• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2006년 추계학술발표대회 개요집
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• pp.38-40
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• 2006

Nuclear power plants are urged to reduce operating and maintaining costs to remain competitive as well as to increase the safety preventing the radioactive material to the atmosphere. To reduce the cost and to increase the safety, the inspection of balance-of-plant heat exchanger becomes important. However, there are some problems for plugging the heat exchanger tubes since the criterion and its basis are not clearly described. The codes and standards related to show the tube plugging criteria may not exist currently. In this paper, a method to establish the tube plugging criteria of BOP heat exchangers is introduced and the tube plugging criteria for the non-regenerative heat exchanger in the steam generator blow-down system of nuclear power plant. This method relies on the similar method used to establish the plugging criteria for the steam generator tubes.

• Journal of Mechanical Science and Technology
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• 제20권11호
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• pp.1934-1941
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• 2006

As the operating time of heat exchangers progresses, fouling caused by water-borne deposits and the number of plugged tubes increase and thermal performance decreases. Both fouling and tube plugging are known to interfere with normal flow characteristics and to reduce thermal efficiencies of heat exchangers. The heat exchangers of Korean nuclear power plants have been analyzed in terms of heat transfer rate and overall heat transfer coefficient as a means of heat exchanger management. Except for fouling resulting from the operation of heat exchangers, all the tubes of heat exchangers have been replaced when the number of plugged tubes exceeded the plugging criteria based on design performance sheet. This paper describes a plugging margin evaluation method taking into account the fouling of shell-and-tube heat exchangers. The method can evaluate thermal performance, estimate future fouling variation, and consider current fouling level in the calculation of plugging margin. To identify the effectiveness of the developed method, fouling and plugging margin evaluations were performed at a component cooling heat exchanger in a Korean nuclear power plant.

• 대한기계학회논문집B
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• 제28권11호
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• pp.1384-1389
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• 2004

As operating time of heat exchangers progresses, fouling generated by water-borne deposits and the number of plugged tubes increase and thermal performance decreases. Both fouling and tube plugging are known to interfere with normal flow characteristics and to reduce thermal efficiencies of heat exchangers. The heat exchangers of domestic nuclear power plants have been analyzed in terms of the heat flux and heat transfer coefficient at test conditions as a means of heat exchanger management. Except for the fouling level generated in operation of heat exchangers, also, all of the tubes of heat exchangers have been replaced when the number of plugged tubes exceeds the plugging criteria based on design performance sheet. This paper describes the plugging margin evaluation mettled reflected the fouling of shell-and-tube heat exchangers, which can evaluate the thermal performance for heat exchangers, estimate the future fouling variations, and reflect the current fouling level. To identify the effectiveness of the developed method, the fouling and plugging margin evaluations were performed for a component cooling heat exchanger in a nuclear power plant.

• 대한기계학회논문집A
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• 제23권7호
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• pp.1094-1103
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• 1999

Ice-plugging of tube in nuclear power plant has been widely used for the purpose of preventing flow of the tube temporarily like a valve. Most common plugging method employs Liquid Nitrogen Gas of $-196^{\circ}C$. According to the change of tube materials and its dimension, the thermal stress caused from the application of the frozen gas can be varied. In this research, a series of experiments have been carried out to inspect the effect of tube geometry on thermal stresses induced due to ice-plugging. Two typical dimension of stainless and mild steels of 3 and 6 inch diameters were used for the experiments. Each critical spots were checked using strain rosette gages. Another inspection was made on the pressure and temperature of the fluid. It is shown that significant thermal stress level which can cause plastic deformation of failure has not been noticed in this series of experiments.

• 화약ㆍ발파
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• 제17권4호
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• pp.18-31
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• 1999

The explosive forming has been used for many year to expand tubes into tubesheets. this process has demonstrated ability to direct carefully the energy of an explosive to expand tubes into tubesheet holes without damaging the tubesheet and without causing the excessive cold work at the tube I.D. that is normally associated with mechanical expansion. The success of explosive tube expansion provided the background for the development of the explosive tube plug. The main results are as follows : (1) The optimum explosives and explosive qualities are PETN, RDX, HMS and about 18~31gr/ft of explosive plugging in nuclear steam generator. (2) Explosive plugging's thickness is 0.9~1.8mm. If groove of 0.4 mm formed in plug outside, For the hydraulic leakage is go up, explosive plugging of formed groove are applicate tube and tubrplate. (3) Sheath is designed on the polyethylene of low density, In thermal impact test of the $430^\circ{C}$, hydraulic leakage is $300kg/cm^2$. (4) About 10~60mm oxide inclusions are existed on the space of explosive plug and tube protect to the leakage.

