• Title/Summary/Keyword: Thermal crack

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A Study on Thermal Shock Characterization of Composite (복합재료의 열충격 특성 평가)

  • Lee Jin Kyung;Park Young Chul;Lee Joon Hyun;Lee Sang Pill
    • Proceedings of the Korean Society For Composite Materials Conference
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    • 2004.10a
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    • pp.246-249
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    • 2004
  • A smart material is used as spectacle frames and brassiere frames, and partly in medical supplies because of its shape memory effect. The smart composite can be used on the wing of an airplane instead of the existing aluminium to control crack propagation. In this study, the smart composite was fabricated by a hot press method. TiNi alloy as reinforcement and A16061 as matrix were used, respectively. The mechanical properties of the smart composite under thermal shock cycles were evaluated. In addition, Acoustic Emission techniques were also used to clarify the damage behavior of the smart composite under thermal shock cycles nondestructive.

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Numerical analysis of post welding heat treatment base on the thermal creep elastic-plastic theory (점열탄소성 이론에 의한 용접후열처리에 대한 수치해석)

  • 방한서;차용훈;오율권;노찬승;김종명
    • Journal of Ocean Engineering and Technology
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    • v.11 no.1
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    • pp.113-123
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    • 1997
  • The welding residual stresses produced by welding frequently cause a crack and promote stress corrosion etc. in heat affected zone contained with external load and weakness of material. For the purpose pof relaxation of welding residual stress, post welding heat teratment(PWHT) is widely used. In this paper, the computer program which is based on Thermal-Elasto-plastic-creep theory for plane deformation on developed by finite element method (F.E.M) and verified its propriety by experimental measurement and also by using the developed computer program. The mechanical behavior of butt welding joint is clairfied during PWHT.

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Thermal Stability of 2.5Y-TZP under Low-Temperature Aging (2.5Y-TZP의 안정성에 관한 연구)

  • 장성도;오경영
    • Journal of the Korean Ceramic Society
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    • v.27 no.2
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    • pp.226-232
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    • 1990
  • The degradation phenomena and thermal stability of 2.5Y-TZP at low-temperature were studied by means of XRD, Raman spectra and microstructural analysis. The degradation of heat-treated 2.5Y-TZP at 20$0^{\circ}C$-20hr in air was observed on the TZP surface, be caused by the cracks generated from tlongrightarrowm transformation, and the cracks was propagated inside the polycrystalline body. The ZrO2 grain boundaries and grains near the crack were revealed as if these were diffused and dissolved. And it was also observed mlongrightarrowt transformation as the degraded TZP was refired at 140$0^{\circ}C$, and it was thought to be the fact that the moisture in atmosphere during the aging process contributed to the degradation. The thermal stability of 2.5Y-TZP was improved dramatically with an addition of 3w/o CeO2 or a provision of high Y2O3 concentration on the TZP surface.

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Probabilistic Integrity Analysis of Reactor Pressure Vessel under Pressurized Thermal Shock (가압열충격을 받는 원자로압력용기의 확률론적 건전성 해석)

  • Kim, Jong-Wook;Huh, Nam-Su;Yoo, Yeon-Sik;Kim, Tae-Wan
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.727-728
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    • 2008
  • The objective of this study is to evaluate the integrity for a reactor pressure vessel under the pressurized thermal shock by applying the probability fracture mechanics. A semi-elliptical axial crack is assumed to be in the beltline region of the reactor pressure vessel. The selected random variables are the neutron fluence on the vessel inside surface, the content of copper, nickel, and phosphorus in the reactor pressure vessel material, and initial RTNDT. The probabilistic integrity analysis was performed using the Monte Carlo simulation.

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Fracture Mechanics Analysis of Reactor Pressure Vessel Under Pressurized Thermal Shock-The Effect of Elastic-Plastic Behavior and Stainless Steel Cladding- (원자로 용기의 가압열충격에 대한 파괴역학 해석 - 탄소성 거동과 클래드부의 영향 -)

  • Ju, Jae-Hwang;Gang, Gi-Ju;Jeong, Myeong-Jo
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.26 no.1
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    • pp.39-47
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    • 2002
  • Performed here is an assessment study for deterministic fracture mechanics analysis of a pressurized thermal shock(PTS). The PTS event means an event or transient in pressurized water reactors(PWRs) causing severe overcooling(thermal shock) concurrent with or followed by significant pressure in the reactor vessel. The problems consisting of two transients and 10 cracks are solved and maximum stress intensity factors and maximum allowable nil-ductility reference temperatures are calculated. Their results are compared each other to address the general characteristics between transients, crack types and analysis methods. The effects of elastic-plastic material behavior and clad coating on the inner surface are explored.

