• 제목/요약/키워드: Water temperature stress

검색결과 643건 처리시간 0.032초

콘크리트 단열온도 상승 예측에 관한 연구 (Estimation of Adiabatic Temperature Rise of Concrete)

  • 방기성;정원섭;송영철;조철희
    • 한국콘크리트학회:학술대회논문집
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    • 한국콘크리트학회 1998년도 가을 학술발표대회 논문집(III)
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    • pp.934-939
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    • 1998
  • This study discusses the results of adiabatic temperature rise tests which were performed considering various parameters, such as cement type, water-cement ratio, unit cement weigh, admixtures and placing temperature, which influence the temperature rise(K) and reaction velocity ($\alpha$). Theadiabatic temperature rise models obtained from this study are similar to those of Japan Concrete Institute. The models to calculate temperature rise and reaction velocity could be used the analysis f concrete thermal stress.

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저변형률시험법에 의한 섬유강화 복합재료의 응력부식균열에 관한 연구 (A Study on Stress Corrosion Cracking of Fiber Reinforced Composite by Slow Strain Rate Test)

  • 임재규;최태수
    • 대한기계학회논문집A
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    • 제20권11호
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    • pp.3433-3440
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    • 1996
  • This paper was investigation of the stres corrosion cracking(SCC) mechanism and the properties of corrosion fracture surface of glass fiber reinforced plastics(GFRP) produced by hand lay up(HLU) method in synthetic sea water. Test material is GFRP, that was used vinylester type epoxy acrylate resin and an unsaturated polyester as the matrix and the chopped strand mat(CSM) type E-glss fiber as the reinforcement. The slow strain rate test(SSRT) was performed on dry, wet and saturated wet specimens in sea water. Here the pH concentration of synthetic sea water was 8.2 and the strain rate is 1 x $10^{-6}$($sec^{-1}$) and test temperature ranges varied from $-60^{\circ}C$ to $80^{\circ}C$. It could be confirmed the fact that wet specimens tested at a particular test temperature ranges were appeared the eviences of SCC such as con-planar, mirror and hackle zone. Moreover, SCC of GFRP in sea water was characterised by falt fracture surfaces with only small amounts of fiber pull-out, in partial.

넙치, Paralichthys olivaceus의 수온 자극 스트레스에 대한 사료첨가제 투여 효과 (The effects of supplementary diets on the water temperture stress in olive flounder, Paralichthys olivaceus)

  • 권문경;박상언;방종득;조병열;이상민;박수일
    • 한국어병학회지
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    • 제16권3호
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    • pp.183-191
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    • 2003
  • 본 연구는 넙치의 수온 스트레스에 대한 사료첨가제(미역 5%, 미역 10%, 어보산 0.5%, 고추냉이 잎 2%, 고추냉이 줄기 2%)의 영향을 혈액학적, 면역학적 측면과 Edwardsiella tarda를 사용하여 질병에 대한 저항성으로서 평가하였다. 혈장의 글루코즈와 콜티졸 농도는 1차 수온 변동 후 대조구에 비하여 미역 5%와 고추냉이잎 2% 첨가구에서 유의적으로 낮게 나타났다(P<0.05). 1차 수온 변동 후 혈장 라이소자임 활성과 E. tarda의 공격 시험 후 생존율은 미역 5% 첨가구에서 대조구에 비하여 유의적으로 높게 나타났다(P<0.05). 본 실험 결과 미역 5% 첨가 사료 투여는 넙치의 스트레스 상태에서 질병 감염에 대한 저항성을 높일 수 있을 것으로 사료된다.

온도변화에 따른 건조 스트레스 환경에서 고추 세균점무늬병 발생 영향 (Evaluation of Bacterial Spot Disease of Capsicum annuum L. in Drought Stress Environment by High Temperature)

  • 장종옥;김병혁;이중복;좌재호;고상욱
    • 식물병연구
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    • 제25권2호
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    • pp.62-70
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    • 2019
  • The global warming by increased $CO_2$ will effect of plant pathogenic microorganisms and resistance of host plants, and it is expected to affect host-pathogen interactions. This study used Capsicum annuum L. and Xanthomonas euvesicatoria, a pathogenic bacteria of pepper, to investigate interactions between hosts and pathogens in a complex environment with increasedcultivation temperature and drought stress. As a result, the bacterial spot disease of C. annuum L. caused by X. euvesicatoria was $35^{\circ}C$ higher than $25^{\circ}C$. In addition, the effect on water potential on bacterial spot disease was much greater water potential -150 kPa than -30 kPa. The disease progress and severity higher than water potential -30 kPa. This result will useful for understanding interaction with red pepper and X. euvesicatoria under the complex environment with increased cultivation temperature and in water potential -150 kPa drought stress in the future.

콘크리트 중력댐 하류면의 균열거동에 미치는 동절기 대기온도의 영향 (An Effect of Wintertime Air Temperature on Crack Behavior at Downstream Face of the Concrete Gravity Dam)

  • 장희석;김종수;심점식
    • 한국콘크리트학회:학술대회논문집
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    • 한국콘크리트학회 2000년도 가을 학술발표회 논문집(II)
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    • pp.1313-1318
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    • 2000
  • Crack behaviors at the downstream face of the concrete gravity dam were studied considering influence of the wintertime air temperature. It is assumed that inside area of 15m away from the dam surface in which temperature is presumed to be $15^{\circ}C$ is not affected from the annual air temperature variation. Water temperature at the upstream face and air temperature at the other faces were considered as outer boundary conditions to get temperature distribution inside of the dam using ADINA-T. These temperature distributions were transferred to FRANC2D to obtain equivalent stress intensity factors and crack propagation paths. Results obtained from changing initial crack locations and direction, air temperatures, and water levels were discussed. And crack behaviors at the upstream face were studied partly.

Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Water Reactors

  • Yonezawa, Toshio
    • Corrosion Science and Technology
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    • 제7권2호
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    • pp.77-84
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    • 2008
  • Based upon the good compatibility to neutron irradiation and high temperature water environment, austenitic stainless steels are widely used for core internal structural materials of light water reactors. But, recently, intergranular cracking was detected in the stainless steels for the core applications in some commercial PWR plants. Authors studied on the root cause of the intergranular cracking and developed the countermeasure including the alternative materials for these core applications. The intergranular cracking in these core applications are defined as an irradiation assisted mechanical cracking and irradiation assisted stress corrosion cracking. In this paper, the root cause of the intergranular cracking and its countermeasure are summarized and discussed.

LPG 액정분사 방식의 대형 엔진용 피스톤의 온도분포와 열응력 해석 (Temperature Distribution and Thermal Stress Analyses of a Large LPLi Engine Piston)

  • 임문혁;손재율;이부윤
    • Journal of Advanced Marine Engineering and Technology
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    • 제28권3호
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    • pp.538-550
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    • 2004
  • The convection heat transfer coefficients on the top surface of a large liquid petroleum liquid injection(LPLi) engine piston with the oil gallery are analyzed by solving an inverse thermal conduction problem. The heat transfer coefficients are numerically found so that the difference between analyzed temperatures from the finite element method and measured temperatures is minimized. Using the resulting heat transfer coefficients as the boundary condition, temperature of a large LPLi engine piston is analyzed. With varying cooling water temperature, temperature, stress, and thermal expansion of the piston are analyzed and evaluated.

Investigation on effect of neutron irradiation on welding residual stresses in core shroud of pressurized water reactor

  • Jong-Sung Kim;Young-Chan Kim;Wan Yoo
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.80-99
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    • 2023
  • This paper presents the results of investigating the change in welding residual stresses of the core shroud, which is one of subcomponents in reactor vessel internals, performing finite element analysis. First, the welding residual stresses of the core shroud were calculated by applying the heat conduction based lumped pass technique and finite element elastic-plastic stress analysis. Second, the temperature distribution of the core shroud during the normal operation was calculated by performing finite element temperature analysis considering gamma heating. Third, through the finite element viscoelastic-plastic stress analysis using the calculated temperature distribution and setting the calculated residual stresses as the initial stress state, the variation of the welding residual stresses was derived according to repeating the normal operation. In the viscoelastic-plastic stress analysis, the effects of neutron irradiation on mechanical properties during the cyclic normal operations were considered by using the previously developed user subroutines for the irradiation agings such as irradiation hardening/embrittlement, irradiation-induced creep, and void swelling. Finally, the effect of neutron irradiation on the welding residual stresses was analysed for each irradiation aging. As a result, it is found that as the normal operation is repeated, the welding residual stresses decrease and show insignificant magnitudes after the 10th refueling cycle. In addition, the irradiation-induced creep/void swelling has significant mitigation effect on the residual stresses whereas the irradiation hardening/embrittlement has no effect on those.

인코벨 690 증기발생기 세관의 고온 마모 거동 (High Temperature Wear Behavior of Inconel 690 Steam Generator tube)

  • 홍진기;김인섭;김형남;장기상
    • 한국윤활학회:학술대회논문집
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    • 한국윤활학회 2001년도 제34회 추계학술대회 개최
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    • pp.59-62
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    • 2001
  • Flow induced vibration in steam generators has caused dynamic interactions between tubes and contacting materials resulting in fretting wear . Series of experiments have been performed to examine the wear properties of Inconel 690 steam generator tubes in various environmental conditions. For the present study, the test rig was designed to examine the fretting wear and rolling wear properties in high temperature(room temperature - 290。C) water. The test was performed at constant applied load and sliding distance to investigate the effect of test temperature on wear properties of the steam generator tube materials. To investigate the wear mechanism of material, the worn was observed using scanning electron microscopy. The weight loss increase at higher test temperature was caused by the decrease of water viscosity and the mechanical property change of tube material. The mechanical property changes of steam generator tube material, such as decrease of hardness or yield stress in the high temperature tests. From the SEM observation of worn surfaces, the severe wear scars were observed in specimens tested at the higher temperature.

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누설 및 파열실험용 SCC 결함 전열관 제작 및 누설거동 평가 (Production of SCC Flaws and Evaluation Leak Behavior of Steam Generator Tubes)

  • 황성식;정만교;박장열;김홍표
    • Corrosion Science and Technology
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    • 제8권5호
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    • pp.188-192
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    • 2009
  • A forced outage due to a steam generator tube leak in a Korean nuclear power plant was reported.1) Primary water stress corrosion cracking has occurred in many tubes in the plant, and they were repaired using sleeves or plugs. In order to develop proper repair criteria, it is necessary to understand the leak behavior of the tubes containing stress corrosion cracks. Stress corrosion cracks were developed in 0.1 M sodium tetrathionate solution at room temperature. Steam generator(SG) tubes with short cracks were successfully fabricated with a restricted solution contact method. The leak rates of the degraded tubes were measured at room temperature. Some tubes with 100 % through wall cracks showed an increase of leak rate with time at a constant pressure.