• 제목/요약/키워드: Semi-elliptical Flaws

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영향계수를 이용한 원통용기 표면결함의 응력확대계수의 계산 (Stress Intensity Factor Calculation for the Semi-elliptical Surface Flaws on the Thin-Wall Cylinder using Influence Coefficients)

  • 장창희;문호림;정일석
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집A
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    • pp.280-285
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    • 2001
  • As an integral part of the probabilistic fracture mechanics analysis, stress intensity factor calculation scheme for semi-elliptical surface flaws in thin-walled cylinder has been introduced. The approximation solution utilizes the influence coefficients to calculate the stress intensity factor at the crack tip. This method has been compared with other solution methods including 3-D finite element analysis for cooldown boundary condition. The analysis results confirmed that the simplified methods provided sufficiently accurate stress intensity factor values for axial semi-elliptcal flaws on the surface of the reactor pressure vessel.

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Approximation Method for the Calculation of Stress Intensity Factors for the Semi-elliptical Surface Flaws on Thin-Walled Cylinder

  • Jang Chang-Heui
    • Journal of Mechanical Science and Technology
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    • 제20권3호
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    • pp.319-328
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    • 2006
  • A simple approximation method for the stress intensity factor at the tip of the axial semielliptical cracks on the cylindrical vessel is developed. The approximation methods, incorporated in VINTIN (Vessel INTegrity analysis-INner flaws), utilizes the influence coefficients to calculate the stress intensity factor at the crack tip. This method has been compared with other solution methods including 3-D finite element analysis for internal pressure, cooldown, and pressurized thermal shock loading conditions. For these, 3-D finite-element analyses are performed to obtain the stress intensity factors for various surface cracks with t/R=0.1. The approximation solutions are within $\pm2.5%$ of the those of finite element analysis using symmetric model of one-forth of a vessel under pressure loading, and 1-3% higher under pressurized thermal shock condition. The analysis results confirm that the approximation method provides sufficiently accurate stress intensity factor values for the axial semi-elliptical flaws on the surface of the reactor pressure vessel.

영향계수를 이용한 원통용기 축방향 표면결함의 응력확대계수의 계산 (Stress Intensity factor Calculation for the Axial Semi-Elliptical Surface Flaws on the Thin-Wall Cylinder Using Influence Coefficients)

  • 장창희;문호림;정일석;김태룡
    • 대한기계학회논문집A
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    • 제26권11호
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    • pp.2390-2398
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    • 2002
  • For integrity analysis of nuclear reactor pressure vessel, including the Pressurized thermal shock analysis, the fast and accurate calculation of the stress intensity factor at the crack tip is needed. For this, a simple approximation scheme is developed and the resulting stress intensity factors for axial semi-elliptical cracks in cylindrical vessel under various loading conditions are compared with those of the finite element method and other approximation methods, such as Raju-Newman's equation and ASME Sec. Xl approach. For these, three-dimensional finite-element analyses are performed to obtain the stress intensity factors for various surface cracks with t/R = 0.1. The approximation methods, incorporated in VINTIN (Vessel INTegrity analysis-INner flaws), utilizes the influence coefficients to calculate the stress intensity factor at the crack tip. This method has been compared with other solution methods including 3-D finite clement analysis for internal pressure, cooldown, and pressurized thermal shock loading conditions. The approximation solutions are within $\pm$2.5% of the those of FEA using symmetric model of one-forth of a vessel under pressure loading, and 1-3% higher under pressurized thermal shock condition. The analysis results confirm that the VINTIN method provides sufficiently accurate stress intensity factor values for axial semi-elliptical flaws on the surface of the reactor pressure vessel.

내압이 작용하는 원통형용기에 대한 축방향 표면결함의 응력확대계수 계산방법 비교 (Comparison of Stress Intensity Factors for Longitudinal Semi-elliptical Surface Cracks in Cyclindrical Pressure Vessels)

  • 문호림;장창희
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집A
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    • pp.622-627
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    • 2001
  • The object of this paper is to compare stress intensity factor that be calculated by Raju-Newman's equation, finite element method, and Vessel INTegrity analysis inner flaws(VINTIN) program for longitudinal semi-elliptical cracks in cylindrical vessel under inner pressure. For this, three-dimensional finite-element analyses were performed to obtain the stress intensity factors for various surface cracks with t/R = 0.1. The finite element meshes were designed for various crack shapes with t/R of 0.1. The crack depth to thickness ratio, a/t, was set to 0.2 and 0.5 matching Raju-Newman's equation. The crack depth to length ratio, a/c, was set to 0.2 and 0.4 in the same way and 0.33 was added to extend the range of crack configuration. Finite Element Analyses(FEA) were performed using the commercial FEA program ABAQUS. The results showed that the Raiu-Newman solutions were about 4-10% lower than FEA's using symmetric model of one-eighth of a vessel and close to those of FEA using symmetric model or one-forth or a vessel. Ana VINTIN solutions were nearly equal to those or Raju-Newman.

