• Title/Summary/Keyword: thermal shock

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A Study on the strengthening of titania ceramic coating layer on the steel substrate (티타니아 세라믹 熔射皮膜의 强度向上에 관한 硏究)

  • 김영식
    • Journal of Welding and Joining
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    • v.10 no.4
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    • pp.181-189
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    • 1992
  • The purpose of this investigation is to examine the effects of the strengthening treatments on the mechanical properties of the flame-sprayed titania ceramic coating layer. The strengthening treatments for flame sprayed specimens were carried out in 12 different conditions in vaccum furance. The mechanical properties such as microhardness, thermal shock resistance, adhesive strength and erosion resistance were tested for the sprayed specimens after strengthening treatments. And it was clear that the mechanical properties of coating layer were much improved by the strengthening treatments. The results obtained are summarized as follows; 1. It was shown that the metallurgical bond was formed between substrate and coating layer by the strengthening treatments and that thermal shock resistance and adhesive strength were remarkably raised. 2. Microhardness of coating lay was considerably increased by the strengthening treatments. 3. Erosion resistance and porosity of coating layer were slightly improved by the strengthening treatments.

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Reliability of Insert Mounted Components under Thermal Shock (열충격하에서의 삽입실장 부품의 신뢰성에 관한 연구)

  • Lee, Jong-Beom;No, Bo-In;Jeong, Seung-Bu
    • Proceedings of the KWS Conference
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    • 2006.10a
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    • pp.202-204
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    • 2006
  • The reliability of insert mounted components has been considered as their life time was getting increased. The spread of crack and the growth of IMC(intermetallic compound) were observed by SEM(scanning electron microscope) and EDS(energy dispersive spectroscope). The cracks in Sn-37wt%Pb under thermal shock test were found earlier than other solders(Sn-3.0wt%Ag-0.5wt%Cu and Sn-0.7wt%Cu-0.01wt%P). The IMC thickness was increased with increasing number of thermal shock cycles in the following order : Sn-0.7Cu-0.01P; Sn-3.0Ag-0.5Cu; Sn-37Pb

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A Study on Thermosonic Bonding Process and Its Reliability Evaluation of Joints (열초음파 접합 공정과 접합부의 신뢰성 평가에 관한 연구)

  • Shin, Young-Eui;Pak, Jin-Suk;Son, Sun-Eik
    • Journal of the Korean Institute of Electrical and Electronic Material Engineers
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    • v.22 no.8
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    • pp.625-631
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    • 2009
  • In this thesis, lateral thermosonic bonding with ACFs was investigated as a process to make high reliability joints for FPD fabrication. Conditions for thermosonic and thermocompression bonding with ACFs were determined and used to make specimens in a driving test jig for testing of bond reliability by thermal shock. The results showed that thermosonic bonding temperature of $199\;^{\circ}C$ and bonding time of 1s produced bonds with good reliability. Additionally, thermosonic bonding temperature and time were reduced and thermal shock test results compared to this proposed curing condition. It is concluded that theromosonic bonding with ACFs can be effectively applied to reduce bonding temperature and time compared with that of thermocompression bonding.

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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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.

Structural Integrity Evaluation of the Integral Reactor SMART under Pressurized Thermal Shock (가압열충격에 대한 일체형원자로 SMART의 구조건전성 평가)

  • Kim, Jong-Wook;Lee, Gyu-Mahn;Choi, Suhn;Park, Keun-Bae
    • Proceedings of the KSME Conference
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    • 2001.06a
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    • pp.441-446
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    • 2001
  • In the integral type reactor, SMART, all the major components such as steam generators, pressurizer and pumps are located inside the single reactor pressure vessel. The objective of this study is to evaluate the structural integrity for RPV of SMART under the postulated pressurized thermal shock by applying the finite element analysis. Input data for the finite element analysis were generated using the commercial code I-DEAS, and the fracture mechanics analysis was performed using the ABAQUS. The crack configurations, the crack aspect ratio and the clad thickness were considered in the parametric study. The effects of these parameters on the reference nil-ductility transition temperature were also investigated.

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Boron Nitride Dispersed Nanocomposites with High Thermal Shock Resistance

  • Kusunose, T.;Sekino, T.;Choa, Y.H.;Nakayama, T.;Niihara, K.
    • Journal of Powder Materials
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    • v.8 no.3
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    • pp.174-178
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    • 2001
  • The microstructure and mechanical properties of $Si_3N_4/BN $nanocomposites synthesized by chemical processing were investigated. The nanocomposites containing 15 vol% hexagonal BN (h-BN) were fabricated by hot-pressing $\alpha-Si_3N_4$powders covered with turbostratic BN (t-BN). The t-BN coating on $\alpha-Si_3N_4$particles was prepared by heating $\alpha-Si_3N_4$ particles covered with a mixture of boric acid and urea in hydrogen gas. TEM observations of this nanocomposite revealed that nano-sized h-BN particles were homogeneously dispersed within $Si_3N_4$grains as well as at grain boundaries. The strength and thermal shock resistance were significantly improved in comparison with the $Si_3N_4/BN$ microcomposites.

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Sensitivity Analyses for Failure Probabilities of the OPR1000 Reactor Vessel Under Pressurized Thermal Shock (가압열충격에 의한 OPR1000 원자로용기의 파손확률 민감도 해석)

  • Oh, Changsik;Jhung, Myung Jo;Choi, Youngin
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.15 no.2
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    • pp.40-49
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    • 2019
  • In this paper, failure probabilities of the OPR1000 reactor vessel under pressurized thermal shock (PTS) were estimated using the probabilistic fracture mechanics code, R-PIE. Input variables of initial crack distribution, crack size, copper contents, and upper shelf toughness were selected for the sensitivity analyses. A wide range of the input data were considered. Through-wall cracking frequencies determined by the product of the vessel failure probability and the corresponding occurrence frequency of the transient were also compared to the acceptance criterion. The results showed that transient history had the most significant impact on the vessel failure probability. Moreover, conservative assumptions resulted in extremely high through-wall cracking frequencies.

Comparison of vessel failure probabilities during PTS for Korean nuclear power plants

  • Jhung, M.J.;Choi, Y.H.;Chang, Y.S.
    • Structural Engineering and Mechanics
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    • v.37 no.3
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    • pp.257-265
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    • 2011
  • Plant-specific analyses of 5 types of domestic reactors in Korea are performed to assure the structural integrity of the reactor pressure vessel (RPV) during transients which are expected to initiate pressurized thermal shock (PTS) events. The failure probability of the RPV due to PTS is obtained by performing probabilistic fracture mechanics analysis. The through-wall cracking frequency is calculated and compared to the acceptance criterion. Considering the fluence at the end of life expected by surveillance test, the sufficient safety margin is expected for the structural integrity of all reactor pressure vessels except for the oldest one during the pressurized thermal shock events. If the flaw with aspect ratio of 1/12 is considered to eliminate the conservatism, the acceptance criteria is not exceeded for all plants until the fluence level of $8{\times}10^{19}\;n/cm^2$, generating sufficient margin beyond the design life.