• 제목/요약/키워드: Thermal cycles

검색결과 494건 처리시간 0.027초

LPG 액정분사식 대형 버스용 엔진 피스톤의 피로수명 해석과 냉각조건 평가 (Fatigue Life Analysis and Cooling Conditions Evaluation of a Piston for Large LPLi Bus Engines)

  • 최경호;이부윤
    • Journal of Advanced Marine Engineering and Technology
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    • 제28권5호
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    • pp.762-772
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    • 2004
  • Fatigue life of a Piston for large liquid Petroleum liquid injection(LPLi) bus engines is analyzed considering effects of cooling condition parameters : temperature of cooling water, and heat transfer coefficients at oil gallery and bottom surface of piston head. Temperature of the piston is analyzed with varying cooling conditions Stresses of the piston from two load cases of pressure loading. and pressure and thermal loading are analyzed Fatigue life under repeated peak pressure and thermal cycle is analyzed by the strain-life theory. For the two load cases, required loading cycles for engine life are defined, and loading cycles to failure and partial damages are calculated. Based on the resulting accumulated fatigue usage factors, endurance of the piston is evaluated and effects of varying cooling condition Parameters are discussed.

Energy optimization of a Sulfur-Iodine thermochemical nuclear hydrogen production cycle

  • Juarez-Martinez, L.C.;Espinosa-Paredes, G.;Vazquez-Rodriguez, A.;Romero-Paredes, H.
    • Nuclear Engineering and Technology
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    • 제53권6호
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    • pp.2066-2073
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    • 2021
  • The use of nuclear reactors is a large studied possible solution for thermochemical water splitting cycles. Nevertheless, there are several problems that have to be solved. One of them is to increase the efficiency of the cycles. Hence, in this paper, a thermal energy optimization of a Sulfur-Iodine nuclear hydrogen production cycle was performed by means a heuristic method with the aim of minimizing the energy targets of the heat exchanger network at different minimum temperature differences. With this method, four different heat exchanger networks are proposed. A reduction of the energy requirements for cooling ranges between 58.9-59.8% and 52.6-53.3% heating, compared to the reference design with no heat exchanger network. With this reduction, the thermal efficiency of the cycle increased in about 10% in average compared to the reference efficiency. This improves the use of thermal energy of the cycle.

Low Ag 조성의 Sn-0.3Ag-0.7Cu 및 Sn-3.0Ag-0.5Cu 무연솔더 접합부의 열충격 신뢰성 (Thermal Shock Reliability of Low Ag Composition Sn-0.3Ag-0.7Cu and Near Eutectic Sn-3.0Ag-0.5Cu Pb-free Solder Joints)

  • 홍원식;오철민
    • 대한금속재료학회지
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    • 제47권12호
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    • pp.842-851
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    • 2009
  • The long-term reliability of Sn-0.3wt%Ag-0.7wt%Cu solder joints was evaluated and compared with Sn-3.0wt%Ag-0.5wt%Cu under thermal shock conditions. Test vehicles were prepared to use Sn-0.3Ag-0.7Cu and Sn-3.0Ag-0.5Cu solder alloys. To compare the shear strength of the solder joints, 0603, 1005, 1608, 2012, 3216 and 4232 multi-layer ceramic chip capacitors were used. A reflow soldering process was utilized in the preparation of the test vehicles involving a FR-4 material-based printed circuit board (PCB). To compare the shear strength degradation following the thermal shock cycles, a thermal shock test was conducted up to 2,000 cycles at temperatures ranging from $-40^{\circ}C$ to $85^{\circ}C$, with a dwell time of 30 min at each temperature. The shear strength of the solder joints of the chip capacitors was measured at every 500 cycles in each case. The intermetallic compounds (IMCs) of the solder joint interfaces werealso analyzed by scanning electron microscopy (SEM) and energy dispersive X-ray spectroscopy (EDS). The results showed that the reliability of Sn-0.3Ag-0.7Cu solder joints was very close to that of Sn-3.0Ag-0.5Cu. Consequently, it was confirmed that Sn-0.3Ag-0.7Cu solder alloy with a low silver content can be replaced with Sn-3.0Ag-0.5Cu.