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가압열충격을 받는 원자로용기의 확률론적 건전성 평가 (Probabilistic Evaluation of RV Integrity Under Pressurized Thermal Shock)

  • 김종민;배재현;손갑헌;윤기석;최택상
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 추계학술대회
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    • pp.90-95
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    • 2004
  • The probabilistic fracture analysis is used to determine the effects of uncertainties involved in material properties, location and size of flaws, etc, which can not be addressed using a deterministic approach. In this paper the probabilistic fracture analysis is applied for evaluating the RV(Reactor Vessel) under PTS(Pressurised Thermal Shock). A semi-elliptical axial crack is assumed in the inside surface of RV. The selected random parameters are initial crack depth, neutron fluence, chemical composition of material (copper, nickel and phosphorous) and $RT_{NDT}$. The deterministically calculated $K_I$ and crack tip temperature are used for the probabilistic calculation. Using Monte Carlo simulation, the crack initiation probability for fixed flaw and PNNL(Pacific Northwest National Laboratory) flaw distribution is calculated. As the results show initiation probability of fixed flaw is much higher than that of PNNL distribution, the postulated crack sizes of 1/10t in this paper and 1/4t of ASME are evaluated to be very conservative.

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반타원형 균열을 가정한 파괴 및 피로역학에 의한 수소 압력용기의 예상 수명 계산과 두께와 내경이 미치는 영향 분석 (Calculation of Expected Life of Hydrogen Pressure Vessels by Fracture and Fatigue Mechanics assuming Semi-elliptical Cracks and Analysis of the Effect of Thickness and Radius)

  • 김정환;이화영;이민경;이재훈;유근준
    • 한국가스학회지
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    • 제25권6호
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    • pp.53-65
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    • 2021
  • 수소충전소의 빠른 확장 및 설치와 동시에 수소충전소의 고압수소 충전 압력용기에 대한 안전 검사가 매우 중요하게 이루어져야 한다. 이 중 ASME에 따르면 일정 압력 이상의 수소를 보관하는 용기에 대해서는 수소 취성 검사를 반드시 해야 한다. 수소취성 검사의 주된 시험방법으로 고압의 수소분위기에서 파괴시험 및 피로 파괴시험을 실시해야 하며, 이를 통해 수소 분위기에서 압력용기의 내구한계를 측정하고, 사용한계를 결정하도록 되어 있다. 세부적으로 stress intensity factor(K)로부터 한계균열깊이를 계산하고, da/dN(피로성장율)로부터 사용수명을 결정할 수 있다. API579-1/ ASME FFS-1 part 9에서 crack-like flaws의 모드에 따른 계산방법을 예시하고 있으나, 플레이트, 실린더 등 다양한 형태의 형상에 대하여 균열의 형상, 위치 등에 의하여 대략 55개 모드가 있고, 상당히 복잡한 수식으로 인하여 쉽게 접근을 못한다. 본 연구에서는 엑셀 및 VBA를 통하여 수치해석적으로 파괴역학계산하는 방법을 소개하고자 한다. 또한, 이를 적용하여 압력용기의 두께와 내경이 수명에 미치는 영향을 분석해 보았다.

3차원 균열을 갖는 구조물에 대한 건전성 평가(II) (Integrity Evaluation for 3D Cracked Structures(II))

  • 이준성
    • 한국산학기술학회논문지
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    • 제14권1호
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    • pp.1-6
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    • 2013
  • 3차원 균열은 항공기나 압력용기 계통에서 흔히 발견되는 결함중의 하나이다. 균열을 갖는 구조물에 대한 정확한 응력확대계수 해석과 균열성장속도는 파괴강도와 피로수명을 평가하는데 필요로 한다. 3차원 유한요소법은 구조물에 존재하는 표면균열의 응력확대계수를 구하는데 이용되어 진다. 기하모델, 즉 균열을 포함하는 솔리드모델을 정의한 후, 절점이 버켓법에 의해 생성되어 진다. 요소생성은 사변형 솔리드요소를 데라우니 삼각화 기술에 의해 생성하도록 하였다. 시스템의 정확도와 효용성을 체크하기 위해 내압을 받는 원통형용기에 균열이 존재하는 경우의 응력확대계수 해석을 수행하였다. 개발된 시스템을 이용한 해석결과는 ASME 식과 Raju-Newnam식과 비교하여 5%이내의 차이를 보였다.

