• Title/Summary/Keyword: 파단곡선

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Development of CAD tool for optimal spot weld joints (점용접 위치의 최적화를 위한 CAD Tool 개발)

  • Ryu, Si-Uk;Lee, Jong-Chan;Lee, Tae-Soo
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.22 no.1
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    • pp.148-159
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    • 1998
  • Spot welding palys a key role in increasing productivity and weight reduction of the final products. This paper proposes a systematic approach on the design of spot weld configuration, dealing with the requried number and location of spot weld joints under the given design parameters, such as the applied loads, lap area, and individual spot weld strength. The optimal design of a spot-welded joint is postulated as a state when the safety factors of all spot weld points (i) are evenly distributed and (ii) reach maximum value. A CAD program is developed to arrange the optimal location of each spot weld based on the derived objective function and constraints. The CAD tool integrates the optimization procedure with Finite Element Analysis (FEA) code through an interface. The interface automatically provides geometrical data and mesh configuration for different spot weld locations to FEA model. It also extracts the transmitted load of each spot weld from the FEA code, and allows the optimization code predict an improved arrangement of spot weld locations. The feasibility of the developed approach is demonstrated by the selected examples.

Assessment of the Internal Pressure Fragility of the PWR Containment Building Using a Nonlinear Finite Element Analysis (비선형 유한요소 해석을 이용한 PWR 격납건물의 내압 취약도 평가)

  • Hahm, Daegi;Park, Hyung-Kui;Choi, In-Kil
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.27 no.2
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    • pp.103-111
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    • 2014
  • In this study, the probabilistic internal pressure fragility analysis was performed by using the non-linear finite element analysis method. The target structure is one of the containment buildings of typical domestic pressurized water reactors(PWRs). The 3-dimensional finite element model of the containment building was developed with considering the large equipment hatches. To consider uncertainties in the material properties and structural capacities, we performed the sensitivity analysis of the ultimate pressure capacity with respect to the variation of four important uncertain parameters. The results of the sensitivity analysis were used to the selection of the probabilistic variables and the determination of their probabilistic parameters. To reflect the present condition of the tendon pre-stressing force, the data of the pre-stressing force acquired from the in-service inspections of tendon forces were used for the determination of the median value. Two failure modes(leak, rupture) were considered and their limit states were defined to assess the internal pressure fragility of target containment building. The internal pressure fragilities for each failure mode were evaluated in terms of median internal pressure capacity, high confidence low probability of failure(HCLPF) capacity, and fragility curves with respect to the confidence levels. The HCLPF capacity was 115.9 psig for leak failure mode, and 125.0 psig for rupture failure mode.

Development of a new lifetime prediction method for gas turbine core parts by digital image analysis of precipitates morphology (석출물 형상의 디지털 이미지 분석에 의한 가스터빈 핵심부품의 새로운 수명평가기술 개발)

  • Chang, Moon Soo;An, Seong Uk
    • Analytical Science and Technology
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    • v.21 no.2
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    • pp.148-157
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    • 2008
  • To describe the lifetime prediction of gas turbine core parts serviced in some ten thousands rpms at over $1,000^{\circ}C$, the Larson-Miller Creep Curves, which are formed by creep rupture tests as the destructive experiment with parameters of stress and temperature, are used often, but not exact and reliable with errors of over some tens. On the other hand, this study shows a non-destructive method with increased accuracy and reliability. The SEM and TEM specimens were extracted by replica after polishing the local airfoil and root surfaces of the first stage scraped blade (bucket), serviced for 18,000 hours at $1,280^{\circ}C$ in Gas Turbines of Boryong. The observed TEM and SEM precipitates were digitalized for calculation of the average size. Here we could find the precipitate size grown from $0.45{\mu}m$ to $0.6{\mu}m$ during service and the grown precipitates to be still sound. From these results we could conclude that the scraped balde can be used for ten thous and hours additionally and for twenty thousand hours by additional heat treatments on the scraped blade.

