• Nuclear Engineering and Technology
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• 제53권2호
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• pp.474-483
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• 2021

To establish the exclusive role of hydrogen on burst behaviour of Zircaloy-4 during loss-of-coolant accident transients, an extensive single-rod burst tests were conducted on both unirradiated as-received and hydrogenated Zircaloy-4 cladding tubes at different heating rates and internal overpressures. The visual observations of cladding tubes during bursting as well as post-burst are presented in detail to understand the effect of hydrogen concentration, heating rate, and internal pressure. Impact of hydrogen on burst parameters-burst stress, burst strain, burst temperature-during loss-of-coolant accident transients are compared and discussed. Rupture at multiple locations for hydrogenated cladding at lower internal pressure and higher heating rate is reported for the very first time. A novel burst criterion accounting hydrogen concentration in nuclear fuel cladding is proposed.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2008년도 추계학술대회A
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• pp.305-310
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• 2008

This paper provides the methods to estimate the burst pressures of the pipes with defects, based on finite element analyses. FE codes are frequently adopted for the simulations of the burst tests of the pipes with defects. However, those do not give the burst pressure directly. Because the post-processing should be followed; determination of the fracture strains in accordance with triaxialities, monitoring the strains of pipes, etc. In the present work, these efforts are implemented in the user subroutine UHARD within the general-purpose FE code, ABAQUS. Four fracture criterions are introduced to estimate the burst pressure of pipes, and a simple fracture strain estimate is also developed. FE analyses for the pipe with gouge and corrosion are performed, and the results are compared with the experiment results.

• 한국추진공학회지
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• 제1권2호
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• pp.1-11
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• 1997

본 연구에서는 음향방출법을 활용한 복합재 연소관의 구조적 건전성 평가 방법을 개발하기 위하여 표준 평가용 시험 시편의 수압 시험 중, 압력용기로부터 방출되는 음향방출 신호를 측정함으로써 시편이 파괴되기 전, 대략적인 시편의 파열 위치 예측 및 일정 압력 유지 상태에서 hit rate(hit/sec) 양상에 의한 시편의 건전성 평가 방법을 제시하였다. 데이터 분석 기법의 향상을 위하여 음향방출 데이터를 시간 및 센서별로 분류하는 프로그램을 개발하였다. 수압 시험을 낮은 압력 단계부터 높은압력 단계까지 일정 압력 유지 상태에서 발생한 hit 수와 1분간 유지한 후, 발생되는 hit rate의 값의 크고 작음이 복합재 압력 용기의 결함수의 증감으로 나타났으며, 이로부터 복합재 압력 용기의 파열 압력과의 상관 관계 및 건전성을 예측할 수 있었다. 복합재 압력 용기의 파열 위치는 energy rate(energy/sec) 측정값을 분석하여 예측하였으며, 시편 파열 압력의 25∼36％에서 가능하였다.

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.666-676
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• 2021

This paper presents numerical estimation of burst pressures of axial cracked U-bend tubes, considering the U-bending process analysis. The validity of the FE simulations is confirmed by comparing with published experimental data. From parametric analyses, it is shown that existing EPRI burst pressure estimation equations for straight tubes can be conservatively used to estimate burst pressures of the U-bend tubes. This is due to the increase in yield strength during the U-bending process. The degree of conservatism would decrease with increasing the bend radius and with increasing the crack depth.

• 한국안전학회지
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• 제30권1호
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• pp.144-149
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• 2015

This study aims to quantitatively evaluate failure pressure of wall-thinned elbow under combined load along with internal pressure, by conducting real-scale burst test and finite element analysis together. For quantitative evaluation, failure pressure data was extracted from the real-scale burst test first, and then finite element analysis was carried out to compare with the test result. For the test, the wall-thinning defect of the extrados or intrados inside the center of 90-degree elbow was considered and the loading modes to open or close the specimen maintaining a certain load or displacement were applied. Internal pressure was applied until failure occurred. As a result, when the bending load was applied under the load control condition, the intrados of the defect was more affected by failure pressure than the extrados, and the opening mode was more vulnerable to failure pressure than the closing mode. When the bending load was applied under the displacement control, it was hardly affected by failure pressure though it was slightly different from the defect position. The result of the finite element analysis showed a similar aspect with the test. Moreover, when major factors such as material properties and pipeline thickness were calibrated to accurate values, the analytical results was more similar to the test results.

• 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.

• 한국안전학회지
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• 제30권4호
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• pp.168-173
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• 2015

A steam generator tubing is one of the main pressure boundary of the reactor coolant system in the nuclear power plants. Structural integrity refers to maintaining adequate margins against failure of the tubing. Burst pressure of a tube at tube support plate can be higher than that for a free-span tube because failure behaviors could be interfered from the tube support plate. Alternative repair criteria for out-diameter stress corrosion cracking indications in tubes to the drilled type tube support plate were developed, however, there are very limited information to the eggcrate type tube support plate. This paper discussed reinforcement effect of steam generator tube burst pressure with axial out-diameter stress corrosion cracking within an eggcrate type tube support plate. A series of tube burst tests were performed under the room temperature and it was found out that there is no significant but marginal effects.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2010년도 제35회 추계학술대회논문집
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• pp.217-220
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• 2010

본 논문에는 가스발생기를 사용한 사출시스템의 성능향상 즉 최대가속도를 줄일 수 있는 방법 중 하나인 노즐마개의 파열압 저감에 대한 내용이 기술되어있다. 여러가지의 노즐마개를 제작하여 공압시험으로 파열압을 측정하여 노치의 형상과 파열압과의 관계를 조사하였다. 파열압을 저감시킨 노즐마개를 적용하여 가스발생기를 제작, 시험한 결과 기준모델과 비교시 최대가속도를 저감에 효과적임을 확인하였다.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2008년도 제31회 추계학술대회논문집
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• pp.288-292
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• 2008

동일 보스 오프닝에 대해 여러 형상의 돔을 설계할 수 있는 복합재 압력용기용 형상 식이 제시되었고, 이러한 돔 형상 변화에 따른 복합재 압력용기의 성능(파열압력*내부용적/복합재무게) 변화를 유한 요소 응력해석과 시험을 통해 규명하였다. 해석을 통해 예측한 돔 형상 변화에 따른 압력용기의 파열압력이 시험 결과와 좋은 일치를 나타내었다. 전반적으로 돔 형상이 낮아짐에 따라 압력용기 내부 용적이 증가하였으나, 파열 압력은 저하되는 현상을 나타내었다. 보스 오프닝 비(${\rho}_o$)가 0.54 이상인 경우, 돔 형상이 낮아짐에 따라 파열 압력이 저하되어 성능 저하가 나타났다. 그러나 보스 오프닝 비(${\rho}_o$)가 0.34이하 경우 돔 형상 변화에 따른 파열 압력 저하가 크지 않음으로 성능의 큰 변화가 없었다.