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
- 2013.12
- 수록면
- 519 - 523 (5page)
이용수
초록· 키워드
오류제보하기
A steam generator (SG) tube is an important component of a nuclear power plant (NPP). It works as a pressure boundary between the primary and secondary systems. The integrity of a SG tube can be assessed by an eddy current test every outage. The eddy current technique(adopting a bobbin probe) is currently the main technique used to assess the integrity of the tubing of a steam generator. An eddy current signal analyst for steam generator tubes continuously analyzes data over a given period of time. However, there are possibilities that the analyst conducting the test may get tired and cause mistakes, such as: missing indications or not being able to separate a true defect signal from one that is more complicated. This error could lead to confusion and an improper interpretation of the signal analysis. In order to avoid these possibilities, many countries of opted for automated analyses. Axial ODSCC (outside diameter stress corrosion cracking) defects on the tubes of OPR1000 steam generators have been found on the tube that are in contract with tube support plates. In this study, automated analysis software called CDS (computer data screening) made by Zetec was used. This paper will discuss the results of introducing an automated analysis system for an axial ODSCC on the tubes of an OPR1000 steam generator.
목차
Abstract
1. Introduction
2. Method and Results
3. Conclusions
References
참고문헌 (5)
참고문헌 신청
1. [기타자료] - Zetec Inc / 2001 / Computer Data Screening User Guide
2. [기타자료] - Electric Power Research Institute / 2009 / Automated analysis performance demonstration database pressurized water reactor steam generator examination guidelines / EPRI SGMP TR-10119123 : 6 ~ 8
3. [기타자료] - Electric Power Research Institute / 2007 / Pressurized water reactor steam generator examination guidelines: Revision 7 / EPRI SGMP TR-1013706 : G-7 ~
4. [기타자료] - Electric Power Research Institute / 2002 / Steam generator tubing burst testing and leak rate testing guidelines, EPRI Binned POD_alculator / EPRI SGMP TR-1006783 : 6 ~ 8
5. [기타자료] - Korea Hydro & Nuclear Power Co., LTD / 2012 / Integrated guidelines of steam generator management program: Revision 1 / Standard Procedure SG Inspection : 28 ~
2. [기타자료] - Electric Power Research Institute / 2009 / Automated analysis performance demonstration database pressurized water reactor steam generator examination guidelines / EPRI SGMP TR-10119123 : 6 ~ 8
3. [기타자료] - Electric Power Research Institute / 2007 / Pressurized water reactor steam generator examination guidelines: Revision 7 / EPRI SGMP TR-1013706 : G-7 ~
4. [기타자료] - Electric Power Research Institute / 2002 / Steam generator tubing burst testing and leak rate testing guidelines, EPRI Binned POD_alculator / EPRI SGMP TR-1006783 : 6 ~ 8
5. [기타자료] - Korea Hydro & Nuclear Power Co., LTD / 2012 / Integrated guidelines of steam generator management program: Revision 1 / Standard Procedure SG Inspection : 28 ~
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