• Title/Summary/Keyword: Fracture intensity

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Development of Analytical Simulation Model for Fatigue Crack Propagation : Crack Closure Behavior Modeling (균열개폐구 거동을 고려한 피로균열전파 해석 모델의 개발 : 균열 개폐구 거동의 모형화)

  • C.W. Kim;I.S. Nho;H.H. Van;B.C. Shin
    • Journal of the Society of Naval Architects of Korea
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    • v.38 no.3
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    • pp.74-83
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    • 2001
  • After the concept of fracture mechanics was applied to fatigue crack propagation by Paris. Paris' law is widely used to predict fatigue crack growth behavior. Since Elber proposed the effective stress intensity factor(SIF) and showed a good agreement with experimental results using the proposed SIF, emphasis in crack propagation studies has been placed on measuring the effective stress range ratio. This paper proposes a numerical model to simulate the crack closure and propagation behaviour under various loading spectrum. The validity of the proposed model is checked by comparing with the Toyosada numerical solutions on the crack propagation behaviour. Important insights developed are summarized.

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Design and fabrication of capsules with isotropic destruction intensity (등방 파괴 강도를 갖는 캡슐 설계 및 제작)

  • Lim, Tae-Uk;Cheng, Hao;Hu, Jie;Wang, Shu-Le;Jung, Won-Suk
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2022.04a
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    • pp.247-248
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    • 2022
  • 3D printer-based self-healing capsules have been proposed to heal cracks by enabling various structural designs, repeatable fabrication, and strength analysis of the capsules. The Fusion Deposition Modeling (FDM) method was used to design, analyze, and produce new self-healing capsules that are widely used at low cost. However, PLA extruded from FDM has low interlayer adhesion energy, and thus strength varies depending on the angle of load applied to the laminated layer and the concrete structure, thereby degrading the performance of the self-healing capsule. Therefore, in this paper, the structure of the capsule manufactured by the FDM PLA method has isotropic strength was designed. In addition, the fracture strength in the x, y, and z directions of the load applied through the compression test was analyzed. As a result, it was confirmed that the newly proposed capsule design has an isotropic fracture strength of 1400% in all directions compared to the existing spherical thin-film capsule.

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fiber Orientation Effects on the Acoustic Emission Characteristics of Class fiber-Reinforced Composite Materials (유리섬유강화 복합재의 AR특성에 대한 섬유배향 효과)

  • Kim, Jung-Hyun;Woo, Sung-Choong;Choi, Nak-Sam
    • Journal of the Korean Society for Nondestructive Testing
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    • v.23 no.5
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    • pp.429-438
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    • 2003
  • The effects of fiber orientation on acoustic emission(AE) characteristics have been studied for the unidirectional and satin-weave, continuous glass-fiber reinforced plastic(UD-GFRP and SW-GFRP) tensile specimens. Reflection and transmission optical microscopy was used for investigation of the damage zone of specimens. AE signals were classified as different types by using short time fourier transform(STFT) : AE signals with high intensity and high frequency band were due to fiber fracture, while weak AE signals with low frequency band were due to matrix and interfacial cracking. The feature in the rate of hit-events having high amplitudes showed a process of fiber breakages, which expressed the characteristic fracture processes of individual fiber-reinforced plastics with different fiber orientations and with different notching directions. As a consequence, the fracture behavior of the continuous GFRP could be monitored as nondestructive evaluation(NDE) through the AE technique.

Failure Probability Estimation of Flaw in CANDU Pressure Tube Considering the Dimensional Change (가동중 중수로 압력관의 외경과 두꼐 변화를 고려한 결함의 파손확률 예측)

  • Kwak, Sang-Log;Lee, Joon-Seong;Kim, Young-Jin;Park, Youn-Won
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.26 no.11
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    • pp.2305-2311
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    • 2002
  • The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle and heavy water coolant. Pressure tubes are installed horizontally inside the reactor and only selected samples are periodically examined during in-service inspection. In this respect, a probabilistic safety assessment method is more appropriate fur the assessment of overall pressure tube safety. The failure behavior of CANDU pressure tubes, however, is governed by delayed hydride cracking which is the major difference from pipings and reactor pressure vessels. Since the delayed hydride cracking has more widely distributed governing parameters, it is impossible to apply a general PFM methodology directly. In this paper, a PFM methodology for the safety assessment of CANDU pressure tubes is introduced by applying Monte Carlo simulation in determining failure probability Initial hydrogen concentration, flaw shape and depth, axial and radial crack growth rate and fracture toughness were considered as probabilistic variables. Parametric study has been done under the base of pressure tube dimension and hydride precipitation temperature in calculating failure probability. Unstable fracture and plastic collapse are used for the failure assessment. The estimated failure probability showed about three-order difference with changing dimensions of pressure tube.

