• 제목/요약/키워드: Commercial Finite Element Code

검색결과 269건 처리시간 0.021초

유한요소법에 의한 드럼 브레이크의 열탄성 접촉해석 (Thermoelastic Contact Analysis of Drums Brakes by Finite Element Method)

  • 구병춘;서정원
    • 한국자동차공학회논문집
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    • 제9권3호
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    • pp.173-180
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    • 2001
  • In the case of axisymmetric thermal analysis of drum brakes, the distribution of frictional heat produced on the interface and temperature difference between mating frictional faces are very interesting problems to computational researchers. In the first part, the influence of the s-cam load angles and elastic modulus of the pad on the contact pressure distribution between pad and drum was checked by a three dimensional model. In the second part heat conduction from the interface to the pad and the drum was modeled by using a thin interface element, so artificial division of the generated frictional heat between pad and drum is not necessary. Temperature difference between mating frictional faces is successfully modeled by using the interface element. The influence of some parameters on the thermal distribution is checked. The analysis was performed by ABAQUS/Standard code.

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추락낙하 사고 시 지면과의 충돌충격에 의하여 다양한 고준위폐기물 처분용기모델에 발생하는 응력에 대한 유한요소해석 비교연구 (Comparative Study of Finite Element Analysis for Stresses Occurring in Various Models of the Spent Nuclear Fuel Disposal Canister due to the Accidental Drop and Impact on to the Ground)

  • 권영주
    • 한국전산구조공학회논문집
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    • 제30권5호
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    • pp.415-425
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    • 2017
  • 고준위폐기물 처분용기를 처분장에서 처분 시 사고로 운송차량에서 추락낙하 하여 지면과 충돌하는 경우 처분용기에 가해지는 충격력에 의해 처분용기에 응력이 발생한다. 본 논문에서는 고준위폐기물 처분용기의 구조안전성 설계과정의 일환으로 이와 같은 충격력에 의하여 여러 가지 처분용기 모델에 발생하는 응력에 대한 비교연구를 수행하였다. 연구의 주된 내용은 이와 같은 비교연구를 통하여 구조적으로 건전한 처분용기의 설계에 관한 것이다. 처분장에서 운반차량으로 처분용기 운반 중 사고로 추락낙하 하여 지면과의 충돌 시에 처분용기에 가해지는 충격력은 기구동역학해석 상용 컴퓨터코드인 RecurDyn으로 구하였다. 이렇게 구한 충격력에 의하여 여러 가지 처분용기 모델에 발생하는 응력 및 변형은 유한요소해석상용 컴퓨터코드인 NISA를 이용하여 구하였다. 이 응력과 변형 값들의 비교 검토를 통하여 구조적으로 건전한 처분용기에 대한 연구를 수행하였다. 연구결과 처분용기 내부 고준위폐기물 다발을 감싸는 외곽 벽의 두께가 두꺼워 질수록 또는 처분용기의 직경이 커질수록 처분용기에 발생하는 응력이 커지는 것을 알 수 있었다. 그러나 처분용기에 가해지는 충격력도 처분용기의 직경이 커짐에 따라 증가하였다. 그럼에도 불구하고, 단위 충격력 당 발생하는 변형의 크기는 직경이 증가함에 따라 감소하였다. 따라서 결론적으로 직경이 증가할수록 처분용기는 구조적으로 건전함을 알 수 있었다.

열린 균열이 있는 보의 효율적 모델링 (An efficient modeling method for open cracked beam structures)

  • 김만달;최성환;홍성욱;이종원
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2002년도 추계학술대회논문집
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    • pp.725-730
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    • 2002
  • This paper presents an efficient modeling method for open cracked beam structures. An equivalent bending spring model is introduced to represent the structural weakening effect in the presence of open cracks. The proposed method adopts the exact dynamic element method (EDEM) to avoid the difficulty and numerical errors in association with re-meshing the structure. The proposed method is rigorously compared with a commercial finite element code. Experiments are also performed to validate the proposed modeling method. Finally, a diagnostic scheme for open cracked beam structures is proposed and demonstrated through a numerical example.

