• Journal of Advanced Marine Engineering and Technology
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• 제25권2호
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• pp.345-345
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• 2001

This paper was studied on the characteristics of galvanic corrosion and its protection on heat exchanger tube plate in the sea water. In this paper, behavior of pitting corrosion of Ni-al bronze connected with Ti tube was measured af flow velocity of 0 m/s and 2.4 m/s. To protect galvanic corrosion, the protection characteristics of Ni-Al bronze connected with Ti tube by Zn-base alloys galvanic anode and hexagonal nylon insert was investigated. Main results obtained asre al follows: 1) The galvanic corrosion of Ni-Al bronze connected with Ti-tube is more active than single Ni-al bronze. 2) As the circuit resistance increase under the cathodic protection employing Zn-base alloys galvanic anode, Ni-al bronze connected with Ti tube is cathodically unpolarized. 3) The corrosion of Ni-Al bronze connected with Ti tube by nylon insert controls approximately 73% than not nylon insert.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.381.2-381
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• 2002

• 에너지공학
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• 제21권4호
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• pp.362-372
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• 2012

원전의 증기발생기 전열관은 압력경계 부위로 결함발생으로 인한 누설 시 방사능물질을 함유한 1차 계통의 냉각수가 2차 계통으로 새어나와 발전소 및 대기를 오염시키게 된다. 근래에 전열관의 균열결함은 대개 응력 부식균열이며 전열관의 확관부위, 슬러지 침적부위 그리고 U-bend 등에서 발생한다. 확관부위 및 U-bend 등에서의 균열발생인자 중 가장 영향을 미치는 인자는 잔류응력이다. 폭발확관법이 적용된 한국표준형원전(OPR-1000)의 운전경험에 따르면, 증기발생기 전열관 확관부위에서 가동 초기부터 응력부식균열이 발생해 왔으며, 특히 원주방향 균열이 대량 발생하고 있다. 따라서 본 연구에서는 확관방법에 따른 잔류응력의 분포 및 상태를 비교하였으며, 특정 방향이 우세한 원인을 살펴보았다.

• 수산해양기술연구
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• 제20권2호
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• pp.137-142
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• 1984

수평관내 증기분무류의 응축열전달에 관하여 실험을 행하고 상당 Reynolds수를 근거로한 열전달효과와의 비교에서 그 결과를 요약하면 다음과 같다. 1. 관내 응축증기 분무류일 경우의 벽면전단응력의 식은 다음과 같이 쓸 수 있다. root($\tau$하(0)/$\tau$하(0v))=1+1.46X 하(tt) 상(0.20). 2. 분무류의 응축열전달효과가 상당 Reynolds수에 의한 값보다 대체로 낮게 나타난 이유는 관내 반경 및 길이방향의 불균일한 액막형성에 의한 Reynolds수 측정값의 차이 때문이다. 3. 분무류의 응축열전달효과에 의한 N sub(u)의 값은 다음과 같다. N 하(u)=1.08$\times$[{$\rho$ 하(l) d/$\mu$ 하(l)}/{$\delta$+(2.5/P 하(rl)) ln(y 하(i)/$\delta$)}]$\times${$\tau$ 하(0)/ $\rho$ 하(l)} 상(1/2)

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2006년도 추계학술대회 논문집
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• pp.361-362
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• 2006

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.513-522
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• 2013

The ODSCC detected in the TSP position of Ulchin 3&4 SGs are typical ODSCC of Alloy 600MA tubes. The causative chemical environment is formed by concentration of impurities inside the occluded region formed by the tube surface, egg crate strips, and sludge deposit there. Most cracks are detected at or near the line contacts between the tube surface and the egg crate strips. The region of dense crack population, as defined as between $4^{th}$ and $9^{th}$ TSPs, and near the center of hot leg hemisphere plane, coincided well with the region of preferential sludge deposition as defined by thermal hydraulics calculation using SGAP computer code. The cracks developed homogeneously in a wide range of SGs, so that the number of cracks detected each outage increased very rapidly since the first detection in the $8^{th}$ refueling outage. The root cause assessment focused on investigation of the difference in microstructure and manufacturing residual stress in order to reveal the cause of different susceptibilities to ODSCC among identical six units. The manufacturing residual stress as measured by XRD on OD surface and by split tube method indicated that the high residual stress of Alloy 600MA tube played a critical role in developing ODSCC. The level of residual stress showed substantial variations among the six units depending on details of straightening and OD grinding processes. Youngwang 3&4 tubes are less susceptible to ODSCC than U3 and U4 tubes because semi-continuous coarse chromium carbides are formed along the grain boundary of Y3&4 tubes, while there are finer less continuous chromium carbides in U3 and U4. The different carbide morphology is caused by the difference in cooling rate after mill anneal. There is a possibility that high chromium content in the Y3&4 tubes, still within the allowable range of Alloy 600, has made some contribution to the improved resistance to ODSCC. It is anticipated that ODSCC in Y5&6 SGs will be retarded more considerably than U3 SGs since the manufacturing residual stress in Y5&6 tubes is substantially lower than in U3 tubes, while the microstructure is similar with each other.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2002년도 추계학술대회논문초록집
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• pp.390.1-390
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• 2002

