가압기 히터슬리브 용접부 PWSCC 검출을 위한 유도초음파 특성 평가

주경문,문용식,정우근,Joo, Kyung-Mun,Moon, Yong-Sig,Chung, Woo-Geun 한국압력기기공학회 2011 한국압력기기공학회 논문집 Vol.7 No.2

Although many defects in PZR heater sleeve have been reported continually from operating experiences in oversea nuclear power plant, utilities get into difficulties in finding appropriate methods for diagnostics of the components due to the limited access or high radiation problems. Recently, as an alternative, diagnostics using Guided Wave Testing(GWT) are proposed and the attention of the methods has been growing gradually because of their long range inspection capability. This study is to investigate the effectiveness of GWT to detect PWSCC in welding points of PZR heater sleeve. Moreover, mode sensitivity analysis of GWT and optimal frequency for the diagnostics of PWSCC are presented by testing the mock-ups specimens that contain artificial flaws.

증기발생기 전열관 외면 축균열 건전성 평가를 위한 비파괴검사 크기 측정 평가

주경문,홍준희,Joo, Kyung-Mun,Hong, Jun-Hee 한국비파괴검사학회 2015 한국비파괴검사학회지 Vol.15 No.1

최근 국내 증기발생기 Alloy 600HTMA 전열관의 관 지지판 부위 외면 축균열 결함의 생성이 지속적으로 증가하고 있다. 이로 인하여 증기발생기가 설계수명 이전에 조기 교체되었으며 또는 교체 예정이다. 전열관 외면 축균열은 건전성 관리에 가장 위협이 되는 요소이므로 정밀한 건전성 평가가 요구된다. 와전류검사(ECT, eddy currunt testing)는 주기적으로 수행되어 지며 이 결과는 건전성 평가 입력 자료로 활용된다. ECT 검사시스템의 신뢰성은 검사기술과 평가자 기량에 의존하며, NDE 시스템 성능을 보여주는 지수는 열화탐지와 크기 측정 오차이다. 본 연구에서는 국내 평가자 성능이 반영된 크기 측정 오차와 그리고 최적의 균열 크기 측정 방법을 제시하였다. 실험은 국내 각기 다른 5개 회사에서 10명의 평가자가 참여한 다자간 비교시험의 결과를 사용하여 이루어졌다. 실험 결과 분석은 파괴검사 결과값과 비파괴검사로 측정된 값의 상관관계를 회귀분석을 통하여 이루어졌다. Recently, the initiation of outside diameter stress corrosion cracking (ODSCC) at the tube support plate region of domestic steam generators (SG) with Alloy600 HTMA tubes has been increasing. As a result, SGs with Alloy600 HTMA tubes must be replaced early or are scheduled to be replaced prior to their designed lifetime. ODSCC is one of the biggest threats to the integrity of SG tubes. Therefore, the accurate evaluation of tube integrity to determine ODSCC is needed. Eddy current testing (ECT) is conducted periodically, and its results could be input as parameters for evaluating the integrity of SG tubes. The reliability of an ECT inspection system depends on the performance of the inspection technique and abilty of the analyst. The detection probability and ECT sizing error of degradation are considered to be the performance indices of a nondestructive evaluation (NDE) system. This paper introduces an optimized evaluation method for ECT, as well as the sizing error, including the analyst performance. This study was based on the results of a round robin program in which 10 inspection analysts from 5 different companies participated. The analysis of ECT sizing results was performed using a linear regression model relating the true defect size data to the measured ECT size data.

유도초음파기법을 이용한 튜빙 결함측정에 관한 연구

주경문,천근영,이정석,Joo, Kyung Mun,Cheon, Keun Young,Lee, Jeong Seok 한국압력기기공학회 2009 한국압력기기공학회 논문집 Vol.5 No.1

There is extensive tubing pipe in the nuclear power plant under high temperature and pressure. Erosion and corrosion defects are expected on this tubing pipe due to environmental and mechanical factors. In this study, Guided Ultrasonic Wave technique was applied to detect defects. The technique explores the advantages of the Guided Ultrasonic Wave method that inspects along the wall of the pipe and can travel long distances, providing rapid collection of data. This paper presents a case study of the Guided Ultrasonic Wave testing of 3/8" tubing pipe. This study offers to understand detected signals through correlation between amplitude and depth of defects.

유도초음파기술을 이용한 배관 감육 평가

주경문(Kyung Mun Joo),진석홍(Seuk Hong Jin),문용식(Yong Sig Moon) 한국비파괴검사학회 2010 한국비파괴검사학회지 Vol.30 No.4

