• 설비공학논문집
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• 제21권9호
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• pp.483-495
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• 2009

Feedwater heaters of many nuclear power plants have recently experienced severe wall thinning damange, which will increase as operating time progresses. Several nuclear power plants in Korea have experienced wall thinning damage in the area around the impingement baffle-installed downstream of the high pressure turbine extraction stream line-inside number 5A and 5B feedwater heaters. At that point, the extracted steam from the high pressure turbine is two phase fluid at high temperature, high pressure, and high speed. Since it flows in reverse direction after impinging the impingement baffle, the shell wall of the number 5 high pressure feedwater heater may be affected by flow-accelerated corrosion. This paper describes operation of experience and numerical analysis composed similar condition with real high pressure feedwater heater. This study applied squared, curved and new type impingement baffle plates to feedwater heater same as previous study. In addition, it shows difference of pressure distribution and value between single phase and two phase based on experience and numerical analysis.

• 대한설비공학회:학술대회논문집
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• 대한설비공학회 2009년도 하계학술발표대회 논문집
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• pp.841-846
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• 2009

Several nuclear power plants in Korea have experienced wall thinning damage in the area around the impingement baffle-installed downstream of the high pressure turbine extraction stream line inside number 5A and 5B feedwater heaters. At that point, the extracted steam from the high pressure turbine is two phase fluid at high temperature, high pressure, and high speed. This paper describes operation of experience and numerical analysis composed similar condition with real high pressure feedwater heater. This study applied several impingement baffle plates to feedwater heater same as previous study. In addition, it shows difference of pressure distribution and value between single phase and two phase based on experience and numerical analysis.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2005년도 창립60주년 기념 추계 학술대회
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• pp.137.1-137.1
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• 2005

• 설비공학논문집
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• 제19권12호
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• pp.821-830
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• 2007

Feedwater heaters of many nuclear power plants have recently experienced severe wall thinning damage, which will increase as operating time progresses. Several nuclear power plants in Korea have experienced wall thinning damage in the area around the impingement baffle-installed downstream of the high pressure turbine extraction steam line- inside number 5A and 5B feedwater heaters. At that point, the extracted steam from the high pressure turbine is two phase fluid at high temperature, high pressure, and high speed. Since it flows in reverse direction after impinging the impingement baffle, the shell wall of the number 5 high pressure feedwater heater may be affected by flow-accelerated corrosion. This paper describes the comparisons between the numerical results using the FLUENT code and the down scale experimental data on effect of geometry of the impingement baffle plate on the shell wall thinning. Additionally, a new type impingement baffle plate was installed above the impingement baffle plate in the feedwater heater and then the numerical and experimental study were performed in the same progress.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.617-621
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• 2003

The purpose of this paper is to analyze piping failure trend of safety pipings In domestic nuclear power plants. First, database for the piping failure was constructed with 105 data fields. The database includes plant population data, event data, and service history data. 7 kinds of piping failures in domestic NPPs were investigated. Among the 7 cases, detailed root causes were investigated for 3 cases. The first one is pipe wall thinning in main feedwater pipings of Westinghouse 3 loop type plants. The root cause of the wall thinning was flow accelerated corrosion near welding area. The next one is leak event in chemical and volume control system(CVCS) due to vibration. Some cracks occurred in socket welding area. The events showed that the integrity or socket weld is very vulnerable to vibration. The last one is also a leak event in primary sampling line in Korean standard reactor due to thermal fatigue. Although the structural integrity was not maintained by the events, there was no effect on nuclear safety in the above 3 piping failure eases.

• Corrosion Science and Technology
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• 제11권5호
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• pp.173-178
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• 2012

To manage the wall thinning of carbon steel piping in nuclear power plants, the utility of Korea has performed thickness inspection for some quantity of pipe components during refueling outages and determined whether repair or replacement after evaluating UT (Ultrasonic Test) data. When the existing UT data evaluation methods, such as Band, Blanket, PTP (Point to Point) Methods, are applied to a certain pipe component, unnecessary re-inspecting situations may be generated even though the component does not thinned. In those cases, economical loss caused by repeated inspection and problems of maintaining the pipe integrity followed by decreasing of newly inspected components may be generated. EPRI (Electric Power Research Institute) in USA has suggested several statistical methods, TPM (Total Point Method), LSS (Least Square Slope) Method, etc. to distinguish whether multiple inspecting components have thinned or not. This paper presents the analysis results for multiple inspecting components over three times based on both NAM (Near Area of Minimum) Method developed by KEPCO-E&C and the other methods suggested by EPRI.

