• 제목/요약/키워드: Simulated Tubes

검색결과 70건 처리시간 0.029초

마찰 계수와 점성 계수 모델이 단열 모세관 유동에 미치는 영향 평가 (An Assessment of Friction Factor and Viscosity Models for Predicting the Refrigerant Characteristics in Adiabatic Capillary Tubes)

  • 손기동;박상구;정지환;이승홍;김윤수
    • 설비공학논문집
    • /
    • 제21권3호
    • /
    • pp.140-148
    • /
    • 2009
  • Capillary tubes are widely used as expansion device in small refrigeration systems. The refrigerant flowing in the capillary tube experiences frictional and accelerational head losses and flashing simultaneously. In this paper flow characteristics of adiabatic capillary tubes were simulated with various friction factor models, two-phase viscosity models, and two-phase frictional multiplier models. The predicted pressure distribution and mass flow rate are compared with experimental data reported in literature. It is confirmed that the predicting accuracy with homogeneous model can be improved by employing suitable correlations of friction factor, two-phase viscosity and two-phase frictional multiplier.

마찰 계수와 점성 계수 모델이 단열 모세관 유동에 미치는 영향 평가 (An assessment of friction factor and viscosity models for predicting the refrigerant characteristics in adiabatic capillary tubes)

  • 손기동;박상구;정지환;김윤수
    • 대한설비공학회:학술대회논문집
    • /
    • 대한설비공학회 2008년도 동계학술발표대회 논문집
    • /
    • pp.47-54
    • /
    • 2008
  • Capillary tubes are widely used as expansion device in small refrigeration systems. The refrigerant flowing in the capillary tube experiences frictional and accelerational head losses, and flashing, simultaneously. In this paper flow characteristics of adiabatic capillary tubes with various friction factor models, two-phase viscosity models, and two-phase frictional multiplier models were simulated. The predicted pressure distribution, mass flow rate are compared with experimental data reported in literature. It is confirmed that the predicting accuracy with homogeneous model can be improved by employing the suitable correlations of friction factor and two-phase viscosity model, and two-phase frictional multiplier.

  • PDF

Calculation of the Reactance for a Magnetic Phase Created in a Steam Generator Tube Material

  • Ryu, Kwon-Sang;Jung, Jae-Kap;Son, Derac;Park, Duck-Gun
    • Journal of Magnetics
    • /
    • 제15권2호
    • /
    • pp.70-73
    • /
    • 2010
  • A magnetic phase is partly produced in a steam generator tube due to stress and heat, because steam generator tubes are exposed to high temperature, high pressure and radioactivity conditions. This adversely affects the safety of steam generator tubes. However, it is difficult to detect it using conventional eddy current methods. Therefore, a new type of probe is needed to separate the signals from the defects and magnetic phases. In this study, a new U-type yoke, which contained two types of coils, a magnetizing coil and detecting coil, was designed. In addition, the signal induced by the magnetic phase and defect in an Inconel 600 plate were simulated.

Explicit/Implicit FEM에 의한 Lower Arm Hydroforming 공정해석 (FE Analysis of Lower Arm Hydroforming by Implicit and Explicit Method)

  • 강영호;김정;장유철;강범수
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2000년도 추계학술대회논문집A
    • /
    • pp.783-788
    • /
    • 2000
  • Hydroforming is a method for forming circular tubes. If this technology is to be applied economically, it is essential to have knowledge of the avoidance of failure cases as well as of the behavior of the tube in the tool under the compressive stress and forces that are exerted by the machine. A finite element simulation for manufacturing of lower arm from straight tubes, using the hydroforming method, was performed to investigate the effects of varying process parameters. Explicit method is used to simulate hydroforming in many cases, but that is not included flow rule. And then it needs simulation for implicit method. It was simulated by two methods, implicit and explicit, to compare the result of the hydroforming.

  • PDF

Detectability and Sizing Ability of Rotating Pancake Coil Technique for Cracks in Steam Generator Tubes

  • Y. M. Cheong;K. W. Kang;Lee, Y. S.;T. E. Chung
    • Nuclear Engineering and Technology
    • /
    • 제30권4호
    • /
    • pp.377-385
    • /
    • 1998
  • Many nuclear power plants have experienced unscheduled shutdown due to the leakage of steam generator tubes. The leakages are normally due to the crack, possibly stress corrosion cracking (SCC) near the tube expansion at the top of tubesheet or at the tangential point of the row-1 U-bend region. The conventional eddy current technique, which makes use of a differential bobbin coil, has been found to be inadequate for the early detection of SCC. During the in-service inspection, therefore, it is a general practice that the rotating pancake coil (RPC) is used for detecting the cracks. Even in using RPC, however, it is difficult to determine the depth of the cracks quantitatively. This paper attempts to determine the detectability and sizing ability of RPC technique for axial or circumferential cracks at the tube expansion region. The simulated cracks with various dimensions were fabricated by electro-discharge machining (EDM) method. Experimental results are discussed with theoretical calculations.

