• Journal of Advanced Marine Engineering and Technology
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• v.16 no.3
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• pp.42-50
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• 1992

다공성 물질이 충전된 밀폐용기 내에서 수용성 이원혼합용액($H_2O{+}NaCl$)이 수평한 상부전열면으로 부터 동결될 때 혼합용액의 초기농도, 액체의 과열 및 다공성물질의 입자직경 크기가 온도와 농도분포에 미치는 영향을 실험하였으며, 동결이 진행됨에 따라 이동하는 고액상 혼합영역의 계명위치를 측정하였다. 다공성물질은 평균직경이 2.85mm, 6mm인 구형의 유리구슬을 이용하였다. 수용성 혼합용액의 초기농도는 공융농도도 이하로 하였으며 상부 전열면은 공융온도 이하로, 하부전열면은 액상선온도 이상으로 유지하여 동결 실험한 결과 상부 전열면으로 부터 고체 영역, 고액상혼합영역, 액체영역으로 구분되었다. 액체의 초기농도가 5%인 경우 과냉현상이 관찰되었으나 10%, 15%인 경우 액체온도는 액상선 온도보다 더 높았다. 용액의 초기농도를 감소시킬수록 고체와 고액상혼합영역의 범위는 증대되었으며 고액상혼합영역과 고체영역의 계면은 더욱 강해진 자연대류에 의하여 2차원성이 증가된 형상을 보였다. 용액의 자연대류는 다공성물질의 직경이 클수록 증가되었으며 계면에서의 제융해현상은 관찰되지 않았다.

• Proceedings of the Korea Information Processing Society Conference
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• 2001.04b
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• pp.751-754
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• 2001

열교환기(Heat Exchanger)는 원전 운영에 핵심적인 설비이다. 따라서 열교환기 전열관의 건전성 유무를 판단키 위해 정기적으로 비파괴검사의 일종인 와전류검사(ECT, Eddy Current Testing)를 수행하고 있다. 이러한 와전류검사 공정은 크게 3가지로 분류할 수 있다. 첫 번째는 전열관 상태검사를 위한 신호데이터 취득공정이고, 두 번째는 취득된 신호를 판독하여 전열관의 건전성 여부를 진단하는 평가공정, 마지막으로 평가공정에서 발생하는 방대한 데이터를 토대로 추이분석 자료를 제공할 수 있는 공정이 필요하다. 본 논문에서는 세 번째 공정에서 필요한 열교환기 Tubesheet를 사용자 정의에 따라 자동으로 구현할 수 있는 기능을 정의하고, 평가공정에서 발생한 데이터를 직접 Tubesheet상에 Mapping 처리하여 시각적으로 전열관 상태를 확인할 수 있는 프로그램 구현방법을 제시한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.110-117
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• 1997

Alloy 690 제1열 시제 전열관을 U 굽힘 가공할 시 전열관에 도입된 표면 잔류응력 및 굽힘 단면에서 치수변화 (벽두께, 진원도)를 위치별로 측정하여 평가하였다. 외측호(extrados)의 표면 잔류응력은 $\psi$=0$^{\circ}$에서 축 방향 응력이 -319 MPa (압축)로 가장 높았으며, 내측호(intrados)는 $\psi$=0$^{\circ}$, 160$^{\circ}$ 위치인 천이영역 부관에서 응력 변화가 크게 되는 경향을 보였다 측면(flank)은 인장 잔류응력으로 $\psi$=90$^{\circ}$(apex)에서 최대 190 MPa 로 축방향 응력으로 나타났다. 잔류응력치는 벽두께 보다는 진원도 변화와 일치되어 나타났으며, 시제 전열관의 벽두께 및 진원도는 ASTM의 치수 허용치 내에 포함되는 것으로 평가되었다. 잔류응력 측정은 스트레인 게이지를 이용한 구멍뚫기 방법 (Hole-Drilling Method)을 사용하였다.

• Journal of the Korean Magnetics Society
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• v.15 no.5
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• pp.292-297
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• 2005

Steam generator of a nuclear power plant has important rolls for the heat transfer and the isolation of radioactive materials. So bursting of the steam generator tube is directly related to the accident of nuclear power plants. Incone1600 has been used for the steam generator tube material. The material shows non-magnetic and metallic properties, eddy current NDT method has been employed for defects detection. In this work, a differential type of eddy current probe was developed to improve resolution of defect detection. To verify properties of the developed differential type eddy current probe, we have made reference material with SUS304 which has similar magnetic and electrical properties of Inconel600. Using the developed differential type eddy current probe, we can detect defect size of 0.25 mm in diameter and 0.2 mm in depth (volume of $1{\times}10^{-3}\;mm^3$) with the reference material.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.40 no.11
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• pp.737-744
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• 2016

