• Corrosion Science and Technology
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• 제15권2호
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• pp.84-91
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• 2016

The transport and deposition of corrosion products in pressurized water nuclear reactor (PWR) steam generators have led to corrosion (SCC, denting etc.) problems. Lancing, mechanical cleaning and chemical cleaning have been used to reduce these problems. The methods of lancing and mechanical cleaning have limitations in removing corrosion products due to the structure of steam generator tubes. But high temperature chemical cleaning (HTCC) with EDTA is the most effective method to remove corrosion products regardless of the structure. However, EDTA in chemical cleaning aqueous solution and chemical cleaning environments affects the integrity of materials used in steam generators. The nuclear power plants have to perform the pre-test (also called as qualification test (QT)) that confirms the effect on the integrity of materials after HTCC. This is one of the series studies that assess the effect, and this study determines the effects of 20 % EDTA aqueous solution on defective tubes in high temperature chemical cleaning environments. The depth and magnitude of defects in steam generator (SG) tubes were measured by eddy current test (ECT) signals. Surface analysis and magnitude of defects were performed by using SEM/EDS. Corrosion rate was assessed by weight loss of specimens. The ECT signals (potential and depth %) of defective tubes increased marginally. But the lengths of defects, oxides on the surface and weights of specimens did not change. The average corrosion rate of standard corrosion specimens was negligible. But the surfaces on specimens showed traces of etching. The depth of etching showed a range on the nanometer. After comprehensive evaluation of all the results, it is concluded that 20 % EDTA aqueous solution in high temperature chemical cleaning environments does not have a negative effect on defective tubes.

• 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.511-518
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• 2013

Steam Generator (SG) tube, as a barrier isolating the primary coolant system from the secondary side of nuclear power plants (NPP), must maintain the structural integrity for the public safety and their efficient power generation. So, SG tubes are subject to the periodic examination and the repairs if needed so that any defective tubes are not in service. Recently, corrosion related degradations were detected in the tubes of the domestic OPR-1000 NPP, as a form of axially oriented outer diameter stress corrosion cracking (ODSCC). According to the studies on the factors causing the heat fouling as well as developing corrosion cracking, densely scaled deposits on the secondary side of the SG tubes are mainly known to be problematic causing the adverse impacts against the soundness of the SG tubes [1]. Therefore, the processes of various cleaning methods efficiently to dissolve and remove the deposits have been applied as well as it is imperative to maintain the structural integrity of the tubes after exposing to the cleaning agent. So qualification test (QT) should be carried out to assess the perfection of the chemical cleaning and QT is to apply the processes and to do ECT. In this paper, the chemical cleaning processes to dissolve and remove the scaled deposits are introduced and results of ECT on the artificial crack specimens to determine the effectiveness of those processes are represented.

• 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.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.175-176
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• 2005

• 공업화학
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• 제17권5호
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• pp.552-556
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• 2006

본 연구에서는 70000 mg/L 가량의 고농도 철(III)-에틸렌디아민테트라아세트산(Fe(III)-EDTA)을 함유하고 있는 원전 증기발생기 화학 세정 폐액의 처리를 위해 펜톤 반응을 사용하였다. Fe(III)-EDTA 분해실험은 모사 폐액 뿐 아니라 실제 폐액을 가지고도 수행되었다. 폐액에 주입된 과산화수소의 양과 폐액의 pH가 Fe(III)-EDTA 분해에 미치는 영향이 정량적으로 평가되었고, 다양한 측면에서 고찰되었다. 분해효율이 최대가 되는 최적의 pH는 폐액에 주입된 과산화수소의 양에 의존하였다. 즉, 폐액에 주입된 과산화수소의 양이 다를 때 최대 분해효율이 얻어지는 pH가 달랐다. Fe(III)-EDTA의 분해를 위한 적정 조건은 폐액의 초기 pH가 9이고 과산화수소 주입량이 24.7 mol ($H_{2}O_{2}$)/mol (Fe(III)-EDTA)일 때였다.

• 원자력산업
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• 제30권3호
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• pp.52-56
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• 2010

증기발생기 2차측 상태는 발전소 운영에 있어 중요한 역할을 수행한다. 기기, 배관 및 열교환기에서 발생되는 침적물은 증기발생기 튜브의 부식 원인이 될 수 있으며, 튜브와 튜브 지지판 사이의 공간을 차단한다. 2차측 침적물에 의한 튜브 파손으로 인해 일부 발전소에서는 강제적으로 발전을 정지하는 사례가 발생하였다. 또한 튜브 지지판의 침적물 축적으로 인해 정상 운전 동안 전력 생산을 감소하게 되는 결과를 초래한 발전소도 있었다. 따라서 증기발생기 2차측 상태 감시와 더불어 증기발생기 부품의 청결 유지는 필수 항목이라 할 수 있다. 웨스팅하우스에서는 증기발생기를 초기 제작 상태로 복구하고 2차측 침적물을 제거하기 위해 EPRI SGOG 증기발생기 화학 세정을 수 년간 이용하고 있다. 본고는 35개 이상의 발전소에서 성공적으로 이용하고 있는 화학 세정 프로세스 개요 및 프로세스를 적용하면서 취득한 경험을 요약한 것이다.

• 한국표면공학회:학술대회논문집
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• 한국표면공학회 2013년도 춘계학술대회 논문집
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• pp.117-118
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• 2013

증기발생기 화학세정 모사 장치를 이용하여 고농도 화학세정(EPRI/SGOG) 용액인 EDTA(20%)가 인위적으로 제작한 결합 시편에 미치는 영향 평가를 수행하였다. 평가 방법은 세정 전 후 표면 산화막 성분, ECT 분석값 비교, 증기발생기 구성 재료 부식률를 이용하였다. 화학세정 전후 부식률은 A508은 $8.023{\mu}m$, Alloy 600(HTMA)은 $0.007{\mu}m$이며 갈바닉 시편의 경우 $63.193{\mu}m$로 모두 부식 허용치 이내이다. 표면 산화막 성분 및 ECT 분석값 역시 변함이 없었다. 이와 같은 결과로 화학세정 용액인 EDTA는 결함 튜브에 미치는 영향이 없는 것으로 판단된다.

• 한국조명전기설비학회:학술대회논문집
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• 한국조명전기설비학회 2008년도 춘계학술대회 논문집
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• pp.415-418
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• 2008

This paper presents an innovative prototype of a new conceptual electromagnetic induction-based fluid beating appliance using voltage-fed type scries capacitor-compensated load resonant high-frequency IGBT inverter with a phase-shifted PWM and a power factor correction schemes. Its operating characteristics in steady-state are illustrated including unique features and evaluated on the basis of its computer simulation and experimental results of 10kw breadboard appliance for hot water producer and superheated steamer. The promising cost effective inverter-fed boiler appliances for electromagnetic induction-heated type fluid-heating in the pipeline systems are proposed for induction-heated boiler, super heat steamer, high temperature water producer, hot gas producer and metal catalyst heating for exhaust gas cleaning in engine, which are more suitable and acceptable for industrial, chemical, and consumer energy utilization for household and business from a practical point of view.