Round robin analysis of vessel failure probabilities for PTS events in Korea

  • Jhung, Myung Jo;Oh, Chang-Sik;Choi, Youngin;Kang, Sung-Sik;Kim, Maan-Won;Kim, Tae-Hyeon;Kim, Jong-Min;Kim, Min Chul;Lee, Bong Sang;Kim, Jong-Min;Kim, Kyuwan
    • Nuclear Engineering and Technology
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    • v.52 no.8
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    • pp.1871-1880
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    • 2020
  • Round robin analyses for vessel failure probabilities due to PTS events are proposed for plant-specific analyses of all types of reactors developed in Korea. Four organizations, that are responsible for regulation, operation, research and design of the nuclear power plant in Korea, participated in the round robin analysis. The vessel failure probabilities from the probabilistic fracture mechanics analyses are calculated to assure the structural integrity of the reactor pressure vessel during transients that are expected to initiate PTS events. The failure probabilities due to various parameters are compared with each other. All results are obtained based on several assumptions about material properties, flaw distribution data, and transient data such as pressure, temperature, and heat transfer coefficient. The realistic input data can be used to obtain more realistic failure probabilities. The various results presented in this study will be helpful not only for benchmark calculations, result comparisons, and verification of PFM codes developed but also as a contribution to knowledge management for the future generation.

Round Robin Analysis for Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock

  • Jhung Myung Jo;Jang Changheui;Kim Seok Hun;Choi Young Hwan;Kim Hho Jung;Jung Sunggyu;Kim Jong Min;Sohn Gap Heon;Jin Tae Eun;Choi Taek Sang;Kim Ji Ho;Kim Jong Wook;Park Keun Bae
    • Journal of Mechanical Science and Technology
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    • v.19 no.2
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    • pp.634-648
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    • 2005
  • Performed here is a comparative assessment study for the probabilistic fracture mechanics approach of the pressurized thermal shock of the reactor pressure vessel. A round robin consisting of one prerequisite deterministic study and five cases for probabilistic approaches is proposed, and all organizations interested are invited. The problems are solved by the participants and their results are compared to issue some recommendation of best practices and to assure an understanding of the key parameters in this type of approach, like transient description and frequency, material properties, defect type and distribution, fracture mechanics methodology etc., which will be useful in the justification through a probabilistic approach for the case of a plant over-passing the screening criteria. Six participants from 3 organizations responded to the problem and their results are compiled and analyzed in this study.

Cure Behaviors and Mechanical Interfacial Properties of Epoxy/Polyurethane Blends Initiated by Latent Thermal Catalyst (열잠재성 개시제에 의한 에폭시/폴리우레탄 블렌드의 경화거동 및 파괴인성)

  • Park, Soo-Jin;Seok, Su-Ja;Kang, Jun-Gil;Kwon, Soo-Han
    • Elastomers and Composites
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    • v.39 no.1
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    • pp.42-50
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    • 2004
  • In this work, the diglycidylether of bisphenol A (DGEBA) and modified polyurethane (PU) blends were initiated by N-benzylpyrazinium hexafluoroantimonate (BPH). The cure and fracture toughness of neat DGEBA with the addition of PU were investigated. The cure properties of DGEBA/PU blend system were examined by DSC and near-IR measurements. The fracture touhtness were investigated by measuring the critical stress intensity factor ($K_{IC}$) and the critical strain energy release rate ($G_{IC}$). According to the results, the maximum values of owe activation energy ($E_a$) and conversion (${\alpha}$) were found at 10 phr of PU. Also the $K_{IC}$ showed a similar behavior with the results of conversion. These results were probably due to increase of crosslinking density in the blends resulted from increase of the hydrogen bonding between the hydroxyl groups of DGEBA and isocyanate groups of PU.

