• Nuclear Engineering and Technology
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• 제46권6호
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• pp.869-874
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• 2014

It was discovered in a Korean PWR that an extensive number of very short and shallow cracks in the SG tubes were undetectable by eddy current in-service-inspection because of the masking effect of sludge deposits. Axial stress corrosion cracks at the outside diameter of the steam generator tubes near the line contacts with the tube support plates are the major concern among the six identical Korean nuclear power plants having CE-type steam generators with Alloy 600 high temperature mill annealed tubes, HU3&4 and HB3~6. The tubes in HB3&4 have a less susceptible microstructure so that the onset of ODSCC was substantially delayed compared to HU3&4 whose tubes are most susceptible to ODSCC among the six units. The numbers of cracks detected by the eddy current inspection jumped drastically after the steam generators of HB4 were chemically cleaned. The purpose of the chemical cleaning was to mitigate stress corrosion cracking by removing the heavy sludge deposit, since a corrosive environment is formed in the occluded region under the sludge deposit. SGCC also enhances the detection capability of the eddy current inspection at the same time. Measurement of the size of each crack using the motorized rotating pancake coil probe indicated that the cracks in HB4 were shorter and substantially shallower than the cracks in HU3&4. It is believed that the cracks were shorter and shallower because the microstructure of the tubes in HB4 is less susceptible to ODSCC. It was readily understood from the size distribution of the cracks and the quantitative information available on the probability of detection that most cracks in HB4 had been undetected until the steam generators were chemically cleaned.

• 비파괴검사학회지
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• 제35권1호
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• pp.61-67
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• 2015

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.

• 한국산학기술학회논문지
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• 제14권4호
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• pp.2043-2048
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• 2013

원자력발전소 OPR-1000 CE형 증기발생기는 전열관 재질이 Alloy-600 HTMA으로 되어 있고, 2차측은 퇴적된 슬러지로 인해 ODSCC가 발생한다. ODSCC는 관판 주변에 집중되고 있고, 슬러지 높이에 따라 영향을 받고 있다. 증기발생기 2차측 부식분위기 저감과 함께 전열관의 응력부식균열의 발생을 억제하기 위하여 부분화학세정을 실시하였다. 슬러지 제거량은 259.2kg이고, 퇴적 슬러지 높이는 0.71인치에서 0.34인치로 낮아졌으며, 부식율은 최대 2.34mils로서 EPRI 권고사항인 10mils 이내로 만족하였다.

• 비파괴검사학회지
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• 제33권6호
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• pp.519-523
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• 2013

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.