• 한국압력기기공학회 논문집
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• 제10권1호
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• pp.7-14
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• 2014

There has been extensive experience associated with the operation of SGs wherein it was believed, based on NDE, that throughwall tube indications were present within the tubesheet. The installation of the SG tubes usually involves the development of a short interference fit, referred to as the tack expansion, at the bottom of the tubesheet. The tack expansion was usually effected by a hard rolling process and thereafter, in most instance, by the expansion of a urethane plug inserted into the tube end and compressed in the axial direction. The rolling process by its very nature is considered to be intensive with regard to metalworking at the inside surface of the tube and would be expected to lead to higher residual surface stresses. Alternate repair criteria(ARC) in the tack expansion area have been developed and applied to nuclear power plants in USA, however domestic nuclear power plants have not applied ARC for tubes in tubeheet area yet. In consideration of the degradation characteristics of tubes in the Steam Generator tubesheet, this paper suggests ARC application for tubes in the steam generator tubesheet of the domestic nuclear power plants in order to assure life time of the steam generator as well as nuclear power plants.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2009년도 제40회 하계학술대회
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• pp.790_791
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• 2009

본 논문에서는 전자기 유한요소 해석을 통하여 원전 증기 발생기(SG, Steam Generator) 세관의 결함 변화에 따른 배열와전류프로브의 와전류탐상 특성을 해석하였다. 프로브의 전자기적 특성을 위해 맥스웰 방정식을 이용하여 지배방정식을 유도하였고, 이를 3차원 전자기 유한요소법을 이용하여 문제를 해석하였다. 해석을 위한 선정한 결함은 프로브의 특성파악을 위한 표준시험편과 원전 SG세관에 발생 가능한 결함인 Pitting, SCC, Wear, Multi SCC 결함을 선정하였다. 해석 대상으로는 원자력발전소 증기발생기 세관으로 사용되고 있는 Inconel 600 도체관을 사용하였다. 본 논문으로 통하여 결함의 형상, 크기, 시험주파수의 변화에 따른 탐상신호의 변화를 확인할 수 있었다. 본 논문의 결과는 배열와전류프로브의 와전류탐상 신호 평가시 도움이 될 것이다.

• Nuclear Engineering and Technology
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• 제41권10호
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• pp.1315-1322
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• 2009

The present article is concerned with the application of an electrochemical noise (EN) monitoring technique to analyze the initiation and propagation of Pb-assisted stress corrosion cracking (SCC) of an Alloy 600 material in a simulated environment of a steam generator (SG) sludge pile at high temperatures. A typical increase of electrochemical current noise (ECN) and electrochemical potential noise (EPN) was frequently recorded from the EN measurement in a caustic solution with such impurities as PbO and CuO, indicating that there are localized corrosion events occurring. With the aid of microscopic and spectral analyses, the EN data involving information on such stochastic processes as uniform corrosion and the initiation and propagation of SCC, were analyzed based on a stochastic theory.

• 한국윤활학회:학술대회논문집
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• 한국윤활학회 2001년도 제33회 춘계학술대회 개최
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• pp.115-121
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• 2001

The wear test has been performed to evaluate the wear mechanism of steam generator (SG) tube materials against ferritic stainless steel in water environment. The wear rates of SG tube materials depend on the change of mechanical properties between contact surfaces during wear test. From the subsurface hardness test, Inconel 690 is more work-hardened than Inconel 600 even though these materials have similar hardness values before the wear test. Main cause is due to the difference of stacking fault energy with the chromium content. In water environment, wear mechanism is closely related with the continuous formation and fracture of deformation layers at the contact surfaces.

• 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.

• Nuclear Engineering and Technology
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• 제36권2호
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• pp.127-141
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• 2004

Various types of integrated steam generators, which integrate IHTS and a steam generator into a single unit of equipment for an LMR, were analyzed using an analytic solution with some simplification. The analysis showed that the undesirable reversed heat transfer, of which occurrence was previously observed only in an integrated single-region bundle type, can also occur in an integrated double-region bundle type. The mechanism of the reversed heat transfer occurrence in the double-region type is explained and it is shown the mechanism in the double-region type is completely different from that in the single-region type. Based on this finding, a method for preventing the aforementioned heat transfer is suggested. The performance of the four types of the integrated steam generators is assessed. For this assessment, a SG is actually designed for each type and the optimization in the geometric parameters and flow rate are optimized.