The printed circuit heat exchanger (PCHE) is regarded as a promising candidate for advanced heat exchangers for the next-generation supercritical $CO_2$ power generation owing to its high compactness and rigid structure. In this study, an innovative type of PCHE, in which the channel sizes for the heat source fluid and heat sink fluid are different, is considered for analysis. The thermal performance of the PCHE, with supercritical $CO_2$ as the working fluid, is numerically analyzed. The results have shown that the thermal performance of the PCHE decreases monotonically when the channel size of either the heat source channel or the heat sink channel, because of the decreased flow velocity. On the other hand, the thermal performance of the PCHE is found to be almost independent of the spacing between the channels. In addition, it was found that the channel cross sectional shape has little effect on the thermal performance when the hydraulic diameter of the channel remains constant.

• Journal of Energy Engineering
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• v.21 no.4
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• pp.362-372
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• 2012

The steam generator tubes of nuclear power plants are pressure boundaries, and if tubes are leaked, the coolant with the radioactive materials was flowed out from the primary system to the secondary system and polluted the plant and the air. Recently most crack defects of tubes are stress corrosion cracks and these defects are located in expansion transition area, sludge pile-up region, and U-bend area. The most effective one of crack initiation factors in expansion transition area and U-bend area is the residual stress. According to the experiences of Korea standard nuclear plants(Optimized Power Reactor-1000), they had the stress corrosion cracks at the tube expansion transition area in early operating stage and especially lots of circumferential cracks were occurred. Therefore in this study, the distributions and conditions of residual stresses by tube expansion methods were compared and the dominant reason of a specific direction was examined.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.13 no.12
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• pp.5676-5683
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• 2012

In this study, numerical analysis was performed on three shapes of heat transfer plates (chevron, wave and dimple type), which are currently used as fillers of cooling towers. Results show that heat transfer rates per consumed power were larger for enhanced plates as compared with that of plain plate. Highest heat transfer coefficient was obtained for wave shape followed by chevron and dimple shape. For wave shape, cross corrugations induced significant mixing of fluids, which enhanced the heat transfer. Friction factor yielded a similar trend with the heat transfer coefficient. However, heat transfer rate and pressure drop per sheet was the largest for chevron shape, due to the largest heat transfer area per sheet.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.34 no.7
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• pp.697-702
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• 2010

An enthalpy exchanger in which heat and moisture transfer occur between the indoor and outdoor air operates at various outdoor conditions. In this study, the effect of the outdoor-air temperature and humidity on the performance of an enthalpy exchanger was experimentally investigated. An apparatus was specially-made to accurately measure the incoming and outgoing dry- and wet-bulb air temperatures as well as the flow rates. Tests were conducted in constant-temperature and constant-humidity chambers at different outdoor temperatures and humidities. It is shown that the effectiveness of latent-heat exchange increases as the relative humidity increases; further, this effect exhibited minimal dependence on the absolute humidity. However, the effectiveness of sensible-heat exchange is independent of both temperature and humidity

• Journal of Energy Engineering
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• v.12 no.2
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• pp.84-92
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• 2003

A one-dimensional thermal-hydraulic analysis computer program is developed for thermal sizing of a copper bonded steam generator. It is assumed that the conduction heat transfer of copper region between the hot side and the cold side tube is one-dimensional and its thermal resistance is derived as a function of a tube pitch. The flow regions of the water/steam side are divided into four regions: subcooled, saturated, film boiling, and super-heated. The number of tube selected ranges from 250 to 3500 and the pitch to tube diameter (P/D) ratios are 1.4, 1.6 and 1.8 for the parametric study calculation. The calculation results showed that when the number of tube was 2500, the length of the heating tube was about 12 m and the outside diameter of the steam generator was about 3 m. If the P/D ratio increases, the thermal resistance of copper component also increases, however the length of the heating tube is not so much increased.

• Journal of the Korean Society for Nondestructive Testing
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• v.21 no.5
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• pp.501-509
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• 2001

For the enhancement of ECT reliability on the primary water stress corrosion cracks of nuclear steam generator tubes, of which the occurrence is on the increase, it is important to comprehend the signal characteristics on crack morphology and to select an appropriate probe type. In this paper, the sizing accuracy and the detectability for the inner wall axial cracks of tubes were quantitatively evaluated using the following specimens: the electric discharge machined notches and the corrosion cracks which were developed on the operating steam generator tubes. The difference of eddy current signal characteristics between pancake and axial coil were also Investigated. The results obtained from this study provide a useful information for more precise evaluation on the inner wall axial tracks oi stram generator tubes.