• 비파괴검사학회지
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• 제26권3호
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• pp.174-180
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• 2006

Steam generator (SG) tubes are expanded inside tubesheet holes by using explosive or hydraulic methods to be fixed in a tubesheet. In the tube expansion process, it is important to minimize the crevice gap between expanded tube and tube sheet. In this paper, absolute and differential signals are computed by a numerical method for several different locations of tube expansion inside and outside a tubesheet and signal variations due to tubesheet, tube expansion and operating frequencies are observed. Results show that low frequency is good for detecting tubesheet location in both types of signals and high frequency is suitable for sizing of tube diameter as well as the detection of transition region. Also learned is that the absolute signal is good for measuring tube diameter, while the differential signal is good for locating the top of tubesheet and both ends of the transition region. In the case of mingled anomaly with tube expansion and tubesheet, low frequency inspection is found to be useful to analyze the mixed signal.

• 비파괴검사학회지
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• 제36권4호
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• pp.295-299
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• 2016

증기발생기 2차측(관판 상단 및 관 지지판)에 잔류하는 이물질은 전열관에 마모를 야기하여 누설을 발생시킬 가능성이 있으며, 마모는 전열관 재료의 부식 특성과는 별개로 이물질의 재료, 형태, 크기 등에 따라 큰 영향을 받는다. 관판 상단 및 관 지지판 부위의 이물질 여부는 원격육안검사(FOSAR) 방법과 와전류탐상검사(ECT)를 통해 확인하고 있다. 증기발생기 2차측의 잔류 이물질은 그 재질이나 전열관과의 접촉상태 등에 따라 검출하는데 제한성이 나타난다. 따라서, 본 연구에서는 다양한 형태와 재료의 이물질을 관판 상단에서 수직 및 수평한 방향으로 이동시켰을 때, 이물질에 대한 보빈신호의 검출 감도를 측정하기 위해 데이터를 수집하고 분석하였다.

• 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.

• Nuclear Engineering and Technology
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• 제30권4호
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• pp.377-385
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• 1998

Many nuclear power plants have experienced unscheduled shutdown due to the leakage of steam generator tubes. The leakages are normally due to the crack, possibly stress corrosion cracking (SCC) near the tube expansion at the top of tubesheet or at the tangential point of the row-1 U-bend region. The conventional eddy current technique, which makes use of a differential bobbin coil, has been found to be inadequate for the early detection of SCC. During the in-service inspection, therefore, it is a general practice that the rotating pancake coil (RPC) is used for detecting the cracks. Even in using RPC, however, it is difficult to determine the depth of the cracks quantitatively. This paper attempts to determine the detectability and sizing ability of RPC technique for axial or circumferential cracks at the tube expansion region. The simulated cracks with various dimensions were fabricated by electro-discharge machining (EDM) method. Experimental results are discussed with theoretical calculations.

• Corrosion Science and Technology
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• 제17권3호
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• pp.116-122
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• 2018

The secondary coolant of a nuclear power plant has small amounts of various impurities (S, Pb, and Cl, etc.) introduced during the initial construction, maintenance, and normal operation. While the concentration of impurities in the feed water is very low, the flow of the cooling water is restricted, so impurities can accumulate on the Top of Tubesheet (TTS). This environment is chemically very complicated and has a very wide range of pH from acidic to alkaline. In this study, the characteristics of the oxide and the mechanism of stress corrosion cracking (SCC) are investigated for Alloy 690 TT in alkaline solution containing Pb, Cl, and S. Reverse U-bend (RUB) specimens were used to evaluate the SCC resistance. The test solution comprises 3m NaCl + 500ppm Pb + 0.31m $Na_2SO_4$ + 0.45m NaOH. Experimental results show that Alloy 690 TT of the crevice environment containing Pb, S, and Cl has significant cracks, indicating that Alloy 690 is vulnerable to stress corrosion cracking under this environment.