• 비파괴검사학회지
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• 제21권5호
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• pp.518-525
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• 2001

증기발생기 전열관이 노후화 됨에 따라 새롭고 판단이 애매한 결함이 발생되기 시작하고 있다. 대부분의 결함은 전열관 외부에서 발생되어 진전된다. 일반 와전류탐상에서는 외부결함으로부터의 신호가 표피효과로 인해 내부결함으로부터의 신호보다 매우 약하기 때문에, 본 논문에서는 자성체 관 검사에서 내부 및 외부결함에 거의 같은 민감도를 보인 바 있는 원격장와전류 탐상을 비자성체인 전열관의 검사에 적용하기 위한 연구를 수행하였다. 유한요소 모델링을 통한 연구결과는 비자성체인 전열관에서 원격장와전류 효과가 나타나려면 탐상주파수가 수백 kHz가 되어야 하며, 여자코일과 센서코일간의 간격은 자성 관 검사시의 절반인 관 외경의 1.5배 정도가 되어야 함을 보였다. 이렇게 설계된 탐촉자를 사용하여 예측한 결함신호들은 이 검사방법이 내부 및 외부결함에 동일하게 민감하며, 위상신호의 세기와 결함깊이간에는 선형적인 비례관계가 존재함을 보여 주었다. 이러한 결과들은 비자성 증기발생기 전열관이라 할지라도 원격장와전류 탐상이 가능함을 말해 주고 있다.

• 비파괴검사학회지
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• 제27권5호
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• pp.383-392
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• 2007

본 논문에서는 신경회로망을 이용하여 원자력 발전소 증기발생기 세관의 결함 깊이와 폭을 예측하는 연구를 수행한다. 결함 크기 추정을 위하여 우선, I-In 형태, I-Out 형태, V-In 형태, V-Out 형태의 4가지 결함형상에 대한 와전류탐상시험(ECT) 신호를 생성한다. 특히, 유한요소법에 기반한 수치해석 기법을 이용하여 여러 가지 폭과 깊이를 갖는 결함 400개의 ECT 신호를 생성한다. 이와 같이 생성된 ECT 신호로부터, 결함 크기와 폭을 예측하기 위한 새로운 특징벡터를 추출하는데, 이 특징벡터에는 최대 임피던스 값을 갖는 점과 최대 임피던스값의 1/2의 값을 갖는 점 사이의 위상각이 포함된다. 추출된 특징벡터를 이용하여 결함의 크기를 예측하기 위해서 하나의 은닉층을 갖는 다층퍼셉트론을 이용하였다. 컴퓨터 모의실험 연구를 통하여 제안된 방법이 우수한 예측성능을 갖는다는 것을 보였다.

• 비파괴검사학회지
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• 제29권1호
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• pp.27-35
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• 2009

본 논문에서는 개선된 특징추출을 이용한 원자력 발전소 증기발생기 세관의 결함 형태 분류에 대한 연구를 수행한다. 본 논문에서는 4가지 축대칭 결함, 즉 I-In 형태, I-Out 형태, V-In 형태, V-Out 형태 결함을 고려한다. 유한요소법에 기초한 수치해석 프로그램을 이용하여 결함의 폭과 깊이를 변화시켜가면서 400개의 와전류탐상시험(ECT) 신호를 생성하였다. 이와 같이 생성된 ECT 신호로부터 새로운 특징을 제안하였는데, 여기에는 최대 임피던스 값을 갖는 점과 최대 임피던스 값의 1/2의 값을 갖는 점 사이의 위상각과 최대임피던스 값을 갖는 점과 최대 임피던스 값의 10%, 20%, 30%, 40%를 갖는 점사이의 위상각들이 포함된다. 또한, 결함형태를 분류하기 위하여 은닉층이 하나인 다층퍼셉트론을 사용하였다. 컴퓨터 모의실험 연구를 통하여 제안된 방법이 최대오차와 평균제곱오차 측면에서 향상된 결함 분류 성능을 얻는다는 것을 보였다.

• Corrosion Science and Technology
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• 제13권3호
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• pp.112-119
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• 2014

In this work, it is aimed to develop the fabrication method of axial stress corrosion cracking (SCC) defects having various sizes, on the outer diameter surface of the steam generator (SG) tubings. To control the length of the artificial SCC defect, the specific area of the SG tubing samples was exposed to an acidic solution after a sensitization heat treatment. During the exposure to an acidic solution, a direct current potential drop (DCPD) method was adopted to monitor the crack depth. The size of the SCC defect was first evaluated by an eddy current test (ECT), and then confirmed by a destructive examination. From the comparison, it was found that the actual crack length was well controlled to be similar to the length of the surface exposed to an acidic solution (5, 10, 20 or 30 mm in this work) with small standard deviation. From in-situ monitoring of the crack depth using the DCPD method, it was possible to distinguish a non-through wall crack from a through wall crack, even though the depth of the non-through wall crack was not able to be precisely controlled. The fabrication method established in this work was useful to simulate the SCC defect having similar size and ECT signals as compared to the field cracks in the SG tubings of the operating Korean PWRs.