논문 상세보기
State-of-Arts of Primary Concrete Degradation Behaviors due to High Temperature and Radiation in Spent Fuel Dry Storage KCI 등재 SCOPUS
사용후핵연료 건식저장 콘크리트의 고열과 방사선으로 인한 주요 열화거동 분석
- 언어KOR
- URLhttps://db.koreascholar.com/Article/Detail/352604
pp.243-260
A literature review on the effects of high temperature and radiation on radiation shielding concrete in Spent Fuel Dry Storage is presented in this study with a focus on concrete degradation. The general threshold is 95℃ for preventing long-term degradation from high temperature, and it is suggested that the temperature gradient should be less than 60℃ to avoid crack generation in concrete structures. The amount of damage depends on the characteristics of the concrete mixture, and increases with the temperature and exposure time. The tensile strength of concrete is more susceptible than the compressive strength to degradation due to high temperature. Nuclear heating from radiation can be neglected under an incident energy flux density of 1010 MeV·cm-2·s-1. Neutron radiation of >1019 n·cm-2 or an integrated dose of gamma radiation exceeding 1010 rads can cause a reduction in the compressive and tensile strengths and the elastic moduli. When concrete is highly irradiated, changes in the mechanical properties are primarily caused by variation in water content resulting from high temperature, volume expansion, and crack generation. It is necessary to fully utilize previous research for effective technology development and licensing of a Korean dry storage system. This study can serve as important baseline data for developing domestic technology with regard to concrete casks of an SF (Spent Fuel) dry storage system.
2. 방사선과 콘크리트의 상호작용
2.1 방사화에 의한 열발생
2.2 콘크리트 내 함수량
3. 온도상승으로 인한 콘크리트 열화
3.1 역학적 물성변화
3.2 물리적 물성변화
4. 방사화에 의한 콘크리트 물성변화
4.1 골재 및 시멘트 페이스트
4.2 역학적 물성변화
4.3 물리적 물성변화
5. 분석 및 토의
5.1 캐스크 온도기준
5.2 캐스크 방사선기준
5.3 차폐체 콘크리트 배합
6. 결론
REFERENCES