In this study, we investigate the plugging effect on the CE type steam generator tube. The natural frequency and mode shape will be changed due to decrease of the effective mass distribution along the tube. We compared the variation of stability ratio for plugged tube with that fur unplugged one. The natural frequency increased because of removing the cooling water inside the steam generator tube, but the stability ratio decreased inversely because of changing the vibrational mode shape. We also investigated the turbulent excitation effect.

• 한국산학기술학회논문지
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• 제16권10호
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• pp.6641-6646
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• 2015

배열회수 보일러의 전열관군은 외부에 가스터빈에서 나온 고온의 배기가스가 흐르게 된다. 이러한 유체의 흐름으로 인해 전열관군에서 시간변화에 따라 양력의 변동이 발생하는데 이에 따라 유동 유발 진동이 발생한다. 이러한 진동이 배열회수 보일러의 전열관군에서 파손을 야기할 수 있어서 열교환기의 구조적 안정성을 위해 열교환기의 전열관군에서 유동 유발 진동 특성을 규명할 필요가 있다. 일반적인 열교환기 전열관군에서 유동 유발 진동에 관한 실험적 연구는 기존에 많이 진행되어 오고 있으며 유동 유발 진동에 대한 무차원 PSD(Power Spectral Density) 함수를 무차원 주파수인 Strouhal 수, fU/U의 함수로 실험적 결과들이 도출되어 있다. 본 연구는 열교환기 전열관군에서 유동 유발 진동에 관한 기존의 실험적 연구들의 결과를 전산유체해석을 통해 검증하고 배열회수 보일러의 전열관군의 유동 유발 진동 특성에 적용하기 위한 기반을 마련하는 것을 목적으로 한다. 이러한 것을 위해 기존 연구에서 실험에 사용한 전열관군에서 비정상 상태 유동해석을 수행하여 전열관군에서의 양력 변화 특성을 살펴보았다. 또한 전열관군에서 양력 변동 특성으로부터 유동 유발 진동에 따른 PSD 특성 결과를 도출하여 기존의 연구들과 비교를 통해 전열관군에서의 PSD 특성을 정립하였다.

• 한국기계가공학회지
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• 제18권12호
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• pp.52-58
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• 2019

This study numerically analyzed the icing process in a U-shaped pipe exposed to the outside by considering the mushy zone of freezing water. Numerical results showed that the flow was pulled outward due to the U-shaped bend in the freezing section exposed to the outside, which resulted in the ice wave formation on the wall of the bended pipe behind. At the same time, the formation of a corrugated ice layer became apparent due to the venturi effect caused by the ice. The factors affecting the freezing were investigated, including the change of the pipe wall temperature, the water inflow velocity, and the pipe bend spacing. It was found that, as a whole, the thickness of the freezing layer increased as the pipe wall temperature decreased. It was also found that the freezing layer became relatively thin when the inflow rate of water was increased, and that the spacing of the pipe bends did not significantly impact the change in the freezing layer.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.889-896
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• 2020

The vertically inverted U-tube steam generator (UTSG) is widely used in the pressurized water reactor (PWR). The reverse flow behavior generally exists in some U-tubes of a steam generator (SG) under both single- and two-phase natural circulations (NCs). The behavior increases the flow resistance in the primary loop and reduces the heat transfer in the SG. As a consequence, the NC ability as well as the inherent safety of nuclear reactors is faced with severe challenges. The theoretical models for calculating single- and two-phase flow pressure drops in U-tubes are developed and validated in this paper. The two-phase reverse flow characteristics in two types of SGs are investigated base on the theoretical models, and the effects of the U-tube height, bending radius, inlet steam quality and primary side pressure on the behavior are analyzed. The conclusions may provide some promising references for SG optimization to reduce the disadvantageous behavior. It is also of significance to improve the NC ability and ensure the PWR safety during some accidents.