured irradiation growth data of Kori-2 KOFA fuel, a two-step irradiation growth model of the KOFA Zircaloy-4 cladding was derived, the accuracy of which can be more clearly verified as the measured data of the irradiation growth are accumulated in the future.

국산 핵연료에 사용되는 KOFA Zircaloy-4피복관의 조사성장 거동을 평가하고 제조 공정이 서로 다른 Siemens사 피복관의 조사성장거동과 비교하기 위하여 고리 2호기에 장전된 핵연료 피복관의 조사성장이 측정되었다. KOFA Zircaloy-4피복관은 최종 열처리시의 부분 재결정화로 인하여 fully annealed Zircaloy피복관고 Siemens사 피복관의 측정된 조사성장율이 차이는 제조공정의 차이에 기인한 피복관 집합도 계수의 차이로서 설명할 수 있었다. 고리 2호기 국산핵연료에서 측정된 자료를 이용하여 KOFA Zircaloy-4 피복관의 2단계 조사성장 모델이 유도되었는데 향후 측정자료가 많이 축적되면 유도된 모델의 정확성이 보다 명확하게 검증될 수 있을 것이다.

Keywords

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