독립형 LNG 화물창의 공학적 결함 평가 (Engineering Critical Assessement for an Independent Type-B LNG Cargo Tank)

  • 서재훈;박규식;차인환;정준모
    • 대한조선학회논문집
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    • 제60권4호
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    • pp.213-221
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    • 2023
  • The demand for Liquefied Natural Gas (LNG) carriers and LNG-fueled ships has significantly increased in recent years due to the sulfur-oxide emission regulations by the International Maritime Organization (IMO). The main goal of this paper is to introduce the process for the Engineering Critical Assessment (ECA) of IMO independent type-B cargo tanks made from 9% nickel alloy. A methodology proposed by the British Standard was used to conduct ECA for any structure with initial flaws. Based on this standard, a Matlab code was developed to perform ECA. Coarse mesh Finite Element Analysis (FEA) was performed on an independent type-B LNG cargo tank with a capacity of 15,000 m3. The location with the highest development of maximum principal stress was identified at the bottom of the cargo tank. Fine mesh FEA was performed to obtain the stress range required for ECA. The dynamic cargo tank loads used for FEA were determined using some ship rules presented by Det Norske Veritas. As a result of performing a 20-year long-term crack propagation analysis with a semi-elliptical surface crack, the fracture-to-yield ratio exceeded the Fracture Assessment Line (FAL) and some structural reinforcement was necessary. Performing a 15-day short-term crack propagation analysis, the fracture-to-yield ratio remained within the FAL, and no significant LNG leaks were expected. This paper is believed to provide a guide for performing ECA of LNG cargo tanks in the future by providing the basic theory and application sample necessary to perform ECA.

Probabilistic fatigue assessment of rib-to-deck joints using thickened edge U-ribs

  • Heng, Junlin;Zheng, Kaifeng;Kaewunruen, Sakdirat;Zhu, Jin;Baniotopoulos, Charalampos
    • Steel and Composite Structures
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    • 제35권6호
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    • pp.799-813
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    • 2020
  • Fatigue cracks of rib-to-deck (RD) joints have been frequently observed in the orthotropic steel decks (OSD) using conventional U-ribs (CU). Thickened edge U-rib (TEU) is proposed to enhance the fatigue strength of RD joints, and its effectiveness has been proved through fatigue tests. In-depth full-scale tests are further carried out to investigate both the fatigue strength and fractography of RD joints. Based on the test result, the mean fatigue strength of TEU specimens is 21% and 17% higher than that of CU specimens in terms of nominal and hot spot stress, respectively. Meanwhile, the development of fatigue cracks has been measured using the strain gauges installed along the welded joint. It is found that such the crack remains almost in semi-elliptical shape during the initiation and propagation. For the further application of TEUs, the design curve under the specific survival rate is required for the RD joints using TEUs. Since the fatigue strength of welded joints is highly scattered, the design curves derived by using the limited test data only are not reliable enough to be used as the reference. On this ground, an experiment-numerical hybrid approach is employed. Basing on the fatigue test, a probabilistic assessment model has been established to predict the fatigue strength of RD joints. In the model, the randomness in material properties, initial flaws and local geometries has been taken into consideration. The multiple-site initiation and coalescence of fatigue cracks are also considered to improve the accuracy. Validation of the model has been rigorously conducted using the test data. By extending the validated model, large-scale databases of fatigue life could be generated in a short period. Through the regression analysis on the generated database, design curves of the RD joint have been derived under the 95% survival rate. As the result, FAT 85 and FAT 110 curves with the power index m of 2.89 are recommended in the fatigue evaluation on the RD joint using TEUs in terms of nominal stress and hot spot stress respectively. Meanwhile, FAT 70 and FAT 90 curves with m of 2.92 are suggested in the evaluation on the RD joint using CUs in terms of nominal stress and hot spot stress, respectively.