지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.1
- 수록면
- 115 - 124 (10page)
이용수
초록· 키워드
오류제보하기
Among the several options to solve PWR spent fuel accumulation problem in Korea, the dry storage method could be the most realistic and applicable solution in the near future. As the basic objectives of dry storage are to prevent a gross rupture of spent fuel during operation and to keep its retrievability until transportation, at the same time the importance of a spent fuel integrity evaluation that can estimate its condition at the final stage of dry storage is very high. According to the national need and technology progress, two representative nations of spent fuel dry storage, the USA and Japan, have established different system temperature criteria, which is the only controllable factor in a dry storage system. However, there are no technical criteria for this evaluation in Korea yet, it is necessary to review the previously well-organized methodologies of advanced countries and to set up our own domestic evaluation direction due to the nation’s need for dry storage. To satisfy this necessity,building a domestic spent fuel test database should be the first step. Based on those data, it is highly recommended to compare domestic data range with foreign results, to build our own criteria, and to expand on evaluation work into recently issued integrity problems by using a comprehensive integrity evaluation code
목차
등록된 정보가 없습니다.
참고문헌 (31)
참고문헌 신청
[학
/ / Licensing requirements for the independent storage of spent nuclear fuel, high-level radioactive waste
A.B. Johnson / 1983 / Technical Basis for Storage of Zircaloy- Clad Spent Fuel in Inert Gases
B. A. Chin / 1986 / Deformation and Fracture Map Methodology for Predicting Cladding Behavior during Dry Storage
B. F. Kammenzind / 2000 / The Long-range migration of hydrogen through zircaloy in response to tensile and compressive stress gradients / Zirconium in the Nuclear Industry: Twelve
/ / Licensing requirements for the independent storage of spent nuclear fuel, high-level radioactive waste
A.B. Johnson / 1983 / Technical Basis for Storage of Zircaloy- Clad Spent Fuel in Inert Gases
B. A. Chin / 1986 / Deformation and Fracture Map Methodology for Predicting Cladding Behavior during Dry Storage
B. F. Kammenzind / 2000 / The Long-range migration of hydrogen through zircaloy in response to tensile and compressive stress gradients / Zirconium in the Nuclear Industry: Twelve
이 논문의 저자 정보
최근 본 자료
댓글(0)
0