• Title/Summary/Keyword: thermal shock

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Fracture Behavior and Mechanical properties of WC-Co Subjected to Thermal Shock (WC-Co의 열충격 후 파괴 현상과 기계적 성질)

  • ;Joh
    • Journal of the Korean Ceramic Society
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    • v.27 no.1
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    • pp.102-108
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    • 1990
  • WC-Co composites are widely used as cutting or drilling tools because of their high hardness, strength, and fracture toughness. The working temperature is, however, generally in the range of 300-$700^{\circ}C$ so thermal shock fracture of WC-Co can occur. In this study, the strength, fracture toughness and fracture surface of 16wt% Co bonded tungsten carbide composites before and after thermal shock were observed.

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Determination of Thermal Shock Stress Intensity Factor for Elliptical Crack by Modified Vainshtok Weight Function Method (수정 Vainshtok 가중함수법에 의한 타원균열의 열충격 응력세기계수의 결정)

  • 이강용;김종성
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.19 no.2
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    • pp.463-474
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    • 1995
  • Modified Vainshtok weight function method is developed. The thermal shock stress intensity factors for elliptical surface cracks existed in the thin and thick walled cylinders are determined. The present results are compared with previous solutions and shown to be good agreement with them.

LOW CYCLE THERMAL FATIGUE OF THE ENGINE EXHAUST MANIFOLD

  • Choi, B.L.;Chang, H.;Park, K.H.
    • International Journal of Automotive Technology
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    • v.5 no.4
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    • pp.297-302
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    • 2004
  • This paper presents the low cycle thermal fatigue of the engine exhaust manifold subject to thermo-mechanical cyclic loading. As a failure of the exhaust manifold is mainly caused by geometric constraints of the less expanded inlet flange and cylinder head, the analysis is based on the exhaust system model with three-dimensional temperature distribution and temperature dependent material properties. The result show that large compressive plastic deformations are generated at an elevated temperature of the exhaust manifold and tensile stresses are remained in several critical zones at a cold condition. From the repetition of these thermal shock cycles, maximum plastic strain range (0.454%) could be estimated by the stabilized stress-strain hysteresis loops. It is used to predict the low cycle thermal fatigue life of the exhaust manifold for the thermal shock test.

Thermal Characteristic Evaluation of Functionally Graded Composites for PSZ/Metal

  • Lim, Jae-Kyoo;Song, Jun-Hee
    • Journal of Mechanical Science and Technology
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    • v.14 no.3
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    • pp.298-305
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    • 2000
  • The functionally graded material (FGM) is the new concept for a heat resisting material. FGM consists of ceramics on one side and metal on the other. A composition and microstructure of an intermediate layer change continuously from ceramics to metal at the micron level. This study is carried out to analyze the thermal shock characteristics of functionally graded PSZ/ metal composites. Heat-resistant property was evaluated by gas burner heating test using $C_2H_2/O_2$ combustion flame. The ceramic surface was heated with burner flame and the bottom surface cooled with water flow. Also, the composition profile and the thickness of the graded layer were varied to study the thermo mechanical response. Furthermore, this study carried out the thermal stress analysis to investigate the thermal characteristics by the finite element method. Acoustic emission (AE) monitoring was performed to detect the microfracture process in a thermal shock test.

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Probabilistic Fracture Mechanics Analysis of Reactor Vessel for Pressurized Thermal Shock - The Effect of Residual Stress and Fracture Toughness - (가압열충격에 대한 원자로 용기의 확률론적 파괴역학해석 - 잔류응력 및 파괴인성곡선의 영향 -)

  • Jung, Sung-Gyu;Jin, Tae-Eun;Jhung, Myung-Jo;Choi, Young-Hwan
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.27 no.6
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    • pp.987-996
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    • 2003
  • The structural integrity of the reactor vessel with the approaching end of life must be assured for pressurized thermal shock. The regulation specifies the screening criteria for this and requires that specific analysis be performed for the reactor vessel which is anticipated to exceed the screening criteria at the end of plant life. In case the screening criteria is exceeded by the deterministic analysis, probabilistic analysis must be performed to show that failure probability Is within the limit. In this study, probabilistic fracture mechanics analysis of the reactor vessel for pressurized thermal shock is performed and the effects of residual stress and master curve on the failure probability are investigated.

