RISS 학술연구정보서비스

검색
다국어 입력

http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.

변환된 중국어를 복사하여 사용하시면 됩니다.

예시)
  • 中文 을 입력하시려면 zhongwen을 입력하시고 space를누르시면됩니다.
  • 北京 을 입력하시려면 beijing을 입력하시고 space를 누르시면 됩니다.
닫기
    인기검색어 순위 펼치기

    RISS 인기검색어

      KCI등재

      Preliminary PINC(Program for the Inspection of Nickel Alloy Components) RRT(Round Robin Test) - Pressurizer Dissimilar Metal Weld -

      한글로보기

      https://www.riss.kr/link?id=A104910054

      • 0

        상세조회
      • 0

        다운로드
      서지정보 열기
      • 내보내기
      • 내책장담기
      • 공유하기
      • 오류접수

      부가정보

      다국어 초록 (Multilingual Abstract) kakao i 다국어 번역

      After several damages by PWSCC were found in the world, USNRC and PNNL(Pacific Northwest National Laboratory) started the research on PWSCC under the project name of PINC. The aim of the project was 1) to fabricate representative NDE mock-ups with flaws to simulate PWSCCs, 2) to identify and quantitatively assess NDE methods for accurately detecting, sizing and characterizing PWSCCs, 3) to document the range of locations and morphologies of PWSCCs and 4) to incorporate results with other results of ongoing PWSCC research programs, as appropriate. Korea nuclear industries have also been participating in the project. Thermally and mechanically cracked-four mockups were prepared and phased array and manual ultrasonic testing(UT) techniques were applied. The results and lessons learned from the preliminary RRT are summarized as follows: 1) Korea RRT teams performed the RRT successfully. 2) Crack detection probability of the participating organizations was an average 87%, 80% and 80% respectively. 3) RMS error of the crack sizing showed comparatively good results. 4) The lessons learned may be helpful to perform the PINC RRT and PSI /ISI in Korea in the future.
      번역하기

      After several damages by PWSCC were found in the world, USNRC and PNNL(Pacific Northwest National Laboratory) started the research on PWSCC under the project name of PINC. The aim of the project was 1) to fabricate representative NDE mock-ups with fla...

      After several damages by PWSCC were found in the world, USNRC and PNNL(Pacific Northwest National Laboratory) started the research on PWSCC under the project name of PINC. The aim of the project was 1) to fabricate representative NDE mock-ups with flaws to simulate PWSCCs, 2) to identify and quantitatively assess NDE methods for accurately detecting, sizing and characterizing PWSCCs, 3) to document the range of locations and morphologies of PWSCCs and 4) to incorporate results with other results of ongoing PWSCC research programs, as appropriate. Korea nuclear industries have also been participating in the project. Thermally and mechanically cracked-four mockups were prepared and phased array and manual ultrasonic testing(UT) techniques were applied. The results and lessons learned from the preliminary RRT are summarized as follows: 1) Korea RRT teams performed the RRT successfully. 2) Crack detection probability of the participating organizations was an average 87%, 80% and 80% respectively. 3) RMS error of the crack sizing showed comparatively good results. 4) The lessons learned may be helpful to perform the PINC RRT and PSI /ISI in Korea in the future.

      더보기

      참고문헌 (Reference)

      1 Jenssen, A., "Structural Assessment of Defected Nozzle to Safe-End Welds in Ringhals 3 and 4" SFEN 43-54, 2002

      2 Amzallag, C., "Stress Corrosion Life Experience of 182 and 82 Welds in French PWRs" 2002

      3 Buisine, D., "Stress Corrosion Cracking in the Vessel Closure Head Penetrations of French PWRs" 1993

      4 "Reactor Coolant System Weld Issues"

      5 Thomas, L. E., "High-Resolution Analytical Electron Microscopy Characterization of Environmentally Assiasted Cracks in Alloy 182 Weldments" ANS 2003

      6 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, "Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle" 2006

      7 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, "Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. SUMMER" 2000

      8 Shah, V. N., "Assessment of Pressurized Water Reactor Control Rod Drive Mechanism Nozzle Cracking, prepared for U.S" Nuclear Regulatory Commission, Safety Programs Division 1994

      9 Bamford, W., "A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends" 2003

      1 Jenssen, A., "Structural Assessment of Defected Nozzle to Safe-End Welds in Ringhals 3 and 4" SFEN 43-54, 2002

      2 Amzallag, C., "Stress Corrosion Life Experience of 182 and 82 Welds in French PWRs" 2002

      3 Buisine, D., "Stress Corrosion Cracking in the Vessel Closure Head Penetrations of French PWRs" 1993

      4 "Reactor Coolant System Weld Issues"

      5 Thomas, L. E., "High-Resolution Analytical Electron Microscopy Characterization of Environmentally Assiasted Cracks in Alloy 182 Weldments" ANS 2003

      6 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, "Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle" 2006

      7 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, "Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. SUMMER" 2000

      8 Shah, V. N., "Assessment of Pressurized Water Reactor Control Rod Drive Mechanism Nozzle Cracking, prepared for U.S" Nuclear Regulatory Commission, Safety Programs Division 1994

      9 Bamford, W., "A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends" 2003

      더보기

      동일학술지(권/호) 다른 논문

      동일학술지 더보기

      더보기

      분석정보

      View

      상세정보조회

      0

      Usage

      원문다운로드

      0

      대출신청

      0

      복사신청

      0

      EDDS신청

      0

      동일 주제 내 활용도 TOP

      더보기

      주제

      연도별 연구동향

      연도별 활용동향

      연관논문

      연구자 네트워크맵

      공동연구자 (7)

      유사연구자 (20) 활용도상위20명

      인용정보 인용지수 설명보기

      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2026 평가예정 재인증평가 신청대상 (재인증)
      2020-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2017-01-01 평가 등재학술지 유지 (계속평가) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2008-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2003-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2002-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2001-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      더보기

      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.36 0.36 0.27
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.21 0.19 0.467 0.14
      더보기

      이 자료와 함께 이용한 RISS 자료

      나만을 위한 추천자료

      해외이동버튼