| 학회 |
한국재료학회 |
| 학술대회 |
2009년 가을 (11/05 ~ 11/06, 포항공과대학교) |
| 권호 |
15권 2호 |
| 발표분야 |
C. Energy and the Environment(에너지 및 환경재료) |
| 제목 |
고온산화 피복관 및 조사피복관의 후프방향 압축특성 |
| 초록 |
To evaluate the degradation of the ductility of nuclear fuel cladding tubes under LOCA condition, the ring compression tests which can simulate the degradation of ductility are performed. In this paper, high temperature oxidized fuel cladding and spent fuel cladding under a compressive loading condition were employed. First of all, the as-received cladding specimens with 8 mm length are oxidized with TGA in air environment at 1200℃ to prepare specimens with various ECR (Equivalent Cladding Reacted). ECR is controlled to have a value of 0%, 5%, 10%, 15%, 20%, including ECR value higher than current LOCA maximum oxidation. For the spent fuel cladding specimens are from Ulchin Unit 2 Zircaloy-4 cladding with ~ 60 GWd/tU. The specimen with a length of 8 mm is located groove on jig plate, and then compressive load is exerted to the specimen with UTM installed in a hot cell. The experiments were carried out at 25℃ and 135℃. In this paper, ductility losses of oxidized cladding and spent fuel cladding are presented, and also oxidation degree and hydrogen content were investigated by ECR evaluation and hydrogen pick-up. |
| 저자 |
김선기, 방제건, 김대호, 임익성, 양용식, 송근우
|
| 소속 |
한국원자력(연) |
| 키워드 |
후프방향 압축특성; 핵연료 피복관; 링압축실험
|
| E-Mail |
|