열피로에 의한 세라믹 코팅재의 파손 (Failure of Ceramic Coatings Subjected to Thermal Cyclings)

  • 한지원
    • 한국안전학회지
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    • 제20권2호
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    • pp.1-5
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    • 2005
  • An experimental study was conducted to develop an understanding of failure of ceramic coating when subjected to a thermal cycling. Number of cycles to failure were decreased as the coating thickness and the oxide of bond coat were increased. Using the finite element method, an analysis of stress distribution in ceramic coatings was performed. Radial compressive stress was increased in the top/bond coat interface with increasing coating thickness and oxide of bond coat.

복합재료의 열-음향방출거동에 있어서의 카이저 효과 (Kaiser Effects in Thermo-Acoustic Emission Behavior of Composites)

  • 김영복;최낙삼
    • Composites Research
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    • 제14권5호
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    • pp.38-45
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    • 2001
  • 복합적층판에 반복 열부하사이클을 부여하여 열-음향방출(thermo-AE)신호의 카이저효과Kaiser effects)를 정량적으로 분석하고 이 거동을 음향방출의 발생원인과 관련시켜 해명하였다. 열부하사이클을 반복함에 따라 음향 방출의 총 링다운 카운트수 및 진폭이 급격히 감소하는 카이저 효과를 나타냈다. 이 카이저 효과는 총 링다운 카운트 수의 지수함수로 표현되었다. 열부하 사이클 시에 발생하는 AE는 균열진전에 의만 것이 아니라, 굴곡진 균열면간의 접촉에 의만 마모 및 2차적 미세손상의 발생과 관련되며, 2차 이후의 열부하 사이클 시에는 균열면간의 마찰적 미끄러짐으로 보다 약한 AE가 적은 사상수로 발생했던 것으로 추정되었다 이러한 열-음향방출 거동은 시험편의 종류 및 열부하 시의 최고온도에 따라 다른 특성을 보였다

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320×240 적외선 검출기를 이용한 열상센서의 설계 (Thermal imaging sensor design using 320×240 IRFPA)

  • 홍석민;송인섭;김창우;유위경;김현숙
    • 한국광학회지
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    • 제15권5호
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    • pp.423-428
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    • 2004
  • 320${\times}$240 배열의 중적외선 대역(3.7 $\mu\textrm{m}$∼4.8 $\mu\textrm{m}$) MCT(HgCdTe) 검출기를 이용하여 분해능과 신뢰도가 대폭 향상된 소형$.$고성능의 적외선 열상센서를 설계, 제작하였다. 개발된 열상센서는 1∼20배의 고배율 줌 광학계로 설계하고 미세주사 기법을 적용하여 640${\times}$480의 화소를 재현하여 항공기의 항법 보조로부터 표적획득에 이르기까지 다양한 활용이 가능하다. 적용된 적외선 줌 광학계는 릴레이 형태의 재결상계로 설계되었으며 미세주사 장치의 개발로 7.6 cycles/mrad 까지 분해가 가능하며 최저배율에서 40$^{\circ}$${\times}$30$^{\circ}$의 초광각(super wide field of view)의 시계를 갖는다. 또한 불균일 보정기법과 히스토그램 가변방식의 결합을 통한 첨단 열 영상처리 기법을 제안하여 열상센서에 적용함으로써 고성능의 실시간 디지털 영상처리를 가능케 하였다. 본 신호처리기의 개발을 통해 획득된 열영상의 최소분해가능 온도차는 고배율에서 0.05K(@1cycles/mrad) 이하의 우수한 결과를 보였다.

복합재료의 열-음향방출거동 (Thermo-Acoustic Emission Behavior of Composites)

  • 김영복;우성충;최낙삼
    • 한국복합재료학회:학술대회논문집
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    • 한국복합재료학회 2001년도 추계학술발표대회 논문집
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    • pp.111-115
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    • 2001
  • Thermo-acoustic emission (AE) from composite laminates under the repetitive thermal cyclic loads have been quantitatively analyzed in consideration of AE source mechanisms. The repetitive thermal load brought about a large reduction, i.e. an exponential decrease in AE total ringdown counts and AE amplitudes. It was thought that generation of thermo-AE during the first thermal cycle was not caused by crack propagation but by secondary microfracturing due to abrasive contact between crack surfaces.

