• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.127.2-127
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• 2001

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.460.1-460
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• 2001

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.401.1-401
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• 2002

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.228.2-228
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• 1999

• 한국자기학회:학술대회 개요집
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• 한국자기학회 2016년도 자성 및 자성재료 국제학술대회
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• pp.90-91
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• 2016

• 대한기계학회논문집A
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• 제25권1호
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• pp.81-88
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• 2001

This study proposed an analytical method to evaluate a local allowable wall thickness (LAWT) for locally thinned pipe subjected to internal pressure and bending moment. In this method, the stresses in the thinned region were calculated by finite element analysis and plastic collapse was applied as a failure criterion of thinned pipe. Using this method, LAWT for a simplified thinned pipe was evaluated with variation in axial extent of thinned area, and it was compared with allowable wall thickness provided by previous pipe wall thickness criteria. The results showed that the LAWT was lower, about 50%, than that calculated by construction code or ASME Code N-597, and it was higher, about 2 times, than that estimated by evaluation model based on pipe experiments. In addition, LAWT was decreased with increasing axial extent of thinned area and saturated with further increase in axial extent. And, the variation in LAWT with axial extent of thinned area depended on type of load, especially a magnitude of bending moment, considering in the evaluation.

• 대한기계학회논문집A
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• 제27권8호
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• pp.1295-1302
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• 2003

In order to evaluate a failure behavior of pipe with notch-type wall thinning, the present study performed full-scale pipe tests using the 102mm, Schedule 80 pipe specimen simulated notch- and circular-type thinning defects. The pipe tests were conducted under the conditions of both monotonic and cyclic bending moment at a constant internal pressure of 10 MPa. From the results. of experiment the failure mode, load carrying capacity, deformation ability, and fatigue life of a notch-type wall thinned pipe were investigated, and they were compared with those of a circular-type wall thinned pipe. The failure mode of notched pipe was similar to that of circular-type thinned pipe under the monotonic bending load. Under the cyclic bending load, however, the mode was clearly distinguished with variation in the shape of wall thinning. The load carrying capacity of a pipe containing notch-type wall thinning was about the same or slightly lower than that of a pipe containing circular-type wall thinning when the thinning area was subjected to tensile stress, whereas it was higher than that of a pipe containing circular-type thinning defect when the thinning area was subjected to compressive stress. On the other hand, the deformation ability and fatigue life of a notch-type wall thinned pipe was lower than those of a circular-type wall thinned pipe.

• 한국압력기기공학회 논문집
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• 제18권2호
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• pp.54-60
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• 2022

ASME BPVC provides stress evaluation rules for Class 2 and 3 nuclear piping. However, such rules are difficult to be applied to reinforced wall-thinned pipes during service. To resolve this issue, a new method for stress evaluation of reinforced wall-thinned pipes is proposed in this work, based on the equivalent stiffness concept. By converting a reinforced wall-thinned pipe to an equivalent straight pipe having the same stiffness, stress evaluation can be proceeded using the current ASME BPVC rules. The proposed method is applied to pipes with 4 different normal pipe size and the effects of reinforcement and wall-thinning dimensions on evaluated stresses are discussed.

• 비파괴검사학회지
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• 제32권2호
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• pp.170-176
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• 2012

원자력 산업에 있어서 파이프의 감육결함은 수명평가 및 안전평가에 막대한 손실을 발생 할 수 있다. 비파괴검사 기법을 이용하여 변형, 진동, 결함 평가를 수행하고 있지만, 넓은 면적의 결함을 평가하는 기법이 적으며, 시간이 오래 걸리는 단점이 있다. 원자력 발전소의 2차계통에서 주로 사용되는 탄소강 배관을 대상으로 내부에 인공 감육결함을 가공하고 두께를 서로 다르게 하여 제작하여 Shearography를 이용하여 감육결함부의 변형을 측정하였다. 또한 광 계측을 통하여 변형, 진동, 결함 평가뿐만 아니라 압력용기의 결함깊이를 정량적으로 평가하고자 한다. 본 논문은 전단간섭계를 이용하여 파이프의 내부 감육 결함을 측정하고, 압력에 따른 변형을 제시한 기법을 이용하여 정량적인 결함의 잉여두께를 평가하고자 한다. 변형량을 이용하여 잉여두께 예측결과 실제 결함깊이와 약 7%의 오차로 신뢰성을 확보하였으며, 압력에 따른 변형량과 잉여두께의 DB구축을 통하여 원전 배관의 감육부 건전성 평가에 활용될 수 있을 것이다. 따라서, 본 연구에서 제안하는 압력용기 결함깊이 측정법은 원자력배관의 감육결함 예측 및 건정성 평가 기술 개발 등 이론과 실험이 결함된 기초연구로서 압력용기의 안정성, 건전성, 보수성을 증진시킬 수 있는 기반확립에 기여할 것으로 기대한다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집D
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• pp.807-812
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• 2001

This paper represents the wall thinning analysis results for secondary side piping of two types of domestic nuclear power plants based on the DB establishment and F AC analysis study for NPP secondary system piping. CHECWORKS code utilized in this study has been applied world widely to wall thinning analyses for secondary side piping and its reliability has also been proved. The predicted wear rates for several piping systems of a pressurized water reactor NPP are compared with those of a pressurized heavy water reactor NPP and with the measured wear rates. On the basis of comparison results of the predicted and measured wear rates, the analysis results can be effectively applied to the development of a standard thinned pipe management program targeted all domestic nuclear power plants.