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균열이 있는 보의 모델링 및 동적 해석에 관한 연구 (A study on the Modeling and Dynamic Analysis of Cracked Beam Structures)

  • 홍성욱;김만달;이종원
    • 한국정밀공학회지
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    • 제20권6호
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    • pp.197-204
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    • 2003
  • This paper presents an efficient modeling and dynamic analysis method for open cracked beam structures. An equivalent bending spring model is introduced to represent the structural weakening effect in the presence of cracks. The proposed method adopts the exact dynamic element method (EDEM) to avoid the inconvenience and numerical errors in association with re-meshing the structural model with the crack position changed. The proposed modeling method is validated through a series of simulation and experiments. First, the proposed method is rigorously compared with a commercial finite element code. Then, two kinds of experiments are performed to validate the proposed modeling method. Finally, a diagnostic scheme fur open cracked beam structures is proposed and demonstrated through a numerical example.

Safety assessment of Generation III nuclear power plant buildings subjected to commercial aircraft crash Part II: Structural damage and vibrations

  • Qu, Y.G.;Wu, H.;Xu, Z.Y.;Liu, X.;Dong, Z.F.;Fang, Q.
    • Nuclear Engineering and Technology
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    • 제52권2호
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    • pp.397-416
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    • 2020
  • Investigations of the commercial aircraft impact effect on nuclear island infrastructures have been drawing extensive attention, and this paper aims to perform the safety assessment of Generation III nuclear power plant (NPP) buildings subjected to typical commercial aircrafts crash. At present Part II, based on the verified finite element (FE) models of aircrafts Airbus A320 and A380, as well as the NPP containment and auxiliary buildings in Part I of this paper, the whole collision process is reproduced numerically by adopting the coupled missile-target interaction approach with the finite element code LS-DYNA. The impact induced damage of NPP plant under four impact locations of containment (cylinder, air intake, conical roof and PCS water tank) and two impact locations of auxiliary buildings (exterior wall and roof of spent fuel pool room) are evaluated. Furthermore, by considering the inner structures in the containment and raft foundation of NPP, the structural vibration analyses are conducted under two impact locations (middle height of cylinder, main control room in the auxiliary buildings). It indicates that, within the discussed scenarios, NPP structures can withstand the impact of both two aircrafts, while the functionality of internal equipment on higher floors will be affected to some extent under impact induced vibrations, and A380 aircraft will cause more serious structural damage and vibrations than A320 aircraft. The present work can provide helpful references to assess the safety of the structures and inner equipment of NPP plant under commercial aircraft impact.

금속인장교정기의 공정변수 설계를 위한 탄소성 유한요소해석 (1)-단순모델 해석 (Elasto-plastic Finite Element Analysis for the Parametric Process Design of the Tension Leveller(1) -Unit Model Analysis)

  • 이형욱;허훈;박상래
    • 소성∙가공
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    • 제11권2호
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    • pp.138-146
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    • 2002
  • This paper is concerned with the simulation-based process design method involved non-steady state problem of tension levelling considering the elasto-plastic hardening behavior of a metallic strip by a commercial code ABAQUS/Standard. The tension levelling process is peformed to elongate the strip plastically in combination of tensile and bending strain by a controlled manner so that all longitudinal fibers in the strip have an approximately equal amount of length and undesirable strip shapes are corrected to the flat share. Objectives of this paper are the development of a general method for the design of a tension leveller by a finite element method and parameter studies for the deisgn variables such as the applied tension, the roll intermash includes the determination of the steady state using the simple unit of the tension levelling line and the effect of the finite element mesh size on the amount and distribution of the strain calculated. The analysis provides the information about the intermesh effect on the amount and final shapes of the strip and distribution of the strain in order to determine the amount elongation for correction of the irregular share.