  • PDF

ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions

  • Takeda, Takeshi
    • Nuclear Engineering and Technology
    • /
    • 제50권6호
    • /
    • pp.981-988
    • /
    • 2018
  • An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with operator recovery actions in a pressurized water reactor. The relief valve of broken SG opened three times after the start of intact SG secondary-side depressurization as the recovery action. Multi-dimensional phenomena specific to the SGTR accident appeared such as significant thermal stratification in a cold leg in broken loop especially during the operation of high-pressure injection (HPI) system. The RELAP5/MOD3.3 code overpredicted the broken SG secondary-side pressure after the start of the intact SG secondary-side depressurization, and failed to calculate the cold leg fluid temperature in broken loop. The combination of the number of the ruptured SG tubes and the HPI system operation difference was found to significantly affect the primary and SG secondary-side pressures through sensitivity analyses with the RELAP5 code.

계단이 포함된 건물 내부의 경로손실 예측과 측정 (Prediction and Measurement of the Path Loss in a Building including the Staircase)

  • 최태관;김성진;김채영
    • 대한전자공학회:학술대회논문집
    • /
    • 대한전자공학회 1999년도 하계종합학술대회 논문집
    • /
    • pp.219-222
    • /
    • 1999
  • A SBR/Image ray-tracing technique using triangular ray tubes to predict the effects of walls. rooms. floors, and staircase is considered. Suggested technique is very efficient to estimate the path loss in three-dimensional buildings including the staircase. The model to predict the path loss through walls and floors in a multifloored building is presented. Measurements are made for three corridors having the staircase at 850 MHz, Measured data shows a close agreement with a simulated data.

  • PDF

증기발생기 전열관에서의 응력부식균열 성장해석 (Simulation of Stress Corrosion Crack Growth in Steam Generator Tubes)

  • 신규인;박재학;김흥덕;정한섭
    • 한국안전학회지
    • /
    • 제15권3호
    • /
    • pp.57-65
    • /
    • 2000
  • The stress corrosion crack growth is simulated assuming a small axial surface crack inside a S/G tube. Internal pressure and residual stresses are considered as applied forces. Stress intensity factors along crack front, variation of crack shape and crack growth rate are obtained and discussed. It is noted that the aspect ratio of the crack is not depend on the initial crack shape but depend on the residual stress distribution.

  • PDF

경질 코팅의 고온 입자침식 현상 연구 (A Study on High Temperature Particles-Erosion of Hard Coatings)

  • 이의열;김종하
    • 한국표면공학회지
    • /
    • 제36권4호
    • /
    • pp.291-295
    • /
    • 2003
  • Many steam turbine components encounter solid particle erosion damage. It has been reported that particle erosion damage is caused by oxide scale exfoliation from boiler tubes. One of the most effective solutions to combat the erosion damage is the application of erosion resistant coatings on the turbine components. In this study, particle erosion resistance for various hard coatings such as nitride, Cr carbide and boride coatings was evaluated under the simulated erosion conditions of steam turbines. Based on the particle erosion tests, the boride coating was found to be more superior to others.

CANDU6 감속재 온도분포 계산을 위한 CFD 해석모델의 타당성 검토 (Validation of a CFD Analysis Model for the Calculation of CANDU6 Moderator Temperature Distribution)

  • 윤철;이보욱;민병주
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2001년도 추계학술대회논문집B
    • /
    • pp.499-504
    • /
    • 2001
  • A validation of a 3D CFD model for predicting local subcooling of moderator in the vicinity of calandria tubes in a CANDU reactor is performed. The small scale moderator experiments performed at Sheridan Park Experimental Laboratory(SPEL) in Ontario, Canada[1] is used for the validation. Also a comparison is made between previous CFD analyses based on 2DMOTH and PHOENICS, and the current model analysis for the same SPEL experiment. For the current model, a set of grid structures for the same geometry as the experimental test section is generated and the momentum, heat and continuity equations are solved by CFX-4.3, a CFD code developed by AEA technology. The matrix of calandria tubes is simplified by the porous media approach. The standard $k-\varepsilon$ turbulence model associated with logarithmic wall treatment and SIMPLEC algorithm on the body fitted grid are used and buoyancy effects are accounted for by the Boussinesq approximation. For the test conditions simulated in this study, the flow pattern identified is a buoyancy-dominated flow, which is generated by the interaction between the dominant buoyancy force by heating and inertial momentum forces by the inlet jets. As a result, the current CFD moderator analysis model predicts the moderator temperature reasonably, and the maximum error against the experimental data is kept at less than $2.0^{\circ}C$ over the whole domain. The simulated velocity field matches with the visualization of SPEL experiments quite well.

  • PDF