• Pediatric Gastroenterology, Hepatology & Nutrition
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• 제5권2호
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• pp.186-191
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• 2002

구토, 심한 보챔, 고열, 복수를 동반한 복부 팽만 등 급성 복막염의 양상을 보인 10개월 된 여아에서 복부 천자 후 담즙성 복막염 의심하에 $^{99m}Tc$ DISIDA 간담도 스캔을 시행하여 진단된 총 담관낭의 자연 천공에 의한 담즙성 복막염 1례를 경험하였기에 문헌 고찰과 함께 보고하는 바이다.

• 한국전산구조공학회논문집
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• 제23권4호
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• pp.445-452
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• 2010

CANDU형 격납건물에 대하여 극한내압하중에 대한 확률론적 취약도 평가를 수행하였다. 격납건물 성능의 불확실성은 가동중 검사 결과를 통해 얻어진 재료 물성치 중앙값과 텐던 긴장력 중앙값을 적용하여 고려하였다. 격납건물은 개구부를 고려하여 3차원 유한요소로 모델링하였으며, 확률론적 취약도 평가를 위하여 대규모의 비선형 유한요소해석 모델을 적용하기에 적합한 효율적인 취약도 평가기법을 개발하였다. 월성 1호기 격납건물에 대한 물성치를 사용하였다. 개발된 새로운 취약도 평가기법을 도입하여 각각의 파괴모드에 대한 취약도 평가를 수행하였으며, 파괴모드 별, 신뢰도 수준별 취약도 곡선을 도출하였다. 벽체 중단부가 극한내압발생으로 인한 방사능물질 누출에 가장 취약한 것으로 나타났다.

• 한국압력기기공학회 논문집
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• 제8권3호
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• pp.13-22
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• 2012

According to recent research on leak-rate estimates to assess rupture probabilities of nuclear piping which contains a circumferential surface/through-wall cracks due to PWSCC, i.e., xLPR (Extremely Low Probability of Rupture) program, it has been revealed that the use of crack shape with an idealized circumferential through-wall crack during actual crack growth can lead to overestimate of the leak-rate. Thus, for accurate estimation of the leak-rate during crack growth, the more realistic crack shape that can simulate the crack shape transition from surface crack to through-wall crack should be used. In this context, in the present study, the elastic crack opening displacement of slanted circumferential through-wall crack in thick-walled cylinder was proposed based on 3-dimensional elastic finite element fracture mechanics analyses. To propose the elastic crack opening displacement of slanted circumferential through-wall crack in thick-walled cylinder, the geometric variables affecting crack opening displacement, i.e., thickness of cylinder, reference inner crack length and slant crack ratio were systematically varied. In terms of loading conditions, axial tension, global bending moment and internal pressure were considered. The present results can be applied to calculate the leak-rate considering more realistic crack shape transition from surface crack to idealized through-wall crack, and can be expected to enhance current leak-rate estimation scheme, for instance, in xLPR program etc.

• 한국가스학회지
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• 제16권3호
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• pp.22-28
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• 2012

BPA 공장의 메탄올 분리공정에서 HAZOP 평가를 실시하고, 사고 시나리오로부터 화재 및 폭발 사고의 피해범위를 예측하였다. 그 결과, 화재사고의 피해범위는 50 mm 직경의 안전밸브 토출배관 파열에 의한 제트화재에서는 20 m이었고, 설비가 전파되어 플래쉬화재가 발생되는 경우에는 267 m이었다. 또한 개방공간 증기운 폭발사고의 피해범위는 토출배관 파열에서는 22 m이었고, 설비 전파인 경우에는 542 m이었다. 그리고 최악의 누출 시나리오에 대한 안전대책으로는 메탄올 분리컬럼 내부의 이상압력 상승을 감지할 수 있는 압력계를 2 out of 3 voting으로 설비 상부에 설치하여 주공급라인 상에 설치된 컨트롤밸브와 긴급차단밸브를 동시에 차단할 수 있도록 하여야 한다.