• 한국압력기기공학회 논문집
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• 제20권1호
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• pp.16-24
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• 2024

Denting of steam generator (SG) tube is defined as the reduction in tube diameter due to the stresses exerted by the corrosion products formed on the outer diameter surface. This phenomenon is mostly observed in the crevices between SG tube and the top-of tubesheet or tube support plate. Despite the replacement of SG tube with Alloy 690, which has better corrosion resistance than Alloy 600, the denting of SG tube still remains a potential problem that could decrease the SG integrity. Deformation of SG tube by denting phenomenon can affect the surface properties and microstructure of SG tube. In this study, the effects of plastic deformation on surface properties and microstructure of Alloy 690 thermally treated (TT) tube was investigated by using the various analysis techniques. The plastic deformation of Alloy 690 increased the surface roughness and area. Many surface defects such as ripped surface and micro-cracks were observed on the deformed Alloy 690TT specimen. Based on the electron backscatter diffraction analysis, the dislocation density of deformed SG tube increased compared to non-deformed SG tube. In addition, the effects of changes in surface properties and microstructure of SG tube on general corrosion behavior were discussed.

• 한국압력기기공학회 논문집
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• 제7권3호
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• pp.61-66
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• 2011

The integrity of the SG(Steam Generator) tubes has been challenged by numerous factors such as flaws, operation, atmosphere, inherently degraded materials, loose parts and even human errors. Of the factors, loose parts(or foreign materials) on the secondary side of the tubes can bring about volumetric defects and even leakage from the primary to the secondary side in a short period of time. More serious concerns about the loose parts are their unknown influx path and rapid growth rate of the defects affected by the loose parts. Therefore it is imperative to detect and characterize the foreign materials and the defects. As a part of the measures for loose part detection, TTS(Top of Tubesheet) MRPC(Motorized Rotating Pancake Coils) ECT has been carried out especially to the restricted high probability area of the loose part. However, in the presence of loose parts in the other areas, wide range loose part detection techniques are required. In this study, loose part standard tube was presented as a way to accurately detect and characterize loose part signals. And the SG tube ECT bobbin coil and MRPC ISI(In-service Inspection) data of domestic OPR-1000 and Westinghouse Model F(W_F) were reviewed and consequently, comprehensive loose part detection technique is derived especially by applying bobbin coil signals

• 비파괴검사학회지
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• 제28권2호
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• pp.184-190
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• 2008

원전 증기발생기 전열관의 건전성을 평가하기 위해서 여러 가지 와전류검사 기법이 적용되고 있다. 이와 같은 와전류검사 기법중에서 보빈탐촉자 기법은 전열관에 발생할 수 있는 축방향균열, 마모 검사에 적용하고 있으며, MRPC 기법은 튜브시트 상단 및 곡관부위 균열의 정밀검사에 적용된다. 원전 증기발생기 전열관의 설치공정 혹은 운전중에 전열관에 덴트(dent, 혹은 ding) 및 벌지(bulge)가 형성될 수 있으며, 와전류검사에서 이러한 지시는 결함으로 간주하지 않기 때문에 일정 크기 이상의 지시만 검사보고서에 기록하여 관리하고 있다. 이러한 지시는 보빈탐촉자 기법으로 용이하게 검출이 가능하고 보빈단면형상검사에 의해 대략적인 크기의 측정이 가능하지만, 정확한 크기 및 형상은 알 수는 없으므로 본 연구에서는 단면형상검사의 정확도를 증가시키기 위해 $8{\times}1$ 다중코일 탐촉자를 설계 개발하여 그 정확도를 평가하였다. 한편, OPR-1000형 증기발생기 전열관의 튜브시트 확관 천이영역에 형성된 덴트부위에 균열성 결함이 발생할 가능성이 높기 때문에 일부 발전소에서는 예방차원의 슬리빙을 수행하고 있다 이와 같은 슬리빙 대상 전열관 선정시 본 검사기법을 활용하면 유용할 것으로 판단된다.