• 한국지반공학회지:지반
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• 제12권2호
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• pp.85-94
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• 1996

말뚝직경이 개단말뚝의 폐색정도와 지지력에 미치는 영향을 규명하기 위하여 응력상태와 상대밀도의 조절이 가능한 토조와 직경이 다른 세개의 모형말뚝을 이용하여 모형말뚝실험을 수행하였다. 모형말뚝은 말뚝의 지지력 성분을 분리측정하기 위하여 직경이 다른 두개의 파이프로 만들어졌다. 실험결과에 의하면 말뚝이 완전폐색 상태로 되는 관입깊이는 말뚝직경과 지반의 상대밀도가 증가할수록 커지는 것을 알 수 있었으며, 관입비와 관내토 증분비가 동일하더라도 단위 관내토 지지력은 말뚝의 직경이 커질수록 감소하는 경향을 보였다. 그러나 기존의 지지력 산정식은 말뚝의 관입비나 폐색정도가 동일한 상태에 대하여 관내토 지지력은 말뚝의 직영에 관계없이 일정하거나 직경이 증가할수록 커지는 결과를 주고 있다. 이는 본 연구의 실험결과와 상반되는 것으로서 관내토 지지력의 산정시 말뚝의 폐색정도 뿐만 아니라 크기효과도 고려하는 것이 필요한 것으로 밝혀졌다.

• 한국지반공학회지:지반
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• 제11권4호
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• pp.25-36
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• 1995

내관과 외관이 분리된, 특별하게 제작된 모형 개단 말뚝을 상이한 방법으로 압력토조내에 설치하여 정적 압축 재하 실험을 실시하였다. 개단 말뚝 각 지지부에서의 지지력을 분리.측정하여 개단 말뚝의 지지 메카니즘과 관내토의 폐색 거동 특성을 고찰하였다. 상대밀도 49%의 모형 지반에 타격 관입된 말뚝의 관내토폐색력은 관입도중 20%정도 발휘되고 압축재하시에 대부분이 발휘되며, 토조에 작용된 구속 압력은 관내토 폐색에 크게 영향을 미치지 않았다. 그러나, 진동 관입된 말뚝의 관내토 폐색력은 관입도중에는 전혀 발생하지 않으며, 압축재하시에 약하게 형성되고, 타격 관입말뚝의 그것의 0.5~0.7배 정도가 발휘되는데 토조에 작용된 구속 압력은 관내토 폐색에 크게 영향을 미쳤다. 단위 관내토 폐색력은 극한 상태에서 최대값에 도달하지 않았다. 즉, 극한 상태에서 관내토는 파괴상태에 도달되지 않았다.

• 대한토목학회논문집
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• 제7권3호
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• pp.175-181
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• 1987

개단 강관말뚝의 선단지지력은 폐색 효과에 의하여 발생되는데 이 폐색 효과는 말뚝의 직경에 대한 관입깊이의 비 즉, 상대 관입깊이와 밀접한 관계가 있는 것으로 알려져 있다. 이에 본 연구에서는 폐색 효과를 종합적으로 평가하기 위하여 지반의 상대밀도와 모형말뚝의 상대 관입 깊이를 달리하여 재하시험을 수행하였으며 개단 말뚝의 유효직경을 축소시킬 목적으로 십자 모양의 칸막이 판을 선단에 부착한 모형말뚝에 대한 시험도 병행하였다. 그 결과로서 개단 말뚝은 말뚝의 극한 지지력을 기준으로 폐색효과를 평가할 때 말뚝 타설 지반이 단단할수록 작은 상대관입깊이에서 큰 폐색효과를 얻을 수 있으나 100%의 폐색효과는 지반의 상대밀도에 상관없이 대략 상대관입깊이 25 정도에서 발휘된다는 사실을 알았다. 그리고 칸막이 판의 설치로 인한 폐색효과의 증대는 기대하기 어려운 것으로 판단된다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 추계학술대회
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• pp.55-60
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• 2003

As operating time of heat exchangers progresses, fouling generated by water-borne deposits increases and thermal performance decreases. The fouling is known to interfere with normal flow characteristics and reduce thermal efficiencies of heat exchangers. The heat exchangers of nuclear power plants have been analyzed in terms of the heat flux and heat transfer coefficient at test conditions based on the ASME OM-S/G-Part 2 as a means of heat exchanger management. It is hard to estimate the heat performance trend and to establish the future management plan. This paper describes the fouling evaluation method which can evaluate the thermal performance for heat exchangers and estimate the future fouling variations and the plugging margin evaluation method which can reflect the current fouling level developed in this study. To develop the fouling and plugging margin evaluation methods for heat exchangers, fouling factor was introduced based on the ASME O&M codes and TEMA standards. For the purpose of verifying the two evaluation methods, the fouling and plugging margin evaluations were performed for a component cooling heat exchanger in a nuclear power plant.

• 한국소음진동공학회논문집
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• 제13권6호
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• pp.452-459
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• 2003

The characteristics of fluid-elastic instability and effects of turbulent excitations for the KSNP steam generator tubes were investigated numerically. The information for the thermal-hydraulic data of the steam generator has been obtained by using the ATHOS3-MOD1 code and the flow-induced vibration(FIV) analysis has been conducted by using the PIAT(program for Integrity assessment of SG tube) code. The KSNP steam generator has the concentrated plugging zone at the vicinity of the stay cylinder inside the SG. To investigate the cause of the concentrated tube plugging zone, the FIV analysis has been performed for various column and row number of the steam generator tubes. From the results of FIV analysis the stability ratio due to the fluid-elastic instability and vibrational amplitude due to the turbulent excitation in the concentrated plugged zone have a trend of larger values than those of the outer concentrated tube Plugging zone.