원자력발전소 탄소강 배관의 유체가속부식은 주요 경년열화 현상이며 발전소의 성능 및 안전성을 저해할 수 있다. 유체가속부식 검사는 보온재 제거 및 설치로 상당한 비용이 수반되므로 최근에 보온재 제거가 필요 없고 원거리 검사가 가능한 유도초음파에 대한 관심이 점점 증가되고 있다. 유체가속부식 검출에 유도초음파 적용이 가능하다면 검사 비용 절감이 예상된다. 본 연구의 목적은 유체가속부식 손상 유무를 확인하고 결함 검출능을 결정하기 위함이다. 본 연구에서는, 실제 유체가속부식 손상 시험편의 엘보우 첫 번째 용접부와 두 번째 용접부의 진폭 감쇄비를 측정하기 위하여 3가지 검사 기법을 사용하였다. 연구 결과, 유체가속부식 손상을 검출하기 위한 최적의 검사 기법과 최소 결함 검출능을 도출하였다. Flow accelerated corrosion(FAC) of carbon steel pipes in nuclear power plants has been known as one of the major degradation mechanisms. It could have bad influence on the plant reliability and safety. Also detection of FAC is a significant cost to the nuclear power plant because of the need to remove and replace insulation. Recently, the interest of the guided wave testing(GWT) has grown because it allows long range inspection without removing insulation of the pipe except at the probe position. If GWT can be applied to detection of FAC damages, it will can significantly reduce the cost for the inspection of the pipes. The objective of this study was to determine the capability of GWT to identify location of FAC damages. In this paper, three kinds of techniques were used to measure the amplitude ratio between the first and the second welds at the elbow area of mock-ups that contain real FAC damages. As a result, optimal inspection technique and minimum detectability to detect FAC damages drew a conclusion.

증기발생기 전열관 외면 축균열 건전성 평가를 위한 비파괴검사 크기 측정 평가

주경문(Kyung-Mun Joo),홍준희(Jun-Hee Hong) 한국비파괴검사학회 2015 한국비파괴검사학회지 Vol.35 No.1

최근 국내 증기발생기 Alloy 600HTMA 전열관의 관 지지판 부위 외면 축균열 결함의 생성이 지속적으로 증가하고 있다. 이로 인하여 증기발생기가 설계수명 이전에 조기 교체되었으며 또는 교체 예정이다. 전열관 외면 축균열은 건전성 관리에 가장 위협이 되는 요소이므로 정밀한 건전성 평가가 요구된다. 와전류 검사(ECT, eddy currunt testing)는 주기적으로 수행되어 지며 이 결과는 건전성 평가 입력 자료로 활용된다. ECT 검사시스템의 신뢰성은 검사기술과 평가자 기량에 의존하며, NDE 시스템 성능을 보여주는 지수는 열화 탐지와 크기 측정 오차이다. 본 연구에서는 국내 평가자 성능이 반영된 크기 측정 오차와 그리고 최적의 균열 크기 측정 방법을 제시하였다. 실험은 국내 각기 다른 5개 회사에서 10명의 평가자가 참여한 다자간 비교시험의 결과를 사용하여 이루어졌다. 실험 결과 분석은 파괴검사 결과값과 비파괴검사로 측정된 값의 상관관계를 회귀분석을 통하여 이루어졌다. Recently, the initiation of outside diameter stress corrosion cracking (ODSCC) at the tube support plate region of domestic steam generators (SG) with Alloy600 HTMA tubes has been increasing. As a result, SGs with Alloy600 HTMA tubes must be replaced early or are scheduled to be replaced prior to their designed lifetime. ODSCC is one of the biggest threats to the integrity of SG tubes. Therefore, the accurate evaluation of tube integrity to determine ODSCC is needed. Eddy current testing (ECT) is conducted periodically, and its results could be input as parameters for evaluating the integrity of SG tubes. The reliability of an ECT inspection system depends on the performance of the inspection technique and abilty of the analyst. The detection probability and ECT sizing error of degradation are considered to be the performance indices of a nondestructive evaluation (NDE) system. This paper introduces an optimized evaluation method for ECT, as well as the sizing error, including the analyst performance. This study was based on the results of a round robin program in which 10 inspection analysts from 5 different companies participated. The analysis of ECT sizing results was performed using a linear regression model relating the true defect size data to the measured ECT size data.

증기발생기 전열관 와전류검사용 국내 개발 보빈탐촉자 적용성 분석

김인철,주경문,문용식,Kim, In-Chul,Joo, Kyung-Mun,Moon, Yong-Sig 한국압력기기공학회 2011 한국압력기기공학회 논문집 Vol.7 No.4

Steam Generator(SG) tube is an important component of Nuclear Power Plant(NPP), which is the pressure boundary between the primary and secondary systems. The integrity of SG tube has been confirmed by the eddy current test every outage. The eddy current technique adopting bobbin probe is currently the primary technique for the steam generator tubing integrity assesment. The bobbin probe is one of the essential components which consist of the whole ECT examination system and provides us a decisive data for the evaluation of tube integrity. Until now, all of the ECT bobbin probes in Korea which is necessary to carry out inspection are imported from overseas. However, KHNP has recently developed the bobbin probe design technology and transferred it to domestic manufacturers to fabricate the probes. This study has been conducted to establish technical requirements applicable to the steam generator tube inspection using the bobbin probes fabricated by the domestic manufactures. The results have been compared with the results obtained by using foreign probe to identify the availability to the steam generator tube inspection. As a result, it is confirmed that the domestic bobbin probe is generally applicable to SG tube inspection in the NPPs.