• 한국압력기기공학회 논문집
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• 제6권2호
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• pp.1-8
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• 2010

Nuclear steam generator tubes have experienced wear degradation at tube support structure. Morphology of wear scar was analyzed by using eddy current signal. A burst test facility for steam generator tubes was established and tubes with 3 types of defects were tested. The burst test results show that the depth of wear scar is the main factor influencing the burst pressure of tubes, meanwhile, both the longitudinal length and the angle also have effect on the burst pressure. Based on test results, the burst pressure equation for wear degradation was proposed.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 추계학술대회
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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.

• 한국가스학회지
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• 제17권3호
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• pp.20-26
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• 2013

본 연구에서는 수압파열시험 장비를 이용하여 Type3 복합용기의 설계 파열압력에 관한 실증연구를 수행하였다. 고압가스를 저장할 수 있는 6.8L급 사용압 31MPa Type3 복합용기에 대한 유한요소 설계해석을 통하여 파열압을 예측하였고 해석의 정확성을 확인하기 위하여 수압파열시험을 3회 실시하였다. 파열시험설비는 수압으로 최대 400MPa까지 가압이 가능한 장비를 활용하였다. 해석으로 예측된 소형 복합용기의 설계 파열압과 실제 파열시험 결과를 비교한 결과, 값의 차이는 4% 이내로 나타났다. 이를 통하여 해석기법의 신뢰성을 확인하였으며, 본 실증에서 검증된 해석기법을 복합용기의 안전성 확보를 위한 국내인증 및 제품검사에 적용할 예정이다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 추계학술대회
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• pp.279-284
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• 2004

In this study, we suggested the ring creep test using the ring specimen of Arsene for estimating the burst creep properties of the cladding in stead of burst creep test. For this objective, we used the load-displacement conversion relationship of ring specimen called LCRR which had been determined on our previous study at high temperature by performing the ring tensile test and the numerical analysis. Then we carried out both the ring creep test and the burst creep test between 350 $^{\circ}C$ and 600$^{\circ}C$ which were higher then the in-service temperature of the cladding in a reactor. The creep properties from the ring creep test with applying LCRR were compared with those from the burst creep test of closed-end specimens. From the results, it could be seen an very strong relationship between them, especially in Larson- Miller parameter. So, it is expected that we can easily anticipate the creep properties of not only claddings but also various small pressure pipes using the ring creep test.

• 대한기계학회논문집A
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• 제29권7호
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• pp.964-969
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• 2005

In this study, we suggested the ring creep test using the ring specimen of Arsene for estimating the burst creep properties of the cladding in stead of burst creep test. For this objective, we used the load-displacement conversion relationship of ring specimen called LCRR which had been determined on our previous study at high temperature by performing the ring tensile test and the numerical analysis. Then we carried out both the ring creep test and the burst creep test between $350^{\circ}C$ and $600^{\circ}C$ which were higher than the in-service temperature of the cladding in a reactor. The creep properties from the ring creep test with applying LCRR were compared with those from the burst creep test of closed-end specimens. From the results, it could be seen an very strong relationship between them, especially in Larson-Miller parameter. So, it is expected that we can easily predict the creep properties of not only claddings but also various small pressure pipes using the ring creep test.

• 대한기계학회논문집A
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• 제26권1호
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• pp.203-210
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• 2002

The transmission pipeline industry spends many millions of dollars annually performing inline inspections, excavating sites of possible corrosion, and repairing or replacing damaged sections of pipe. New criteria fur evaluation of the integrity of corroded pipe have been developed in recent years to help in controlling these costs. These new criteria vary widely in their estimates of integrity and the most appropriate criterion fur a given pipeline is net always clear. This paper presents an overview, comparison and evaluation of acceptability criteria for corrosion deflects in pipelines. By full scale burst tests, this paper has assessed the relative accuracy of each of theses criteria in predicting burst pressure. Many of the criteria appear to be excessively conservative and indicate that deflects must be repaired when none is needed, based upon burst test data.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 춘계학술대회
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• pp.222-227
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• 2004