Thermal Shock Behavior of Barium Titanate Ceramics

  • Jae Yeon Kim;Young Wook Kim;Kyeong Sik Cho;June Gunn Lee
    • The Korean Journal of Ceramics
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    • v.3 no.3
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    • pp.195-198
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    • 1997
  • Post-firing process of electronic ceramic, such as electroding and encapsultion with resin, often causes damage by thermal shock. The thermal shock behavior of $BaTiO_3$ ceramics was investigated by the down-quench test, where the relative strength retained is determined after the sample is quenched from an elevated temperature into a fixed temperature bath. The critical temperature drop, $\DeltaTc$, was evaluated for three kinds of sintered $BaTiO_3$ ceramics, which were formed by extrustioin, uniaxial pressing using granules, and uniaxial pressing using powders. A drastic loss in strength caused by microcracking was observed for the specimens quenched with $\DeltaT\geq150^{\circ}C$. This concentp can be adopted as a method of the quality control by monitoring the sudden drop of the strength of capacitor products after each exposure to heat.

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Probabilistic Structural Integrity Assessment of a Reactor Vessel Under Pressurized Thermal Shock

  • Kim, Ji-Ho;Kim, Yong-Wan;Kim, Tae-Wan;Hyung-Huh;Kim, Jong-In
    • Nuclear Engineering and Technology
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    • v.32 no.2
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    • pp.99-107
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    • 2000
  • A probabilistic integrity analysis method is presented for a reactor vessel under pressurized thermal shock(PTS) based on Monte Carlo simulation. This method can be applied to the structural integrity assessment of a reactor vessel subjected to pressurized thermal shock where the coolant temperature transient cannot be expressed explicitly as a time function. An axially or circumferentially oriented infinite length surface crack is assumed to be in the beltline weld region of the rector vessel's inside surface. The random variables are the initial crack depth, neutron fluence on the vessel's inside surface, the copper and nickel content of the vessel materials, R $T_{NDT}$ , $K_{IC}$ , and K/aub la/. The reliability of a sample reactor vessel under PTS is assessed quantitatively and the influence of the amount of neutron fluence is also examined by applying the present method.sent method.

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Morphological Observation on Tribological Characteristic of Thermal Spray Coated Steel-Bar (용사 코팅된 스틸바의 트라이볼로지적 특성의 형상학적 관찰)

  • Lee, Duk Gyu;Cho, Hee Keun
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.38 no.5
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    • pp.559-566
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    • 2014
  • Plasma coatings have been conducted to improve the mechanical properties of thermal resistance, wear resistance, corrosion resistance and thermal shock with respect to Great-Bar which is used as a carrier device for ironstone sintering under $700^{\circ}C$. The surface coatings on the upper side of the Great-Bar exposed on extreme environments of high temperature, severe wear, corrosion and thermal shock extended the life time due to the barrier coating layer. $Al_2O_3$, $Cr_2O_3$, WC coatings were applied to Great-Bar and their mechanical and chemical properties are analyzed by several experimental tests such as thermal resistance, wear resistance, corrosion resistance and thermal shock resistance. It shows excellent advantages with respect to wear, thermal shock and corrosion.

Treatment of Stainless Steel Cladding in Pressurized Thermal Shock Evaluation: Deterministic Analyses

  • Changheui Jang;Jeong, lll-Seok;Hong, Sung-Yull
    • Nuclear Engineering and Technology
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    • v.33 no.2
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    • pp.132-144
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    • 2001
  • Fracture mechanics is one of the major areas of the pressurized thermal shock (PTS) evaluation. To evaluate the reactor pressure vessel integrity associated with PTS, PFM methodology demands precise calculation of temperature, stress, and stress intensity factor for the variety of PTS transients. However, the existence of stainless steel cladding, with different thermal, physical, and mechanical property, at the inner surface of reactor pressure vessel complicates the fracture mechanics analysis. In this paper, treatment schemes to evaluate stress and resulting stress intensity factor for RPV with stainless steel clad are introduced. For a reference transient, the effects of clad thermal conductivity and thermal expansion coefficients on deterministic fracture mechanics analysis are examined.

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Fracture Behavior of Ceramic Coatings Subjected to Thermal Shock (열충격에 의한 세라믹코팅재의 파괴거동)

  • Han, Ji-Won
    • Journal of the Korean Society of Safety
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    • v.18 no.4
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    • pp.39-43
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    • 2003
  • An experimental study was conducted to develop and understanding of fracture behavior of ceramic thermal barrier coating when subjected to a thermal shock loading. The thermal loading was applied using a 1.5kW $CO_2$ laser. In the experiments, beam-shaped specimens were subjected to a high heat flux for 4sec and cooling of 7sec in air. The interface crack length was increased as the crack density, the surface pre-crack legth and the coating thickness were increased. The center surface crack length was increased as the maximum surface temperature got higher and the surface pre-crack length for shorter.