• 한국안전학회지
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• 제18권4호
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• pp.16-22
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• 2003

Generally the rupture of steam generator tubes proceeds from significant plastic deformation before failure. In this study, the burst pressures of damaged steam generator tubes were calculated from the plastic instability analysis with the finite element method. Two wear types, flat and circumferential types were considered. An equation for the burst pressure was proposed by using the strength reduction factor and the Svensson equation. The analysis results were compared with the experiment data from published references and they showed a good agreement with the experiment data.

• 한국분무공학회지
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• 제9권4호
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• pp.24-30
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• 2004

Feedwater flowing tube side of number 5 high pressure feedwatrr heaters was heated by extracting steam from high pressure turbine and draining water from moisture separators and number 6 high pressure feedwater heaters and supplied into steam generators. Because the extracting steam from the high pressure turbine is two phase fluid of high temperature, high pressure, and high speed and flows to inverse direction after impinging to impingement baffle. the shell wall of the number 5 high pressure feedwater heater may be affected by flow accelerated corrosion. On May 14, 1999, Point Beach Nuclear Plant (PBNP) with operating at full power experienced a steam leak from rupture of shell side of number 4B feedwater heater. Also, d domestic nuclear power plant experienced a severe wall thinning of shell side of number 5A and 5B feedwater heaters. This paper describes the fluid mixing analysis study using PHOENICS code in order to get at the root of the shell wall thinning of the feedwater heaters. The sections included in the fluid mixing analysis model are around the number 5h feedwater heater shell including the extracting pipeline. To identify the relation between the local velocities and wall thinning. the local velocities according to the analysis results were compared with the distribution of the shell wall thickness by ultrasonic test.

• 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.

• 한국수소및신에너지학회논문집
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• 제20권3호
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• pp.188-193
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• 2009

Fuel cell vehicles are equipped with Pressure Relief Devices(PRDs) installed in pressure tank cylinder to prevent the explosion of the tank during a fire. PRDs are safety devices that perceive a fire and release gas in the pressure tank cylinder before it is exploded. But if the PRD does not actuate, because either the PRD fails or can't be surrounded by the flame of a fire, the tank will rupture and produce a blast wave and hydrogen fire ball. In this paper, we observed the fire behavior of actual fuel cell vehicle, comparing with that of gasoline vehicle.

• Steel and Composite Structures
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• 제32권6호
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• pp.701-715
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• 2019

Using first-order shear deformation theory (FSDT), a semi-analytical solution is employed to analyze creep damage and remaining life assessment of 304L austenitic stainless steel thick (304L ASS) cylindrical pressure vessels with variable thickness subjected to the temperature gradient and internal non-uniform pressure. Damages are obtained in thick cylinder using Robinson's linear life fraction damage rule, and time to rupture and remaining life assessment is determined by Larson-Miller Parameter (LMP). The thermo-elastic creep response of the material is described by Norton's law. The novelty of the present work is that it seeks to investigate creep damage and life assessment of the vessels with variable thickness made of 304L ASS using LMP based on first-order shear deformation theory. A numerical solution using finite element method (FEM) is also presented and good agreement is found. It is shown that temperature gradient and non-uniform pressure have significant influences on the creep damages and remaining life of the vessel.

• 한국항공우주학회지
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• 제30권8호
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• pp.103-111
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• 2002

열하중과 원심력을 고려한 발전용 터빈 블레이드의 정상 상태 크리프 해석을 수행하였다. 3차원 터빈 블레이드 유한 요소 모델에 대하여 크리프 변형률과 응력을 계산하고 수치적 방법에 의해 크리프 수명을 예측하였다. 약 200시간 정도의 크리프 해석 결과 GTD111 터빈 블레이드는 아직 파손 응력에 도달하지 않았으며, 크리프 응력은 시간이 경과함에 따라 점차 이완되고 있다. 터빈 블레이드의 최대 크리프 변형률은 익형의 압력면 끝단에서 발생하며 수치적 방법에 의해 약 50,000 시간 이후에 파손 변형률에 도달할 것이다. 따라서 현재 터빈의 기동 중 블레이드는 크리프에 의한 손상을 입지 않는다.