A Study on Strength Prediction of Mechanical Joint of Composite under Bending Load (굽힘 하중을 받는 복합재 기계적 체결부의 강도예측에 관한 연구)

  • Baek, Seol;Kang, Kyung-Tak;Lee, Jina;Chun, Heoung-Jae
    • Composites Research
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    • v.27 no.6
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    • pp.213-218
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    • 2014
  • This paper predicted the strength of mechanical joint of composites under bending load by means of the characteristic curve method. The method has been employed only for tensile and compression load conditions, but in this study, this method was extended to the bending load condition. For the finite element analysis (FEA), the nonlinear analysis was conducted considering the contact and friction effects between composite material and pin. The failure strength and mode on characteristic curve were evaluate with Tsai-Wu failure theory. To validate the results of FEA, the experiments were conducted to find out the failure load by applying bending moment on the composite specimens. The results showed reasonable agreements with theoretical results. These results lead to a conclusion that the characteristic curve method can be applied to predict the bending strength of mechanical joint of composites.

Experimental Investigation on Torsional Analysis and Fracture of Tripod Shaft for High-speed Train (고속열차용 트리포드 축의 비틀림 해석 및 파단에 대한 실험적 연구)

  • Lee, Joo Hong;Kim, Do Sik;Nam, Tae Yeon;Lee, Tae Young;Cho, Hae Yong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.40 no.11
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    • pp.979-986
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    • 2016
  • The tripod shafts of constant-velocity joint are used in both the trains KTX and KTX-sanchon. It is an important component that connects the motor reduction unit and the axle reduction unit in a power bogie. The tripod shaft not only transmits drive and brake torque in the rotational direction, but also slides in the axial direction. If the drive system is loaded with an excessive torque, the fuse part of the shaft will be fractured firstly to protect the other important components. In this study, a rig was developed for conducting torsion tests on the tripod shaft, which is a type of mechanical fuse. The tripod shafts were subjected to torsional fracture test and torsional fatigue test on the rig. The weak zone of the tripod shaft was identified, and its fatigue life was predicted using finite element analysis (FEA). After analyzing the FEA results, design solutions were proposed to improve the strength and fatigue life of the tripod shaft. Furthermore, the deterioration trend and time for failure of the tripod shaft were verified using the hysteresis loops which had been changed with the advancement of the torsional fatigue test.

Prediction of Fracture Resistance Curves for Nuclear Piping Materials (원자력 배관재료의 파괴저항곡선 예측)

  • 장윤석;석창성;김영진
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.19 no.4
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    • pp.1051-1061
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    • 1995
  • In order perform leak-before-break design of nuclear piping systems and integrity evaluation of reactor vessels, full stress-strain (.sigma. - .epsilon.) curves and fracture resistance (J-R) curves are required. However it is time-consuming and expensive to obtain J-R curves experimentally. The objective of this paper is to develop two methods for J-R curve prediction. In the first method, elastic-plastic finite element analyses for a series of crack length / specimen width ratio were performed. Accordingly the load versus load line displacement (P .delta.) curve corresponding to the fracture strain is obtained and the J-R curve based on the generalized locus method is obtained. In the second method, the correlation between .sigma.-.epsilon. curves and J-R curves was statistically analyzed and an empirical equation to predict the J-R curve from the .sigma.-.epsilon. test result is proposed. A good correlation between the predicted results based on the proposed methods and the experimental ones is obtained.

Prediction of Fracture Resistance Curves for Nuclear Piping Materials(II) (원자력 배관재료의 파괴저항곡선 예측)

  • Chang, Yoon-Suk;Seok, Chang-Sung;Kim, Young-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.21 no.11
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    • pp.1786-1795
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    • 1997
  • In order to perform leak-before-break design of nuclear piping systems and integrity evaluation of reactor vessels, full stress-strain curves and fracture resistance (J-R) curves are required. However it is time-consuming and expensive to obtain J-R curves experimentally. The objective of this paper is to modify two J-R curve prediction methods previously proposed by the authors and to propose an additional J-R curve prediction method for nuclear piping materials. In the first method which is based on the elastic-plastic finite element analysis, a blunting region handling procedure is added to the existing method. In the second method which is based on the empirical equation, a revised general equation is proposed to apply to both carbon steel and stainless steel. Finally, in the third method, both full stress-strain curve and finite element analysis results are used for J-R curve prediction. A good agreement between the predicted results based on the proposed methods and the experimental ones is obtained.

