• Title/Summary/Keyword: Through-wall Crack

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Assesment on the Characteristics of Foundation Bearing Capacity in Reinforced Soil Wall Structure of Large Scale (대규모 보강토옹벽 구조물에서의 기초지반 지지력특성 평가)

  • Han, Jung-Geun;Yoo, Seung-Kyung;Cho, Sam-Deuk;Lee, Kyang-Woo;Hong, Ki-Kwon
    • Journal of the Korean Geosynthetics Society
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    • v.5 no.1
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    • pp.9-14
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    • 2006
  • The reinforced soil retaining wall structures of serious types with environmental are widely expanding more and more in Korea, which divided conventional type's reinforced soil retaining wall on segmental retaining wall. The causes of most crack occurred at block in reinforced soil retaining wall structure caused by the differential settlement of foundation. It is difference of settlement for significant factor that with overall slope stability. In this study, design assessment of foundation bearing capacity related to differential settlement of foundation ground was considered. And, also, through case study, the countermeasure methods and its application were suggested that the bearing capacity of foundation had to stabilize. The foundation ground in charge of bearing capacity should be affected by the resisting force of sliding, because the foundation parts of reinforced soil retaining wall were belongs to potential slope sliding area in overall stabilizing including retaining wall structures. Therefore, the analyzing or the designing of bearing capacity for foundation should be considered control capacity on the overall slope sliding.

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EVALUATION AND TEST OF A CRACK INITIATION FOR A 316 SS CYLINDRICAL Y-JUNCTION STRUCTURE IN A LIQUID METAL REACTOR

  • Park, Chang-Gyu;Kim, Jong-Bum;Lee, Jae-Han
    • Nuclear Engineering and Technology
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    • v.38 no.3
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    • pp.293-300
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    • 2006
  • A liquid metal reactor (LMR) operated at high temperatures is subjected to both cyclic mechanical loading and thermal loading; thus, creep-fatigue is a major concern to be addressed with regard to maintaining structural integrity. The Korea Advanced Liquid Metal Reactor (KALIMER), which has a normal operating temperature of $545^{\circ}C$ and a total service life time of 60 years, is composed of various cylindrical structures, such as the reactor vessel and the reactor baffle. This study focuses on the creepfatigue crack initiation for a cylindrical Y-junction structure made of 316 stainless steel (SS), which is subjected to cyclic axial tensile loading and thermal loading at a high-temperature hold time of $545^{\circ}C$. The evaluation of the considered creep-fatigue crack initiation was carried out utilizing the ${\sigma}_d$ approach of the RCC-MR A16 guide, which is the high-temperature defect assessment procedure. This procedure is based on the total accumulated strain during the service time. To confirm the evaluated result, a high-temperature creep-fatigue structural test was performed. The test model had a circumferential through wall defect at the center of the model. The defect front of the test model was investigated after the $100^{th}$ cycle of the testing by utilizing a metallurgical inspection technique with an optical microscope, after which the test result was compared with the evaluation result. This study shows how creep-fatigue crack initiation for a high-temperature structure can be predicted with conservatism per the RCC-MR A16 guide.

Ductile Failure Simulation of Tensile Plates with Multiple Through-Wall Cracks Based on Damage Mechanics (유한요소 손상 해석을 이용한 다중 관통균열 인장시편의 연성 파괴 시뮬레이션)

  • Jeon, Jun-Young;Kim, Nak-Hyun;Oh, Chang-Sik;Kim, Yun-Jae
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.36 no.3
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    • pp.245-252
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    • 2012
  • This paper proposes a simple numerical method, based on the stress-modified fracture strain-damage model with the stress-reduction technique, for predicting the failure behaviors of ductile plates with multiple through-wall cracks. This technique is implemented using the user-defined subroutines provided in ABAQUS. For validation, the results simulated using the proposed method are compared with published experimental data of Japanese researchers.

