• 한국생산제조학회지
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• 제8권4호
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• pp.123-129
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• 1999

Although type 316 stainless steel is widely used such as in reactors of petrochemical plants and pipes of steam power plants and s attracting attention as potential basic material for the fast breeder reactor structure alloys in nuclear power plants and is attracting attention as potential basic material for the fast breeder reactor structure alloys in nuclear power plants the effect of precipitates which form during the long term exposure at service temperature on creep properties is not known sufficiently. In this study to investigate the creep properties and the influence of prior aging on the microstructure to form precipitates specimens were first solutionized at 113$0^{\circ}C$ for 20 minutes and then aged for different times of 0 hr, 100 hrs, 1000 hrs and 2200 hrs at 75$0^{\circ}C$ After heat treatments tensile tests both at room temperature and $650^{\circ}C$ and constant load creep ruptuere tests were carried out.

• Earthquakes and Structures
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• 제1권3호
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• pp.253-267
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• 2010

A novel simple approach is presented for the seismic analysis of continuous buried pipelines subject to fault ruptures. The method is based on the minimization of the total dissipated energy during faulting, taking into account the basic factors that affect the problem, namely: a) the pipe yielding under axial and bending load, through the formation of plastic hinges and axial slip; b) the longitudinal friction across the pipe-soil interface; c) the lateral resistance of soil. The advantages and drawbacks of the proposed method are highlighted through a comparison with previous approaches, as well as with finite element calculations accounting for the 3D kinematics of the pipe-soil-fault systems under large deformations. Parametric analyses are also provided to assess the relative influence of the various parameters affecting the problem.

• 대한금속재료학회지
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• 제49권4호
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• pp.275-280
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• 2011

This paper focuses on reliability prediction of long-term creep strength for Modified 9Cr-1Mo steel (Gr. 91) which is considered as one of the structural materials of next generation reactor systems. A "Z-parameter" method was introduced to describe the magnitude of standard deviation of creep rupture data to the master curve which can be plotted by log stress vs. The larson-Miller parameter (LMP). Statistical analysis showed that the scattering of the Z-parameter for the Gr. 91 steel well followed normal distribution. Using this normal distribution of the Z-parameter, the various reliability curves for creep strength design, such as stress-time temperature parameter reliability curves (${\sigma}$-TTP-R curves), stress-rupture time-reliability curves (${\sigma}-t_{r}-R$ curves), and allowable stress-temperature- reliability curves ([${\sigma}$]-T-R curves) were reasonably drawn, and their results are discussed.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.2953-2959
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• 2021

A new practical modeling of the Norton's power law creep is proposed and implemented to analyze the high temperature behaviors of Alloy 690 SG tube material. In the model, both the stress exponent n and the rate constant B are simply treated as the temperature dependent parameters. Based on the two-step optimization procedure, the temperature function of the rate constant B(T) was determined for the data set of each B value after fixing the stress exponent n value by using the prior optimized function at each temperature. This procedure could significantly reduce the numerical errors when using the power law creep equations. Based on the better description of the steady-state creep rates, the experimental rupture times could also be well predicted by using the Monkman-Grant relationship. Furthermore, the difference in tensile strengths at high temperatures could be very well estimated by assuming the imaginary creep stress related to the given strain rate after correcting the temperature effects on the elastic modulus.

• 터널과지하공간
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• 제31권1호
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• pp.52-65
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• 2021

본 연구에서는 멕시코시티 외곽에 있는 프로판 저장기지인 PEMIX 터미널에서 발생한 프로판 누출에 따른 증기운 폭발을 분석하였다. 누출된 4750 kg의 프로판에 대한 TNT 등가량은 9398 kg으로 평가되었다. 폭원으로부터 40~400 (m) 떨어진 지점에서의 최대과압, 양의 압력 지속시간, 충격량과 같은 폭발변수를 TNT 등가법과 다중에너지법을 적용하여 구하였다. 폭발 변수들을 이용하여 구한 프로빗 함수를 적용하여 폐 손상, 고막 파열, 머리 충격, 전신 전위 충격으로 인한 손상 확률을 평가하였다. 고려한 모든 거리에서 다중에너지법을 이용하여 구한 최대과압이 TNT 등가법을 적용하여 구한 최대과압보다 큰 것으로 나타났으나, 200 m 이후 지점부터는 큰 차이가 없는 것으로 평가되었다. 다중에너지법에 의해 구해진 최대과압을 적용하여 구조물 손상 범위를 평가한 결과 폭원으로부터 100 m 이내에 있는 구조물의 경우 완전히 붕괴될 것으로 예측되고, 400 m 떨어진 구조물의 유리창도 거의 파손될 것으로 추정되었다. 폐 손상에 의한 사망 확률은 충격파 진행방향으로 위치하고 있는 인체의 자세에 따라 달라지는 것으로 나타났으며, 인체 주변에 반사면이 있는 경우 사망 확률이 가장 큰 것으로 평가되었다. 충격파가 폐 손상, 고막 파열, 머리 충격, 전신 전위 충격에 미치는 영향을 평가한 결과 전신 전위 충격 < 폐 손상 < 고막파열 < 머리 충격 순으로 영향을 미치는 것으로 나타났다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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• pp.291-295
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• 1996

