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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2012.5
- 수록면
- 474 - 479 (6page)
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이 논문의 연구 히스토리 (14)
2014
2013
2012
2011
APR1400 원자로내부구조물 종합진동평가 응답측정시험 허용기준
고도영
,
김규형
,
김성환
한국소음진동공학회논문집
2011.11
학술저널
APR1400 원자로내부구조물 종합진동평가 응답측정시험 허용기준 수립
고도영
,
김규형
,
김성환
한국소음진동공학회 학술대회논문집
2011.10
학술대회자료
APR1400 원자로내부구조물 종합진동평가 측정위치 선정 기준
고도영
,
김규형
,
김성환
한국소음진동공학회논문집
2011.08
학술저널
APR1400 원자로내부구조물 종합진동평가 측정위치 선정기준 개발
고도영
,
김규형
,
김성환
한국소음진동공학회 학술대회논문집
2011.04
학술대회자료
APR1400 원자로 내부구조물 종합진동평가프로그램용 측정센서 검토
고도영
,
이재곤
한국소음진동공학회논문집
2011.01
학술저널
- 이 논문의 후속연구가 궁금하신가요?
- 연관 학술논문 또는 학술발표를 통해 보다 발전된 연구결과를 확인하실 수 있습니다.
- 이 논문의 연구 히스토리 확인하기
초록· 키워드
오류제보하기
A comprehensive vibration assessment program for the advanced power reactor 1400(APR1400) reactor vessel internals is established in accordance with the united states nuclear regulatory commission regulatory guide 1.20 revision 3. This paper is related to instruments and measurement locations based on the vibration and stress response analysis results of the inner barrel assembly top plate in APR1400. The analysis results of the inner barrel assembly top plate in the reactor show that the deterministic stress and deformation due to the reactor coolant pump induced pressure pulsations are larger than the random stress and deformation induced by the flow turbulence. The selection of the instruments and measurement locations at inner barrel assembly top plate in the reactor is essential requirements and very important study process for the vibration and stress measurement program in comprehensive vibration assessment program for APR1400 reactor vessel internals.
목차
등록된 정보가 없습니다.
참고문헌 (19)
참고문헌 신청
1. [기타자료] - US Nuclear Regulatory Commission / 2007 / Regulatory Guide 1.20, Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Testing, Rev. 3
2. [학술지(정기간행물)] - Ko, D. Y. / 2009 / Development of a Measurement System of Gap between CSB and RV to Shorten a Nuclear Reactor Installation Period / Nuclear Engineering and Design 239 (2009) : 495 ~ 500
3. [기타자료] - / 2000 / Report on the Observation and Synthesis about CVAP in KNGR RVI / Korea Electric Power Corp.
4. [기타자료] - / 2008 / Design Specification for Reactor Vessel Core Support and Internal Structures / KEPCO Engineering and Construction Company Inc.
5. [기타자료] - / 2008 / Fluid System and Component Engineering Design Data for Plant Safety, Containment and Performance Analyses / KEPCO Engineering and Construction Company Inc.
2. [학술지(정기간행물)] - Ko, D. Y. / 2009 / Development of a Measurement System of Gap between CSB and RV to Shorten a Nuclear Reactor Installation Period / Nuclear Engineering and Design 239 (2009) : 495 ~ 500
3. [기타자료] - / 2000 / Report on the Observation and Synthesis about CVAP in KNGR RVI / Korea Electric Power Corp.
4. [기타자료] - / 2008 / Design Specification for Reactor Vessel Core Support and Internal Structures / KEPCO Engineering and Construction Company Inc.
5. [기타자료] - / 2008 / Fluid System and Component Engineering Design Data for Plant Safety, Containment and Performance Analyses / KEPCO Engineering and Construction Company Inc.
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