Application of enhanced Reference Stress Method to Nuclear Piping LBB Analysis : Finite Element Validation (원자력 배관의 파단전누설 해석을 위한 개선된 참조응력법의 수치해석적 검증)

  • Heo, Nam-Su;Kim, Yun-Jae;Kim, Yeong-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.25 no.4
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    • pp.741-747
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    • 2001
  • Three-dimensional, elastic-plastic finite element analyses for circumferential through-wall cracked pipes are performed using actual tensile data of stainless steels, for two purposes. The first one is to validate the recently-proposed enhanced reference stress (ERS) method to estimate the J-integral and COD for circumferential through-wall cracked pipes. The second one is to compare those results with the GE/EPRI estimations. It is found that the J-integral and COD estimations according to the GE/EPRI method can be very sensitive to how the stress-strain data are fitted using the Ramberg-Osgood relation. Moreover, no tendency can be found regarding the most appropriate fitting range for the Ramberg-Osgood fit. On the contrary, the J-integral and COD estimations based on the ERS method give more accurate results than the GE/EPRI estimation. The present results provide confidence in applying the proposed method to the Leak-Before-Break(LBB) analysis.

Plastic Limit Loads for Slanted Circumferential Through-Wall Cracked Pipes Using 3D Finite-Element Limit Analyses (3차원 유한요소 한계해석을 이용한 원주방향 경사관통균열 배관의 소성한계하중)

  • Jang, Hyun-Min;Cho, Doo-Ho;Kim, Young-Jin;Huh, Nam-Su;Shim, Do-Jun;Choi, Young-Hwan;Park, Jung-Soon
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.35 no.10
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    • pp.1329-1335
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    • 2011
  • On the basis of detailed 3D finite-element (FE) limit analyses, the plastic limit load solutions for pipes with slanted circumferential through-wall cracks (TWCs) subjected to axial tension, global bending, and internal pressure are reported. The FE model and analysis procedure employed in the present numerical study were validated by comparing the present FE results with existing solutions for plastic limit loads of pipes with idealized TWCs. For the quantification of the effect of slanted crack on plastic limit load, slant correction factors for calculating the plastic limit loads of pipes with slanted TWCs from pipes with idealized TWCs are newly proposed from extensive 3D FE calculations. These slant-correction factors are presented in tabulated form for practical ranges of geometry and for each set of loading conditions.

A CONFOCAL LASER SCANNING MICROSCOPIC STUDY ON THE INTERFACE BETWEEN TOOTH COLORED RESTORATIVE MATERIALS AND DENTIN (공초점레이저주사현미경을 이용한 심미수복재와 상아질의 접착계면에 관한 연구)

  • Park, Byung-Chul;Cho, Young-Gon;Moon, Joo-Hoon
    • Restorative Dentistry and Endodontics
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    • v.25 no.3
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    • pp.313-320
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    • 2000
  • The purpose of this study was to evaluate on the interfacial morphology between dentin and restorative materials. In this in vitro study, the cavity wall restorated with 3 different kinds of tooth colored restorative materials [resin-modified Glass Ionomer cement (Fuji II LC), composite resin (Z-100), compomer (Dyract)]. The thirty extracted human molar teeth without caries and/or restorations are used. The experimental teeth were randomly divided into three groups of ten teeth each. In each group, Wedge shaped cavities (width: 3mm, length: 2mm, depth: 1.5mm) were prepared at the cementoenamel junction on buccal and lingual surfaces. The adhesive of composite resin were mixed with rhodamine B. Primer of composite resin, Prime & Bond 2.1 of Dyract and liquid of Fuji II LC were mixed with fluorescein. In group 1, the cavity wall was treatment with dentin conditioner, and then restorated with Fuji II LC. In group 2, the cavity wall was treatment with Prime & Bond 2.1 and then restorated with Dyract. In group 3, the cavity wall was etching with 10% maleic acid, applied with primer and bonding agent and then restorated with Z-100. The interface between dentin and restorative materials was observed by fluoresence imaging with a confocal laser scanning microscope. The results were as follows : 1. In Glass ionomer group, adaptation of resin modified Glass-ionomer restoration against cavity wall is tight, but the crack formed inside of restoration were observed. 2. In Dyract group, the penetration of resin tag is shorter and the width of hybrid layer is narrower than composite resin group. 3. In Z-100 group, primer penetrated deeply through dentinal tubule. Also bonding agent was penetrated along the primer, but the penetration length is shorter than primer part, and in 3-D image, the resin tag is conical shape and lateral branch is observed.

