• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.219.2-219
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.220.1-220
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.222.1-222
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• 1999

• Journal of Advanced Marine Engineering and Technology
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• v.34 no.4
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• pp.491-499
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• 2010

Heat transfer performance of tube bundles have long been investigated since they were widely used. Most of previous experimental and numerical works for tube bundles were performed with tube diameter in the range of 25~51mm and Reynolds number of $8.000{\leq}Re{\leq}30.000$. Recently, tube bundles with small diameter tube collects interests since the mini-channel tube provides higher compactness. The present work aims to investigate the applicability of previous correlations available in the open literature to the tube bundles with small diameter of 1.5mm and $3.000{\leq}Re{\leq}7.000$. A commercial CFD package was used to analyze the thermal-hydraulic performance of them. The results show that the Zukauskas correlation developed for larger diameter tube and higher Reynolds number are still in good agreement with them within the discrepancy of 4.7%. The analyses also show that the Nuselt number increases with a decrease in the longitudinal pitch.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.6 no.1
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• pp.83-88
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• 2010

Domestic nuclear steam generators with Alloy 600 HTMA tubes have experienced axial cracking at eggcrate tube support plates(TSPs). The axial stress corrosion cracks were observed at the crevice between outside of tubes and eggcrate TSPs. The root cause of axial cracking was investigated by thermal hydraulic analysis and sludge distribution diagnosis. It is suggested that deposition of sludge at eggcrate TSPs could increase the outside surface temperature of tube and promote the enrichment of impurities at crevice, and thus accelerate cracking. Additionally strategy for reducing the sludge ingress to steam generators is discussed.

• Proceedings of the KSME Conference
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• 2004.11a
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• pp.353-358
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• 2004

Tracing the study of the burst test of steam generator tube, few studies have been reported to effect of external pressure acting on secondary-side in service condition. In this study the burst tests of Inconel 690TT were conducted in order to evaluate burst strength characteristics under the effect of external pressure. We obtained the result that the burst strength of Inconel 690TT increased when external pressure increased while both total circumferential elongation and uniform burst elongation were not affected. Also, according to the increased of external pressure, the size of the burst opening became smaller and the tear was getting severe.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.799-800
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• 2004

한전전력연구원에서는 한국표준형 원전 증기발생기인 시스템 80 모델의 튜브시트 상부에 침전된 슬러지를 제거하기 위한 고압 분사식 슬러지 세정장비를 개발하였다. 국내에는 영광 3,4,5,6 호기 및 울진 3,4,5,6 호기 등 총 8 기의 한국표준형 원전이 운전중에 있으나 기 사용하고 있던 증기발생기 세정 장비가 자동화가 미흡하여 작업자의 방사선 쪼임량이 과대하고 장비가 전열관에 충돌하여 전열관이 손상될 가능성이 상존하며 세정 방식이 증기발생기 가장자리인 annulus 에서 중앙의 center stay cylinder 로 향해 슬러지가 증기발생기 중앙 부분에 집중적으로 침적될 가능성이 있는 등 문제점을 해결하기 위하여 개발에 착수하였다. 개발된 증기발생기 세정 장비는 2004 년 4 월 중 울진 3 호기 증기발생기 세정 작업에 성공적으로 활용되었다.

• Proceedings of the KAIS Fall Conference
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• 2002.05a
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• pp.264-266
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• 2002

원자력 발전소의 2차계통수에는 pH를 조절하여 부식을 억제하기 위해 pH제어제로 약염기성 화학물질을 첨가하고 있다. pH 제어제로 암모니아를 사용하였으나 pH가 낮아 부식생성물이 생성되어 증기발생기의 전열관에 슬러지의 퇴적으로 전열관의 부식이 촉진되므로 pH 제어제를 에탄올아민으로 바꿈으로 슬러지의 생성 및 이동을 억제하고 있다. 그러나 에탄올아민은 암모니아와 물리화학적 성질이 다르므로, 증기발생기에 유입되는 부식생성물의 용해와 흡착, 이온성 불순물의 잠복현상에 미치는 영향이 다르다. 본 연구는 암모니아와 에탄올아민이 온도가 점차 높아짐에 따라 부식생성물에 대찬 용해와 흡착, 이온성불순물의 잠복현상에 미치는 영향을 조사하였다. 이 실험의 결과로 2차 계통수의 pH 제어제는 ETA가 암모니아보다 증기발생기 슬러지의 철산화물에 더 흡착되어 더 많이 용해되어 퇴적된 슬러지 양을 감소시키므로, 슬러지에 흡착된 불순물의 양을 감소시저 잠복 현상을 억제할 것으로 조사되었다.

• Journal of Power System Engineering
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• v.10 no.3
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• pp.38-44
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• 2006

Failure assessment of steam generator tube are very important for the integrity of energy plants. In pipes of energy plants, sometimes, the local wall thinning may result from severe erosion-corrosion damage. Recently, the effects of local wall thinning on fracture strength and fracture behavior of piping system have been well studied. In this paper, the elasto-plastic analysis is performed by FE code ANSIS on steam generator tube with wall thinning. We evaluated the failure mode, fracture strength and fracture behavior from FE analysis. It was possible to predict the crack initiation point by estimating true fracture ductility under multi-axial stress conditions at the center of the thinned area.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.49-54
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• 2003

Most of the operating pressurized water reactors (PWRs)has chosen Inconel 600 as steam generator tubing. The long-term operation of steam generators showed that the use of this material induced localized corrosion damages. The current trend is using Inconel 690 as a tube material for the replacement steam generators. Based on the current trend, we have chosen Inconel 690 for the advanced Power Reactor 1400 (APR1400) steam generator tube material. In this paper, we examined the technical consideration in this modification: the effect of chemical composition, thermal conductivity, corrosion resistance and wear characteristics