• 비파괴검사학회지
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• 제32권2호
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• pp.170-176
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• 2012

원자력 산업에 있어서 파이프의 감육결함은 수명평가 및 안전평가에 막대한 손실을 발생 할 수 있다. 비파괴검사 기법을 이용하여 변형, 진동, 결함 평가를 수행하고 있지만, 넓은 면적의 결함을 평가하는 기법이 적으며, 시간이 오래 걸리는 단점이 있다. 원자력 발전소의 2차계통에서 주로 사용되는 탄소강 배관을 대상으로 내부에 인공 감육결함을 가공하고 두께를 서로 다르게 하여 제작하여 Shearography를 이용하여 감육결함부의 변형을 측정하였다. 또한 광 계측을 통하여 변형, 진동, 결함 평가뿐만 아니라 압력용기의 결함깊이를 정량적으로 평가하고자 한다. 본 논문은 전단간섭계를 이용하여 파이프의 내부 감육 결함을 측정하고, 압력에 따른 변형을 제시한 기법을 이용하여 정량적인 결함의 잉여두께를 평가하고자 한다. 변형량을 이용하여 잉여두께 예측결과 실제 결함깊이와 약 7%의 오차로 신뢰성을 확보하였으며, 압력에 따른 변형량과 잉여두께의 DB구축을 통하여 원전 배관의 감육부 건전성 평가에 활용될 수 있을 것이다. 따라서, 본 연구에서 제안하는 압력용기 결함깊이 측정법은 원자력배관의 감육결함 예측 및 건정성 평가 기술 개발 등 이론과 실험이 결함된 기초연구로서 압력용기의 안정성, 건전성, 보수성을 증진시킬 수 있는 기반확립에 기여할 것으로 기대한다.

• 한국압력기기공학회 논문집
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• 제11권1호
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• pp.1-11
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• 2015

Feedwater Heaters are important components in a nuclear power plant. As the age of heater increases, the maintenance cost required for continuous operation also increases. Most heaters have the carbon steel shells, tube support plates and flow baffles. The carbon steel is susceptible to flow-accelerated corrosion. This is especially true if the flow has a two-phase mixture of steam and condensate. The wall thinning around the wet steam entrance area of the shell is inevitable during some long term operation. The structural integrity of the feedwater heater shell affects the safe operation of the nuclear power plant. Therefore, it is needed for the thinned shell to be repaired. The maintenance method for preventing failure of the shell should be determined by investigating various factors including the stress distribution of thinned area. The stress analysis of the shell including the steam entrance region is studied in this paper. The results of thinned shell is compared with that of intact shell.

• Corrosion Science and Technology
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• 제12권3호
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• pp.125-131
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• 2013

The most common pipe wall thinning degradation mechanisms that can occur in the steam and feedwater systems are FAC (Flow Acceleration Corrosion), cavitation, flashing, and LDIE (Liquid Droplet Impingement Erosion). Among those degradation mechanisms, FAC has been investigated by many laboratories and industries. Cavitation and flashing are also protected on the piping design phase. LDIE has mainly investigated in aviation industry and turbine blade manufactures. On the other hand, LDIE has been little studied in NPP (Nuclear Power Plant) industry. This paper presents the development of prediction system for pipe wall thinning caused by LDIE in terms of erosion rate based on air-water ratio and material. Experiment is conducted in 3 cases of air-water ratio 0.79, 1.00, and 1.72 using the three types of the materials of A106B, SS400, and A6061. The main control parameter is the air-water ratio which is defined as the volumetric ratio of water to air (0.79, 1.00, 1.72). The experiments were performed for 15 days, and the surface morphology and hardness of the materials were examined for every 5 days. Since the spraying velocity (v) of liquid droplets and their contact area ($A_c$) on specimens are changed according to the air-water ratio, we analyzed the behavior of LDIE for the materials. Finally, the prediction equations(i.e. erosion rate) for LDIE of the materials were determined in the range of the air-water ratio from 0 to 2%.

• 치과방사선
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• 제24권1호
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• pp.47-55
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• 1994

Post operative maxillary cyst may arise after the surgical treatment for maxillary sinusitis with the symtoms of swelling, pain, and pus discharge in the buccal region. It is examined by Waters' view, panoramic view and other intraoral radiographs, but quite variable radiologically. Most of the cyst is seen round or ovoid shape radiolucency, destruction, expansion and thinning of the lateral wall or posterior wall, and roots of the adjacent teeth may be resorbed. We studied about 117 cases of the post operative maxillary cysts which diagnosed in department of oral and maxillofacial radiology, Seoul National University Hospital. We analyzed and obtained following results. 1. These cysts occured more frequently in male than in female and the incidence is highest in the 4th and 5th decade. 2. Initial radical operation of maxillary sinus were performed mainly between the age of 10 and 45 years, and about 60% of the patients were 15 to 25 years. 3. Pain and swelling on buccal area, pus discharge, and toothache are most chief compaints, seven cases were found at routine examination without symtoms. 4. Most of these cysts were unilocular with smooth and well-defined border. 5. The majority of the cysts occurred in the anterolateral wall of maxillary sinus. 6. Dental changes of the lesional area were loss of lamina dura and root resorption, but about 55% were not changed.