풍선확장식 스텐트의 기계적 특성에 대한 유한요소해석 (Finite Element Analysis of Mechanical Properties of a Balloon-Expandable Stent)

  • 오병기;조해용;김용연
    • 대한기계학회논문집A
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    • 제28권7호
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    • pp.915-922
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    • 2004
  • A stent is small tube-like structure expanded into stenotic arteries to restore blood flow. The stent expansion behaviors define the effectiveness of the surgical operation. In this paper, finite-element method was employed to analyze expansion behaviors and fatigue life of a typical diamond-shaped balloon-expandable stent. Beyond safety considerations, this type of analysis provides mechanical properties that are often difficult to obtain by experiments. Mechanical properties of the stent expansion pressure, radial recoil, longitudinal recoil and foreshortening were simulated using commercial FEM code, ANSYS and fatigue life were estimated using NISAII ENDURE. The FEM results showed that the pressures necessary to expand the stent up to a diameter of 3mm, 4mm and 5mm were 0.75MPa, 0.82MPa and 0.97MPa. The fatigue lifes according to expansion diameter were 114${\times}$10$^{7}$cycles, 714${\times}$$^{6}$cycles and 163${\times}$10$^{6}$cycles. As a result, a finite element model used in this study can simulate expansion behaviors of stents and should be useful to design new stents or analyze actual stents.

베어링 지지 효과를 고려한 3차원 로터동역학 해석 (Three-dimensional Rotordynamic Analysis Considering Bearing Support Effects)

  • 박효근;김동만;김유성;김명국;전승배;김동현
    • 한국소음진동공학회논문집
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    • 제17권2호
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    • pp.105-113
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    • 2007
  • In this study, three-dimensional rotordynamic analyses have been conducted using equivalent beam, hybrid and full three-dimensional models. The present computational method is based on the general finite element method with rotating gyroscopic effects of the rotor system. General purpose commercial finite element code, SAMCEF which includes practical rotordynamics module with various types of rotor analysis tools and bearing elements is applied. For the purpose of numerical verification, comparison study for a benchmark rotor model with support bearings is performed first. Detailed finite element models based on three different modeling concepts are constructed and then computational analyses are conducted for the realistic and complex three-dimensional rotor system. The results for rotor stability and mass unbalance response are presented and compared with the experimental vibration test data conducted herein.

원자로 노심 쉬라우드의 조사유기응력부식균열 민감도 예비 분석 (Preliminary Analysis on IASCC Sensitivity of Core Shroud in Reactor Pressure Vessel)

  • 김종성;박창제
    • 한국압력기기공학회 논문집
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    • 제15권2호
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    • pp.58-63
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    • 2019
  • This paper presents preliminary analysis and results on IASCC sensitivity of a core shroud in the reactor pressure vessel. First, neutron irradiation flux distribution of the reactor internals was calculated by using the Monte Carlo simulation code, MCNP6.1 and the nuclear data library, ENDF/B-VII.1. Second, based on the neutron irradiation flux distribution, temperature and stress distributions of the core shroud during normal operation were determined by performing finite element analysis using the commercial finite element analysis program, ABAQUS, considering irradiation aging-related degradation mechanisms. Last, IASCC sensitivity of the core shroud was assessed by using the IASCC sensitivity definition of EPRI MRP-211 and the finite element analysis results. As a result of the preliminary analysis, it was found that the point at which the maximum IASCC sensitivity is derived varies over operating time, initially moving from the shroud plate located in the center of the core to the top shroud plate-ring connection brace over operating time. In addition, it was concluded that IASCC will not occur on the core shroud even after 60 years of operation (40EFPYs) because the maximum IASCC sensitivity is less than 0.5.

유한요소해석에 의한 헤밍 공정 변수연구 (A Parametric Study of the Hemming Process by Finite Element Analysis)

  • 김형종;최원목;임재규;박춘달;이우홍;김헌영
    • 대한기계학회논문집A
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    • 제28권2호
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    • pp.149-157
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    • 2004
  • Implicit finite element analysis of the flat surface-straight edge hemming process is performed by using a commercial code ABAQUS/Standard. Methods of finite element modeling for springback simulation and contact pair definition are discussed. An optimal mesh system is chosen through the error analysis that is based on the smoothing of discontinuity in the state variables. This study has focused on the investigation of the influence of process parameters in flanging, pre-hemming and main hemming on final hem quality, which can be defined by turn-down, warp and roll-in. The parameters adopted in this parametric study are flange length, flange angle, flanging die corner radius, face angle and insertion angle of pre-hemming punch, and over-stroke of pre-hemming and main hemming punches.