The failure assessment for corroded pipeline has been considered with the full scale burst test and the finite element analysis. The burst tests were conducted on 762 mm diameter, 17.5 mm wall thickness and API 5L X65 pipe that contained specially manufactured rectangular corrosion defect. The failure pressure for corroded pipeline was measured by burst testing and classified with respect to corrosion sizes and corroded regions - the body, the girth weld and the seam weld of pipe. Finite element analysis was carried out to derive failure criteria of corrosion defect on the pipe. A series of finite element analyses were performed to obtain a limit load solution for corrosion defects on the basis of burst test. As a result, the criteria for failure assessment of corrosion defect within the body, the girth weld and the seam weld of API 5L X65 gas pipeline were proposed.

• 한국전자파학회논문지
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• 제27권3호
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• pp.291-298
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• 2016

본 논문에서는 전자파적합성 국제 규격인 IEC 61000-4-4에서 규정하고 있는 전기적으로 빠른 과도현상/버스트(EFT/Burst) 신호가 전원선을 따라 시험대상품에 인가될 때, 인가신호에 기인하여 방사되는 불요전자파와 그 신호가 피시험품에 미치는 영향에 대해 연구하였다. 먼저 국제규격에 규정된 시험 배치방법에 따라 시험 샘플을 설치하고, 검증된 EFT/Burst 발생기로 1분 동안 +4 kV의 규정된 신호를 길이 1 m인 전원선을 통해 시험 샘플에 인가하였다. 그 결과, 전원선을 통해 인가되는 전도성 EFT/Burst 내성 신호 외 버스트 발생기 및 전원선에서 직접 공기 중으로 방출되는 방사성 신호(EFT/Burst 노이즈)가 검출되었고, 국제 공인시험 규격으로 이 신호를 측정한 결과, 규제 레벨보다 30 dB 이상 높았다. 또한, EFT/Burst 방사성 신호의 최대 방사 지점과 시험품의 이격 거리에 따른 전계강도를 측정한 결과, 방사내성 국제 규격치보다 최대 23 V/m 이상 강한 전계강도가 검출되었다. 이는 EFT/Burst 방사성 노이즈가 직접적으로 제품에 인가되어 오동작을 유발할 가능성이 대단히 높으므로 대책이 요구됨을 확인하였다.

• Corrosion Science and Technology
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• 제3권1호
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• pp.30-33
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• 2004

It has been reported that some events of a rupture of seam generator tube have occurred in nuclear power plants around the world. Main causes of the leakage are from various types of corrosion in the steam generator(SG) tubings. Primary water stress corrosion cracking(PWSCC) of steam generator tubings have occurred in many tubes in Korean plant, and they were repaired using sleeves or plugs, In order to develop proper repair criteria, it is necessary to ascertain the leak behavior of the tubings. A high pressure leak and burst testing system was manufactured. Various types of Electro Discharged Machined (EDM) notches were developed on the SG tubes. Leak rate and burst pressure were measured on the tubes at room temperature. Burst pressure of the part through wall defected tubes depends on the defect depth, Water flow rates after the burst were independent of the t1aw types; tubes having 20 to 60 mm long EDM notches showed similar flow rates regardless of the defect depth. A fast pressurization rate gave the tube a lower burst pressure than the case of a slow pressurization.

• 한국유체기계학회 논문집
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• 제14권4호
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• pp.12-18
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• 2011

Volute casings for liquid rocket turbopump are designed and evaluated in a structural point of view. At the design step 3D modeling and finite element analyses are conducted iteratively. During the step various loads such as internal pressure, casing stiffness and mounting forces are considered in the analyses, along with the weight minimization effort. After the design step volute casings are manufactured by metal casting process, and then they are subjected to burst test for structural verification. In the burst test strains at several points are measured and compared with predicted values.