Experimental Study of SBLOCA Simulation of Safety-Injection Line Break with Single Train Passive Safety System of SMART-ITL (SMART-ITL 1 계열 피동안전계통을 이용한 안전주입배관 파단 소형냉각재상실사고 모의에 대한 실험적 연구)

  • Ryu, Sung Uk;Bae, Hwang;Ryu, Hyo Bong;Byun, Sun Joon;Kim, Woo Shik;Shin, Yong-Cheol;Yi, Sung-Jae;Park, Hyun-Sik
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.40 no.3
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    • pp.165-172
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    • 2016
  • An experimental study of the thermal-hydraulic characteristics of passive safety systems (PSSs) was conducted using a system-integrated modular advanced reactor-integral test loop (SMART-ITL). The present passive safety injection system for the SMART-ITL consists of one train with the core makeup tank (CMT), the safety injection tank, and the automatic depressurization system. The objective of this study is to investigate the injection effect of the PSS on the small-break loss-of-coolant accident (SBLOCA) scenario for a 0.4 inch line break in the safety-injection system (SIS). The steady-state condition was maintained for 746 seconds before the break. When the major parameters of the target value and test results were compared, most of the thermal-hydraulic parameters agreed closely with each other. The water level of the reactor pressure vessel (RPV) was maintained higher than that of the fuel assembly plate during the transient, for the present CMT and safety injection tank (SIT) flow rate conditions. It can be seen that the capability of an emergency core cooling system is sufficient during the transient with SMART passive SISs.

Prediction of the Maximum Strain of Circular Concrete Columns Confined with Fiber Composites (섬유에 의하여 구속된 원형 콘크리트 기둥의 최대변형률 예측)

  • Lee, Jung-Yoon;Jeong, Hoon-Sik
    • Journal of the Korea Concrete Institute
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    • v.15 no.5
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    • pp.726-736
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    • 2003
  • Concrete columns confined with high-strength fiber composites can enhance its strength as well as maximum strain. In recent years, several equations have been developed to predict the behavior of the concrete columns confined with fiber composites. While the developed equations can predict the compressive strength of the confined columns with reasonable agreement, these equations are not successful in predicting the observed maximum strain of the columns. In this paper, a total of 61 test results is analysed to propose an equation to predict both compressive strength and maximum strain of concrete cylinders. The proposed equation takes into account the effects of confining pressure and cylinder size. Furthermore, in order to verify the proposed stress-strain curve for concrete cylinders, six cylindrical specimens were tested. Comparisons between the observed and calculated stress-strain curves of the tested cylinders showed reasonable agreement.

Experimental Study on Progressive Collapse Resisting Capacity of Reinforced Concrete Beam-Column Sub-assemblage (RC 보-기둥 요소의 연쇄붕괴 저항 거동에 대한 실험적 연구)

  • Choi, Hyun-Hoon;Kim, Jin-Koo;Park, Kyoung-Hoon;Jeon, Yong
    • Proceedings of the Computational Structural Engineering Institute Conference
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    • 2009.04a
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    • pp.450-453
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    • 2009
  • 본 논문에서는 지진하중을 고려하여 충분한 연성거동이 가능하도록 배근한 철근콘크리트 횡하중 저항 골조(내진상세)와 고정하중과 적재하중만을 고려하여 설계한 중력하중 저항 골조(일반상세)를 대상으로 외부기둥과 내부기둥에 연결된 보의 연쇄붕괴 거동을 평가하기 위한 실험을 수행하였다. 일방향 가력실험 결과에 따르면 내진상세의 경우 대변형 상태에서 보의 하단철근의 파단이후 상단 압축철근이 인장력을 부담하면서 전체 보 부재는 축인장력이 작용을 하면서 힘-변위 곡선은 상승하는 현수작용이 발현되었다. 그러나 일반상세의 경우 충분한 현수작용이 발현되기 전에 보의 주근이 정착된 외부기둥 접합부의 파괴로 인하여 저항내력이 감소하였다.

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