[논문]Heat Transfer Characteristics of an Internally-Heated Annulus Cooled with R-134a Near the Critical Pressure

Hong, Sung-Deok; Chun, Se-Young; Kim, Se-Yun; Baek, Won-Pil

Heat Transfer Characteristics of an Internally-Heated Annulus Cooled with R-134a Near the Critical Pressure 원문보기

Journal of the Korean Nuclear Society = 원자력학회지, v.36 no.5, 2004년, pp.403 - 414

Hong, Sung-Deok (Korea Atomic Energy Research Institute) , Chun, Se-Young (Korea Atomic Energy Research Institute) , Kim, Se-Yun (Korea Atomic Energy Research Institute) , Baek, Won-Pil (Korea Atomic Energy Research Institute)

Abstract ▼ AI-Helper

An experimental study of heat transfer characteristics near the critical pressure has been performed with an internally-heated vertical annular channel cooled by R-134a fluid. Two series of tests have been completed: (a) steady-state critical heat flux (CHF) tests, and (b) heat transfer tests for pressure reduction transients through the critical pressure. In the present experimental range, the steady-state CHF decreases with increase of the system pressure for fixed inlet mass flux and subcooling. The CHF falls sharply at about 3.8 MPa and shows a trend towards converging to zero as the pressure approaches the critical point of 4.059 MPa. The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall, because the CHF occurs at remarkably low power levels. In the pressure reduction transients, as soon as the pressure passes below the critical pressure from the supercritical pressure, the wall temperatures rise rapidly up to very high values due to the departure from nucleate boiling. The wall temperature reaches a maximum at the saturation point of the outlet temperature, and then tends to decrease gradually.

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가설 설정

(b) When the pressure approaches the critical pressure, the critical quality also drops very sharply and represents subcooled conditions. (c) The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall because the CHF occurs at remarkably low power levels.
and (b) heat transfer tests during pressure decrease from supercritical to sub-critical pressures. The following conclusions can be drawn from this study:
conditions. (c) The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall because the CHF occurs at remarkably low power levels.

제안 방법

The heat loss in the test section is taken into account in the calculation of heat flux. Before starting a set of experiments, pretests (i.e., heat balance tests) were carried out to estimate the heat loss from the test section. The heat losses estimated by the pretests for each pressure condition are less than 1.
FPPs. Therefore, the experimental study has been performed on steady-state CHF under sub-critical pressure conditions near the critical point and heat transfer during transition from the supercritical to sub-critical pressures with an internally-heated annulus cooled by R-134a (HFC₁₃4a) fluid. In this paper, the results from these experiments are presented and the heat transfer characteristics near the critical pressure are discussed.

대상 데이터

The experimental work has been performed in the Freon Thermal-Hydraulic Experimental Loop at the Korea Atomic Energy Research Institute (KAERI). This loop uses R-134a (Pc = 4.

이론/모형

For performance of the experiments and analysis of the experimental data, the thermodynamic properties of R-134a from NIST Chemistry WebBook are used [6]. The uncertainties of the measuring sy아。m are estimated from calibration of the sensors and the accuracy of the equipment, according to a propagation error analysis based on Taylor's series method [7]. The evaluated maximum uncertainties of the pressures, flow rates, and temperatures are less than +0.

참고문헌 (10)

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상세보기
J. D. Jackson and W. B. Hall, 'Forced convection heat transfer to fluids at supercritical pressure,' Turbulent forced convection in channels and bundles (Edited by S. Kakac and D. B.Spalding), Hemisphere,Vol. 2, pp. 563-612 (1979)
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Se-Young Chun, Heung-June Chung, Sung-Deok Hong, Sun-Kyu Yang and Moon-Ki Chung, 'Critical heat flux in uniformly heated vertical annulus under a wide range of pressures-0.57 to 15.0 MPa,' Journal of the Korean Nuclear Society, 32[2], pp. 128-141 (2000)
I. L. Pioro, D. C. Groeneveld, L. K. H. Leung, S. S. Doerffer, S. C. Cheng, Yu. V. Antoshko, Y. Guo and A. Vasic, 'Comparison of CHF measurements in horizontal and vertical tubes cooled with R-134a,' Int. J. Heat Mass Transfer, 45, pp. 4435-4450 (2002)

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Heat Transfer Characteristics of an Internally-Heated Annulus Cooled with R-134a Near the Critical Pressure 원문보기

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Heat Transfer Characteristics of an Internally-Heated Annulus Cooled with R-134a Near the Critical Pressure 원문보기

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