• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2011.04a
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• pp.693-699
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• 2011

The outermost SG tubes have more structural problems than inside tubes. Many studies have used a uniform added mass coefficient for all of the SG tubes during the FIV analysis. The purpose of this study is to find out the added mass coefficients for each tube in a cylindrical shell. When a number of tubes are increased, added mass coefficients are also increased. And added mass coefficients at outermost tubes are less than those of inside tubes. According to gap changes between outermost tube and cylindrical shell, added mass coefficients are decreased with increasing the gap. When the gap has very large value, it shows that the added mass coefficient is asymptotically converged to the value of the tube array in a free fluid field.

• Proceedings of the KWS Conference
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• 2007.11a
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• pp.196-198
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• 2007

Laser cladding technology was studied as a method for upgrading the present repair procedures of damaged tubes in a nuclear steam generator and Doosan subsequently developed and designed a new Laser Cladding Repair System. One of the important features of this newly developed Laser Cladding Repair System is that molten metal can be deposited on damaged tube surfaces using a laser beam and filler wire without the need to install sleeves inside the tube. Laser cladding qualification tests on the steam generator tube material, Alloy 600, were performed according to ASME Section IX.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.741-746
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• 1995

일체형원자로는 노심, 증기발생기, 가압기, 펌프 등 1차측 주기기들을 하나의 압력용기 안에 모두 포함하고 있고 또 1차측 냉각재가 원자로 안에서만 순환하므로 기존의 분리 형에 비해 구조특성상 상당히 다른 설계개념이 필요하다. 본 연구에서 개발중에 있는 일체형 열병합원자로에서 채택한 설계개념은, 먼저 증기발생기는 많은 수의 전열관들이 나사선처럼 노심지지원통을 감고 올라가는 일체형 관류식 나선형을 사용하였으며, CEDM은 지진하중과 같은 동적하중에 의한 영향을 최소화하기 위하여 원자로용기 외부로의 돌출부분을 최소화하는 설계개념을 채택하였다. 또한 가압기는 별도의 부품없이 원자로용기 헤드의 빈공간을 활용한 자기가압방식으로 대체하였고 냉각재 펑프는 Canned Motor Pump를 원자로벽에 직접 부착하는 개념을 사용하였다. 본 논문에서는 예비개념설계된 일체형 신형원자로의 기계구조설계상의 특징들을 설명하고 앞으로의 연구방향을 간략히 소개한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.597-602
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• 1995

원자력 발전소 증기발생기 전열관 재료인 합금 600의 대체재료로써 설계된 합금 690의 내식성의 향상을 위해서 염소 이온이 다량 포함된 환경에서의 부식 저항성을 크게 향상시킨다고 보고된 Mo을 첨가하여 부식 및 기계적 특성에 미치는 영향을 알아보았다. 미세조직상 Mo를 첨가함에 따라 기지에 미세한 석출물이 석출되어 입자의 미세화를 얻을 수 있었으며 연신율의 감소없이 항복 강도, 인장 강도 및 경도의 향상을 얻을 수 있었다. 공식 저항성은 Mo의 첨가량이 증가함에 따라 부식 속도가 감소하였다. 양극 분극 시험에서도 5$0^{\circ}C$, 3.5wt% NaCl 용액과 0.5N HCl 용액 모두에서 Mo의 함량이 증가할수록 부동태화 전류 밀도 및 임계 부동태화 전류 밀도가 감소하여 전반적으로 현저한 내식성의 향상을 관찰할 수 있었다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2003.05a
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• pp.670-676
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• 2003

To investigate the group plugging effect the fluid-elastic instability analysis has been performed on various column and row number of the KSNP steam generator lutes. This study compares the stability ratio of the plugged tube with that of the intact one. The information on the thermal-hydraulic data of the steam generator have been obtained by using the ATHOS3-MOD1 code with and without the thermal energy transfer at the plugged region. Both of the boundary conditions of hot-leg temperature and feedwater mass flow rate are fixed for this investigation. From the results of this study the stability ratios inside the group plugging zone are decreased slightly. At the outside of group plugging zone, however, most of the stability ratios tend to be increased.

• Proceedings of the KIEE Conference
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• 2000.07b
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• pp.831-833
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• 2000

In this paper, a numerical analysis algorithm of eddy current testing(ECT) for heat exchanger tube with axi-symmetric defects using finite element method(FEM) is presented. In the ECT FEM analysis, we used trianglular and rectangular elements for exact signal of ECT for variable shape of defects. This paper presents a systematic and efficient numerical analysis algorithm for ECT. We employ the LU decomposition and Cholesky method for solving the system matrix. This numerical analysis algorithm is effectively applied to heat exchanger tube with defects.

• Proceedings of the Korean Society of Machine Tool Engineers Conference
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• 1999.05a
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• pp.163-169
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• 1999

Residual stresses causing stress corrosion cracking (SCC) of thin-walled steam generator U tubes were investigated. The residual stresses were measured by hole drilling methods, and the applied stresses resulting from the internal pressure and the temperature gradient in the steam generator were estimated theoretically. In U-bent regions, the residual stresses at extrados were induced with compressive stress(-), and its maximum value reached -319MPa in axial direction at $\phi$= $0^{\circ}$ in position. Maximum tensile residual stress of 170MPa was found to be at the flank side at position of $\phi$= $90^{\circ}$, i.e., at apex region. Hoop stress due to the pressure and temperature differences between primary and secondary side were analyzed to be 76 MPa and 45 MPa, respectively.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.13 no.12
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• pp.1214-1222
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• 2001

The present study investigated the effect of diameter and length on the absorption performance of a vertical falling film type absorber using $LiBr-H_2$O solution of 60 wt%. The parameters were diameter of absorber (17.2, 23.4, 31.1 mm), length of absorber (771, 1150, 1528 mm), and film Reynolds numbers (50, 70, 90, 110, 130, 150). As the diameter of the absorber was increased, the absorption mass flux, Sherwood number, heat flux, and heat transfer coefficient were increased, in which Sherwood number and heat transfer coefficient were increased up to 13% and 30% respectively. As the length of the absorber was increased, the total absorption rate and heat transfer coefficient were increased by 37% and 35% respectively, while the absorption mass flux was decreased.

• Proceedings of the KSME Conference
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• 2000.04a
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• pp.19-24
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• 2000

Stress corrosion crack growth is simulated after assuming a small axial surface crack inside a S/G tube. Internal pressure and residual stresses are considered as applied forces. Stress intensity factors along crack front, variation of crack shape and crack growth rate are obtained and discussed. It is noticed that the aspect ratio of the crack is not depend on the initial crack shape but depend on the residual stress distribution.

• Journal of the Korean Society of Safety
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• v.18 no.4
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• pp.16-22
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• 2003

Generally the rupture of steam generator tubes proceeds from significant plastic deformation before failure. In this study, the burst pressures of damaged steam generator tubes were calculated from the plastic instability analysis with the finite element method. Two wear types, flat and circumferential types were considered. An equation for the burst pressure was proposed by using the strength reduction factor and the Svensson equation. The analysis results were compared with the experiment data from published references and they showed a good agreement with the experiment data.