Thermal Properties and Fracture Toughness of Bisphenol-Based DGEBA/DGEBS Epoxy Blend System (Bisphenol계 DGEBA/DGEBS 에폭시 블렌드 시스템의 열적 특성 및 파괴인성)

  • 박수진;김범용;이재락;신재섭
    • Polymer(Korea)
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    • v.27 no.1
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    • pp.33-39
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    • 2003
  • In this study, the bisphenol-based DGEBA/GEBS blend systems were studied in cure kinetics, thermal stabilities, and fracture toughness of the casting specimen. The content of DGEBA/DCEBS was varied in 100 : 0, 90 : 10, 80 : 20, 70 : 30, and 60 : 40 wt%. The cure activation energies ($E_a$) of the blend systems were determined by Ozawa's equation. The thermal stabilities, including initial decomposed temperature (IDT), temperatures of maximum rate of degradation ($T_{max}$), and integral procedural decomposition temperature (IPDT) of the cured specimen were investigated by thermogravimetric analysis (TGA). For the mechanical interfacial properties of the specimens, the critical stress intensity factor ($K_{IC}$) test was performed and their fractured surfaces were examined by using a scanning electron microscope (SEM). As a result, $E_a$, IPDT, and $K_{IC}$ show maximum values in the 20 wt% DGEBS content compared with the neat DGEBA resins. This was probably due to the fact that the elevated networks were farmed by the introduction of sulfonyl groups of the DCEBS resin.

A Study on the Fracture Behavior of a Crack in 9% Ni Steel Considering Constraint Effect (구속효과를 고려한 9% Ni강 균열의 파괴거동 해석에 관한 연구)

  • Kim, Young Kyun;Yoon, Ihn soo;Kim, Jae Hoon
    • Journal of the Korean Institute of Gas
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    • v.25 no.6
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    • pp.14-21
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    • 2021
  • Inner shell material of LNG storage tanks that store ultra-low temperature LNG at -162℃ requires structural integrity assessment of a crack-like defect. From the viewpoint of conventional fracture mechanics, the assessment has mainly performed by single parameter using stress intensity factor K, J-integral and CTOD. However, the stresses in a material of crack tip are not unique caused by constraint loss due to size and geometry of the structure. Various attempts have been made to complement a single parameter fracture mechanics, typically with Q-stress. In this paper, we have performed a two-parameter approach by deriving the Q-stress coupling with J-integral suitable for the evaluation of the crack tip stress field in the non-linear elastic region. A quantitative evaluation of the constraint effect has performed by using the J-Q approach. It was evaluated that the SENB type specimen had a crack ratio of 0.1 to 0.7 and the wide type specimen had a crack ratio of 0.2 to 0.6.

FATIGUE DESIGN OF BUTT-WELDED TUBULAR JOINTS

  • Kim, D. S.;S. Nho;F. Kopp
    • Proceedings of the KWS Conference
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    • 2002.10a
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    • pp.127-132
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    • 2002
  • Recent deepwater offshore structures in Gulf of Mexico utilize butt welded tubular joints. Application of welded tubular joint includes tendons, production risers, and steel catenary risers. Fatigue life assessment of these joints becomes more critical because the structures to which they are attached are allowed to undergo cyclic and sometimes large displacements around an anchored position. Estimating the fatigue behavior of these tubular members in the design stage is generally conducted by using S-N curves specified in the codes and standards. Applying the stress concentration factor of the welded structure to S-N approach often results in very conservative assessment because the stress field acting on the tubular has a non-uniform distribution through the thickness. Fracture mechanics and fitness for service (FFS) technology have been applied in the design of the catenary risers. This technology enables the engineer to establish proper requirements on weld quality and inspection acceptance criteria to assure satisfactory structural integrity during its design life. It also provides guidance on proper design curves to be used and a methodology for accounting for the effects of non-uniform stress distribution through the wall thickness. An attempt was made to develop set of S-N curves based on fracture mechanics approach by considering non-uniform stress distribution and a threshold stress intensity factor. Series of S-N curves generated from this approach were compared to the existing S-N curves. For flat plate butt joint, the S-N curve generated from fracture mechanics matches with the IIW class 100 curve when initial crack depth was 0.5 mm (0.02"). Similar comparison with API X′ was made for tubular joint.. These initial crack depths are larger than the limits of inspection by current Non-destructive examination (NDE) means, such as Automatic Ultrasonic Inspection (AUT). Thus a safe approach can be taken by specifying acceptance criteria that are close to limits of sizing capability of the selected NDE method. The comparison illustrates conservatism built into the S-N design curve.

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