• 비파괴검사학회지
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• 제13권1호
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• pp.40-45
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• 1993

The steam generator tubes of the nuclear power plant should be inspected using eddy current techniques. Recently the crack-like defects become a major concern for the integrity of the steam generator tubes. These defects could be detected by the MRPC(Motorized Rotating Pancake Coil) method, not by the conventional bobbin coil method. In this paper it has been attempted to estimate the length of the cracks at the tube expansion region using of MRPC technique. The lengths of both axial and circumferential cracks show a tendency of overestimation compared to the real lengths. As the depths of the defects decrease from 100% through 50% of the wall thickness, the error of the length estimation is increased.

• 대한기계학회논문집A
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• 제31권5호
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• pp.586-593
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• 2007

This paper proposes closed-form plastic limit load solutions for elbow with local wall thinning at extrados under internal pressure. This work was performed using 3-dimensional, small strain FE analyses based on elastic-perfectly plastic materials. The wide range of elbow and local wall thinning geometries are considered. For systematic analyses for effect of axial thinning extent on limit loads, two limiting cases are considered; a sufficiently long thinning, and the circumferential part-through surface crack. Then, the closed-form plastic limit load solutions for intermediate thinning are obtained by using result of two limiting cases. The effect of axial thinning extent for elbow on plastic limit load is highlighted by comparing with that for straight pipes. Although the proposed limit load solutions are developed for the case when local wall thinning exist in the center of elbow, it is also shown that they can be applied to the case when local wall thinning exists anywhere within elbow.

• 수산해양기술연구
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• 제36권2호
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• pp.147-154
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• 2000

실온 대기 중에서 탄소강배관(STS370)의 피로시험을 행하였다. 배관에는 외부결함을 인공적으로 상정하여, 피로균열진전 및 관통의 거동, 균열형상, 누설 및 파단수명, 균열개구변위를 실험과 이론의 양면으로부터 비교·검토하였다. 특히, 배관의 벽두께 관통후에 있어서의 응력확대계수를 평가하기 위하여 새로운 식을 제안하였다. 피로균열이 관벽을 관통하기 전에 있어서는 판모델에 의한 Newman-Raju의 응력확대계수 평가식을 이용하므로서 aspect비와 누설수명 등 관통전의 피로균열성장거동을 평가할 수 있음을 나타내었다. 또한, 피로균열이 관벽을 관통한 후에 있어서는 본 논문에서 제안한 배관모델에 의한 응력확대계수의 평가식을 이용하여 관통후의 균열형상, 파단수명 및 균열개구변위 등 관통후의 피로균열성장거동을 평가하였다.

• 대한기계학회논문집A
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• 제35권10호
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• pp.1329-1335
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• 2011

본 논문에서는 3 차원 유한요소 한계해석을 기반으로 하여 인장하중, 굽힘 모멘트 및 내압이 작용하는 원주방향 경사관통균열을 갖는 배관의 소성한계 하중값을 제안하였다. 본 연구에서 수행된 유한요소 모델 및 해석 방법은 이상화된 관통균열을 갖는 배관의 소성한계 하중값을 구하기 위한 기존의 이론식과의 비교를 통해 타당성을 입증하였다. 또한, 경사균열이 소성한계 하중값에 미치는 영향을 정량화하기 위하여 대규모의 3 차원 유한요소 해석을 통해 이상화된 관통균열 배관의 소성한계 하중값으로부터 경사관통균열 배관의 소성한계 하중값을 구할 수 있는 새로운 경사균열 보정계수를 제안하고자 한다. 본 논문의 결과인 경사균열 보정계수들은 각 하중조건 및 실제 조건의 형상들에 대해 표 형식으로 나타내었다.

• 한국소음진동공학회논문집
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• 제13권5호
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• pp.400-408
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• 2003

This paper investigates the vibration characteristics of steam generator (SG) U-tubes with defect. The operating SG shell-side flow field conditions for determining the fluidelastic instability parameters such as added mass are obtained from three-dimensional SG flow calculation. Modal analyses are performed for the U-tubes either with axial or circumferential flaw with different sizes. Special emphases are on the effects of flaw orientation and size on the modal and instability characteristics of tubes, which are expressed in terms of the natural frequency, corresponding mode shape and stability ratio. Also, addressed is the effect of the internal pressure on the vibration characteristics of the tube.

• 대한기계학회논문집
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• 제19권3호
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• pp.731-740
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• 1995

The objective of this paper is to develop defect assessment technology for integrity evaluation of CANDU pressure tubes. In fracture mechanics analysis, three-dimensional and two-dimensional (line-spring model) finite element analyses were performed to obtain the stress intensity factor for axial and circumferential surface cracks. In leak before break (LBB) analysis, heat transfer analyses for through-wall cracks were performed by considering the cooling effect and the LBB application time was computed. It was shown that the analytical results obtained in this study provide less-conservative but accurate solution for defect assessment of CANDU pressure tubes.

• Nuclear Engineering and Technology
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• 제38권3호
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• pp.293-300
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• 2006

A liquid metal reactor (LMR) operated at high temperatures is subjected to both cyclic mechanical loading and thermal loading; thus, creep-fatigue is a major concern to be addressed with regard to maintaining structural integrity. The Korea Advanced Liquid Metal Reactor (KALIMER), which has a normal operating temperature of $545^{\circ}C$ and a total service life time of 60 years, is composed of various cylindrical structures, such as the reactor vessel and the reactor baffle. This study focuses on the creepfatigue crack initiation for a cylindrical Y-junction structure made of 316 stainless steel (SS), which is subjected to cyclic axial tensile loading and thermal loading at a high-temperature hold time of $545^{\circ}C$. The evaluation of the considered creep-fatigue crack initiation was carried out utilizing the ${\sigma}_d$ approach of the RCC-MR A16 guide, which is the high-temperature defect assessment procedure. This procedure is based on the total accumulated strain during the service time. To confirm the evaluated result, a high-temperature creep-fatigue structural test was performed. The test model had a circumferential through wall defect at the center of the model. The defect front of the test model was investigated after the $100^{th}$ cycle of the testing by utilizing a metallurgical inspection technique with an optical microscope, after which the test result was compared with the evaluation result. This study shows how creep-fatigue crack initiation for a high-temperature structure can be predicted with conservatism per the RCC-MR A16 guide.

• 대한기계학회논문집A
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• 제39권7호
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• pp.645-652
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• 2015

본 논문은 이전 연구에서 제시한 여러 가지 Ramberg-Osgood 상수 결정법을 비교하여 파단전 누설평가에 사용되기 가장 적합한 상수 결정법을 선정하였다. 비교에 사용한 재료는 운전온도인 $316^{\circ}C$에서 실험한 SA312 TP316 과 SA508 Gr.1a 이다. 상수 결정법을 선정하기 위해 실제 응력-변형률 데이터를 모두 이용하는 증분 소성 이론과 Ramberg-Osgood 상수를 이용하는 변형 소성이론을 유한요소 해석에 적용하여 계산한 J 적분과 균열 열림 변위를 비교하였다. 비교 결과에서 증분 소성 이론 결과와 가장 잘 일치하는 상수 결정법을 최종적으로 파단전 누설 평가에 적합한 방법으로 선정하였다.