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Design Approach of Large-scale Experimental Facilities Reflect the Load Flow (하중흐름을 통한 대형구조실험용 반력시설물의 설계)

  • Lee, Sung-Eun;Ko, Dong-Woo
    • Journal of Korean Association for Spatial Structures
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    • v.16 no.2
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    • pp.69-77
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    • 2016
  • The purpose of this study is to present a method that can estimate the height of reaction facilities for large structural experiment through load flow as primary design procedure. The characteristic of the load transmission according to the type of experiment was analyzed to obtain tensile and compressive forces occurring on the reaction facilities. Strong walls that are affected by the bending moment is applied the post-tensioning method, and the strong floor under the control of the tension and compression is designed in accordance with the load flow. And the optimum cross-section of the reaction facilities was obtained by comparing the stresses of the tensile stress and crack the concrete. Through validating elastic analysis, the design results were satisfied a given design conditions.

Development of a Three Dimensional Elastic Plastic Analysis System for the Integrity Evaluation of Nuclear Power Plant Components (원자력발전소 주요기기의 건전성 평가를 위한 3차원 탄소성 해석 시스템의 개발)

  • Huh, Nam-Su;Im, Chang-Ju;Kim, Young-Jin;Pyo, Chang-Ryul;Park, Chi-Yong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.24 no.8 s.179
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    • pp.2015-2021
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    • 2000
  • In order to evaluate the integrity of nuclear power plant components, the analysis based on fracture mechanics is crucial. For this purpose, finite element method is popularly used to obtain J-integral. However, it is time consuming to design the finite element model of a cracked structure. Also, the J-integral should be verified by alternative methods since it may differ depending on the calculation method. The objective of this paper is to develop a three-dimensional elastic-plastic J-integral analysis system which is named as EPAS program. The EPAS program consists of an automatic mesh generator for a through-wall crack and a surface crack, a solver based on ABAQUS program, and a J-integral calculation program which provides DI (Domain Integral) and EDI (Equivalent Domain Integral) based J-integral calculation. Using the EPAS program, an optimized finite element model for a cracked structure can be generated and corresponding J-integral can be obtained subsequently.

Stress checklist of box girder structure based on spatial grid analysis method

  • Ni, Ying-sheng;Li, Ming;Xu, Dong
    • Computers and Concrete
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    • v.27 no.5
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    • pp.407-416
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    • 2021
  • The checking stresses in the Chinese codes for reinforced concrete (RC) or prestressed concrete (PC) bridges are aimed for the thin-web beam, which cannot reflect the actual behavior of the modern structures. The incompleteness of the checking stresses could give rise to the deficiency in the design and calculation, and unable to reveal the reason of some common cracks in the structure. In this paper, the complete stress checklist for RC or PC girder bridges are listed, as well as the corresponding crack shapes. The expression of the complete checking stresses is proposed in details. Spatial Grid Model can reflect all the concerned stresses in the structure. Through the comparison of the calculation results from the spatial grid model and the solid model, it is seen that the spatial grid model can reflect load effects such as shear lag effect, thin-wall effect and local effect. The stresses obtained from the spatial grid model could help engineers to have a good understanding of the structural behavior. Meanwhile, the stress checklist provides the information for analyzing and solving the deficiency in the structure.

A study on the optimization of manufacturing processes of double wall bellows for dual fuel engine II - Optimization of welding process - (Dual Fuel 엔진용 이중관 벨로우즈 제작 공정의 최적화에 관한 연구 II - 용접공정의 최적화 -)

  • Kim, Pyung-Su;Kim, Jong-Do;Song, Moo-Keun
    • Journal of Advanced Marine Engineering and Technology
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    • v.40 no.6
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    • pp.504-509
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    • 2016
  • Production processes of double wall bellows can be roughly categorized into two steps. In the first step, inner and outer bellows are made of STS316L in austenite stainless steel due to their excellent formability and corrosion resistance. In the second step, the double wall bellows are manufactured using the welding method with both the inner and outer bellows. The microstructure and defects of each weldment are observed to ensure the reliability of bellows since weldment is a highly vulnerable part, which can crack and fracture when bellows are formed or used. In this study, optimum welding conditions were derived from the analysis of microstructure and inspection of weldment of bellows that were produced using various welding procedure. Moreover, the mechanical properties were evaluated through hardness measurement of substrate, weldment and the heat-affected zone.