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
- 학술대회자료
- 저자정보
- 발행연도
- 2008.11
- 수록면
- 239 - 244 (6page)
이용수
초록· 키워드
오류제보하기
In Korea, MR(Maintenance Rule) programs development for all PWR were completed. However, in case of PHWR (CANDU type, Wolsong Unit 1&2,3,4), the study of MR program was delayed, since the design concepts and operating experiences are different from those of PWR. Additionally, in Canada that designed the CANDU reactor originally, the MR program has not been tried even though the similar programs such as the Reliability Program and Maintenance Program exist. In 2007， KEPRI started a project for developing similar MR program for the domestic PHWR considering the unique design characteristics and operating experience of Wolsong Unit 1,2,3 & 4.This paper describes the characteristics of CANDU design experienced during the function analysis in scoping process that is the first step in MR program development, and the results of scoping process, ^ince the design features of CANDU is different from those of PWR (for example, using D20 as a coolant and moderator, the pressure tube and Calandria, and the fuel changing machine, etc.), the applicability of NUMARC 93-01 Criteria to CANDU had to be investigated and justified in this paper. Next step, the risk importance determination process for functions in scope will be described. The risk importance was determined by mapping important PSA basic event to function in scope and Delphi method. For Delphi evaluation, Delphi evaluation item for CANDU need to be developed because the design and normal operation functions are different from PWR.
The final review for risk importance determination was performed by Expert Panel organized by the plant expert engineers of Wolsong Unit 3&4. In this paper, the discussion results are also described, so it will be a great help to understand the functional characteristics ana identity the important function of CANDU plant
The final review for risk importance determination was performed by Expert Panel organized by the plant expert engineers of Wolsong Unit 3&4. In this paper, the discussion results are also described, so it will be a great help to understand the functional characteristics ana identity the important function of CANDU plant
목차
Abstract
1. 서론
2. 감시대상 기능선정
3. 중요도 평가
4. 결론
후기
참고문헌
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
CANDU-3 설계
원자력산업
1991 .01
-
CANDU형 원전 계속운전 평가지침서 개발
대한기계학회 춘추학술대회
2009 .04
-
CANDU 압력관에 대한 건전성 평가 시스템 개발 ( Development of Integrity Evaluation System for CANDU Pressure Tube )
대한기계학회 춘추학술대회
2000 .01
-
CANDU 압력관의 건전성 평가 ( Evaluation of CANDU Pressure Tube Integrity )
대한기계학회지
1993 .05
-
CANDU Energy System Design and Safety - a Status Review
에너지공학
1993 .09
-
CANDU 압력관 건전성평가를 위한 결함해석 ( Defect Assessment for Integrity Evaluation of CANDU Pressure Tubes )
대한기계학회 논문집
1995 .03
-
Experiences on the Expansion of Spent Fuel Storage Capacity at PWR and CANDU plants in Korea
한국방사성폐기물학회 학술대회
2007 .01
-
CANDU형 원전 압력관에 존재하는 균열의 건전성 평가
대한기계학회 춘추학술대회
2011 .04
-
CANDU 압력관 확률론적 결함평가 프로그램 개발
대한기계학회 춘추학술대회
2011 .04
-
CANDU형 원전 계속운전 평가지침서 개발
대한기계학회 논문집 A권
2010 .04
-
CANDU 발전소의 핵연료 압력관 검사
비파괴검사학회지
1986 .11
-
CANDU 원자로용 다영역 핵연료모델 ( Multi Zone Fuel Model for CANDU Reactor )
한국에너지학회 학술발표회
1993 .11
-
중수로 원전 유량정체 사고 시 핵연료 피복관 온도거동 해석
대한기계학회 춘추학술대회
2014 .11
-
PWR과 CANDU형 발전소의 계통화학 및 파손평가 연구
원자력산업
1983 .01
-
일본의 CANDU로=도입을 위한 기술검토=WORKING GROUP
원자력
1979 .01
-
CANDU 시뮬레이션을 위한 증기발생기 모델링 ( Steam Generator Modeling for CANDU Transients Simulation )
한국에너지학회 학술발표회
1994 .05
-
CANDU용 변환우라늄 연료 사용 사례 및 적용성 연구
한국에너지학회 학술발표회
2013 .11
-
CANDU 핵연료 채널에 대한 동특성 및 결함증상 해석
한국소음진동공학회 학술대회논문집
2003 .11
-
CANDU 원자로에서의 Co-60 생산
원자력산업
2002 .01
이 논문의 저자 정보
최근 본 자료
댓글(0)
0
UCI(KEPA) : I410-ECN-0101-2013-550-000668197