Evaluation Method of Adhesive Fracture Toughness Based on Double Cantilever Beam (DCB) Tests Including Residual Thermal Stresses

  • Yokozeki, Tomohiro;Ogasawara, Toshio
    • Advanced Composite Materials
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    • v.17 no.3
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    • pp.301-317
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    • 2008
  • The energy release rate associated with crack growth in adhesive double cantilever beam (DCB) specimens, including the effect of residual stresses, was formulated using beam theory. Because of the rotation of the asymmetric arms in the adhesive DCB specimens due to temperature change, it is necessary to correct the evaluated fracture toughness of the DCB specimens, specifically in the case of a large temperature change. This study shows that the difference between the true toughness and an apparent toughness due to the consequence of ignoring residual stresses can be calculated for a given specimen geometry and thermo-mechanical properties (e.g. coefficient of thermal expansion). The calculated difference in the energy release rates based on the present correction method is compared with that from FEM in order to verify the present correction method. The residual stress effects on the evaluation of the adhesive fracture toughness are discussed.

Analysis Study for the Determination of Optimized Block Size in Mass Concrete (매스콘크리트에서 최적의 타설 단면 결정을 위한 해석적 연구)

  • 김진근;김상철;이두재;김국한
    • Proceedings of the Korea Concrete Institute Conference
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    • 1997.04a
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    • pp.422-429
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    • 1997
  • Thermal stress induced by hydration heat may produce cracks in mass concrete structure, which can result in structural problems as well as bad appearance. To minimize crack occurrence in massive structural, thus, the study put an emphasis on the determination of optimized lift height and block size. In the parametric study different sizes and lift heights were used to measure the magnitudes of hydration heat and thermal stresses for 3 different types of concrete fabricated with 1 pure cement and 2 blended Portland cements. As a result of analysis. it was found that magnitude of hydration heat and the occurrence of thermal cracks depend on the restriction conditions and material characteristics, especially adiabatic material parameters. It was also found that optimized lift height and block size can be determined from an appropriate combination of the degree of inner and outer structural restrictions.

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Thermal Stress Analysis on the Heat of Hydration Considering Creep and Shrinkage Effects of Mass Concrete (크리이프와 건조수축영향을 고려한 매스콘크리트에서 수화열에 대한 온도응력해석)

  • 김진근;김국한
    • Proceedings of the Korea Concrete Institute Conference
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    • 1992.04a
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    • pp.107-113
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    • 1992
  • The heat of hydration of cement the causes the internal temperature rise at early age, particulary in massive concrete structures such as a mat-slab of nuclear reactor building or a dam or a large footing. As the result of the temperature rise and restraint of foundation, the thermal stress enough to induce concrete cracks can occur. Therefore, the prediction of the thermal stress is very important in the design and construction stages in order to control the cracks developed in massive concrete structures. And, more creep and shrinkage take place at elevated temperatures in young concrete, Thus the effect of creep and shrinkage must be considered for checking the safety and servicebility(crack, durability and leakage).

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Fracture Mechanics Analysis of a Reactor Pressure Vessel Considering Pressurized Thermal Shock (가압열충격을 고려한 원자로 압력용기의 파괴역학적 해석)

  • 박재학;박상윤
    • Journal of the Korean Society of Safety
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    • v.16 no.4
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    • pp.29-38
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    • 2001
  • The purpose of this paper is to evaluate the structural integrity of a reactor pressure vessel subjected to the pressurized thermal shock(PTS) during the transient events, such as main steam line break(MSLB) and small break loss of coolant accident(SBLOCA). For postulated surface or subsurface cracks, variation curves of stress intensity factor are obtained by using the three different methods, including ASME section XI code anlysis, the finite element alternating method and the finite element method. From the stress intensity factor curves, the maximum allowable nil-ductility transition temperatures(RT/NDT/) are determined by the tangent criterion and the maximum criterion for various crack configurations and two initial transient events. As a result of the analysis, it is noted that axial cracks have smaller maximum allowable RT$_{NDT}$ values than same-sized circumferential cracks for both the transient events in the case of the tangent criterion. Axial cracks have smaller RT$_{NDT}$ values than same-sized circumferential cracks for MSLB and circumferential cracks have smaller values than axial cracks for SBLOCA in the case of the maximum criterion.

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Study on the Thermal Degradation Properties of Epoxy Resin for the Cast Resin Transformer (몰드변압기용 에폭시 수지의 열 열화 특성에 관한 연구)

  • Nam, K.D.;Jung, J.I.;Huh, C.S.
    • Proceedings of the KIEE Conference
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    • 2000.07c
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    • pp.1572-1574
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    • 2000
  • In this paper, study on the properties of the thermal degradated epoxy resin which is used in cast resin transformer is performed to investigate the problems of the decreasing insulation characteristics and crack in the cast resin transformer. In the test, contact angle, weight loss, surface resistivity and relative dielectric constant are measured. As the results of the above measurements, the epoxy resin has increased to 150$^{\circ}C$ in the contact angle and surface resistivity but at the above 150$^{\circ}C$ the values have decreased. The relative dielectric constants have increased in the thermal treated samples with the degradation temperature. Consequently, the insulation properties of the epoxy resin which is used in cast resin transformer have increased by the 150$^{\circ}C$ but decreased in the above 150$^{\circ}C$.

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