In CANDU reactor, each pressure tubes contain twelve fuel bundles and provide the inlet and outlet for the primary coolant. If a leak develops in the pressure tube, it is detected by Annulus Gas System which contains circulating dry $CO_2$ gas. Since the leaks caused by the flaws are resulted in pressure tube break, establishment of flaw assessment method is very significant in view of the fracture mechanics. In this paper, various criteria for assessing the flaws are presented to prevent the tube rupture and ensure the integrity of reactor operating.

• 동력기계공학회지
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• 제9권4호
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• pp.96-101
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• 2005

Magnesium alloys have been widely used for many structural components of automobiles and aircraft because of high specific strength and good cast ability in spite of hexagonal closed-packed crystal structure of pure magnesium. In this study, uniaxial tension tests at high temperature and creep tests are done in order to investigate the characteristics of high temperature and mechanisms for creep deformation of AZ31 Mg alloy. Yield stress and ultimate tensile stress decreased with increasing temperature, but elongation increased from results of uniaxial tension test at high temperature. The apparent activation energy Qc, the applied stress exponent n and rupture life have been determined during creep of AZ31 Mg alloy over the temperature range of 473K to 573K and stress range of 23.42 MPa to 93.59 MPa, respectively, in order to investigate the creep behavior. Constant load creep tests were carried out in the equipment including automatic temperature controller, whose data are sent to computer. At around the temperature of $473K{\sim}493K$ and under the stress level of $62.43{\sim}93.59%MPa$, and again at around the temperature of $553K{\sim}573K$ and under the stress level of $23.42{\sim}39.00MPa$, the creep behavior obeyed a simple power-law relating steady state creep rate to applied stress and the activation energy for the creep deformation was nearly equal, respectively, and a little low to that of the self diffusion of Mg alloy including aluminum. Also rupture surfaces at high temperature have had bigger dimples than those at lower temperature by SEM.

• Corrosion Science and Technology
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• 제22권1호
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• pp.44-54
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• 2023

The rupture disk corrosion test (RDCT) method was recently developed to evaluate stress corrosion cracking (SCC) and was found to have great potential for the real-time detection of SCC initiation in a high temperature and pressure environment, simulating the primary water coolant of pressurized water reactors. However, it is difficult to directly measure the stress applied to a disk specimen, which is an essential factor in SCC initiation. In this work, finite element analysis (FEA) was performed using ABAQUS^TM to calculate the stress and deformation of a disk specimen. To determine the best mesh design for a thin disk specimen, hexahedron, hex-dominated, and tetrahedron models were used in FEA. All models revealed similar dome-shaped deformation behavior of the disk specimen. However, there was a considerable difference in stress distribution in the disk specimens. In the hex-dominated model, the applied stress was calculated to be the maximum at the dome center, whereas the stress was calculated to be the maximum at the dome edge in the hexahedron and tetrahedron models. From a comparison of the FEA results with deformation behavior and SCC location on the disk specimen after RDCT, the most proper FE model was found to be the tetrahedron model.

• 에너지공학
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• 제21권1호
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• pp.75-80
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• 2012

본 논문은 원자력발전소의 대형탱크 또는 배관파단에 따른 격실의 침수분석을 수행함에 있어 최적평가방법을 개발하여 원전에 실제로 적용하는 방법에 관한 논문을 작성하는데 목적이 있다. 주급수관파단사고 분석을 위해 RETRAN 전산코드를 사용하였다. 유출수 질량유량을 계산하는데 있어서 주급수제어밸브가 계통설계에 의거 원자로정지 후 5.0초 만에 닫히는 것으로 모델링하여 분석하였다. 출력 70% 운전시 방출유량이 가장 높은 것으로 나타났다. 방출 질량유량을 가지고 침수위를 계산한 결과 주급수관 격실의 최대 침수위는 1.43m로서 이는 안전성기기가 설치된 위치보다 낮아 원전의 안전정지에 미치는 영향이 없는 것으로 나타났다.

• 에너지공학
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• 제24권2호
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• pp.115-119
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• 2015

Pipe vibration caused great threat to the safety in production. Strong pipeline vibration will line accessories, especially the joints and pipe fittings etc. pipe joints loosening and rupture, causing serious accidents. By the action of the compressor constant fluid flow within the pipe, this process produces pulsating fluid flow may cause vibration of the pipe, thereby reducing the efficiency of the pipeline, structural vibration induced fatigue, thereby resulting in even piping structural damage. This paper studies on the vibration problems caused by fluid, by analyzing the causes of pipeline vibration and factors affecting pipeline vibrations, FEM (Finite Element Method) analysis of modal and enforced vibration.