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W 섬유강화(纖維强化) Al 합금기지(合金基地) 복합재(複合材)의 열(熱)cycle에 따른 계면거동(界面擧動)에 관(關)한 연구(硏究) (A Study on Interfacial Phenomena of Tungsten Fiber Reinforced Aluminium Matrix Composite under Thermal Cycles)

  • 허재근;김정태;현창용;김용석;김석윤
    • 열처리공학회지
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    • 제7권3호
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    • pp.169-174
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    • 1994
  • The reaction layer formed at interface between matrix and fiber has significant effects on the mechanical properties and behaviors of deformation m FRM. In this study, the mechanical properties and interfacial behaviors according to surface finishing on the fibers and according to heat treatment in FRM were investigated. FRM was fibricated by diffusion bonding method. In W/Al alloy composite and W/Al composite, W of which was coated with $WO_3$, the heat treatment was carried out thermal cycling method from 373K to 673K. In W/Al composite, W of which was coated with $WO_3$, growth of interface layer was hardly occured in spite of the increasing various thermal cycles. It was exhibited that oxidized W/Al composite were higher strength than non-oxidezed W/Al composite with the increasing thermal cycles. The compounds of fiber/matrix interface were analyzed into $WAl_{12}$, $WAl_7$, and $AlWO_3$, respectivly. Therefore the interfacial compounds of fiber/matrix seriously affected the mechanical properties and behaviors of deformation in FRM.

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A Comparative Study on the Proliferation Resistance of Nuclear Fuel Cycles

  • Chang, H.L.;Ko, W.I.;Lee, Y.D.;Lee, K.S.;Kim, H.D.
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2009년도 학술논문요약집
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    • pp.53-54
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    • 2009
  • The preliminary quantitative analysis of proliferation resistance for the five nuclear fuel cycles demonstrated that the thermal MOX fuel cycle is most vulnerable to proliferation due to the presence of pure $PuO_2$ in the fuel cycle, while the once-through fuel cycle has the highest proliferation resistance. The innovative next generation fuel cycles such as Pyro-SFR and Wet-SFR were found to have similar levels of proliferation resistance to that of the DUPIC fuel cycle which is believed to have proliferation resistance strong enough for commercial deployment. The sensitivity analysis also demonstrated the effectiveness of the proposed methodology in applying to existing and/or newly developing nuclear fuel cycles so as to improve the proliferation resistance characteristic of the fuel cycle systems.

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원자력 구조재 신뢰성 향상을 위한 열피로 균열 시험편 제작 기법 개발 (Development the Technique for Fabrication of the Thermal Fatigue Crack to Enhance the Reliability of Structural Component in NPPs)

  • 김용;김재성;이보영
    • Journal of Welding and Joining
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    • 제26권2호
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    • pp.43-49
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    • 2008
  • Fatigue cracks due to thermal stratification or corrosion in pipelines of nuclear power plants can cause serious problems on reactor cooling system. Therefore, the development of an integrated technology including fabrication of standard specimens and their practical usage is needed to enhance the reliability of nondestructive testing. The test material was austenitic STS 304, which is used as pipelines in the Reactor Coolant System of a nuclear power plants. The best condition for fabrication of thermal fatigue cracks at the notch plate was selected using the thermal stress analysis of ANSYS. The specimen was installed from the tensile tester and underwent continuos tension loads of 51,000N. Then, after the specimen was heated to $450^{\circ}C$ for 1 minute using HF induction heater, it was cooled to $20^{\circ}C$ in 1 minute using a mixture of dry ice and water. The initial crack was generated at 17,000 cycles, 560 hours later (1cycle/2min.) and the depth of the thermal fatigue crack reached about 40% of the thickness of the specimen at 22,000 cycles. As a results of optical microscope and SEM analysis, it is confirmed that fabricated thermal fatigue cracks have the same characteristics as real fatigue cracks in nuclear power plants. The crack shape and size were identified.