• 제목/요약/키워드: Subcooled transient boiling curve

검색결과 3건 처리시간 0.016초

탄소강의 담금질 열전달에 관한 연구 (A Study on the Heat Transfer of Carbon Steels in Quenching)

  • 김경근;윤석훈
    • Journal of Advanced Marine Engineering and Technology
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    • 제19권2호
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    • pp.20-26
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    • 1995
  • The very rapid cooling problem from $820^{\circ}$C to $20^{\circ}$C on the surface of the steel by thermal conduction including the latent heat of phase transformation of steel and by transient boiling heat transfer of water are considered to principal problem in quenching. The transient boiling process of water at the surface of specimen during the quenching process were experimentally analyzed. Then the heat flux was numerically calculated by the numerical method of inverse heat condition problem. In this report, the simulation program to calculate the cooling curves for large rolls was made using the subcooled transient boiling curve as a boundary condition. By this simulation program, the cooling curves of rolls from D=50mm to D=200mm were calculated and the effects of agitation of circulation of water also investigated.

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고온 강재의 담금질 열전달에 관한 연구 제1보 : 과냉과도 비등열전달과 냉각곡선 (A Study on the Heat Transfer of the High Temperature Metals in Quenching 1st Reprot; Subcooled Transient Boiling Heat Transfer and Colling Curves)

  • 윤석훈;홍영표;김경근;김용모
    • 대한기계학회논문집
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    • 제17권6호
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    • pp.1529-1540
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    • 1993
  • 본 연구에서는 금속 열처리를 위한 고온면의 막비등 급냉각에 관한 1차적 연구로서 과냉과도 비등곡선의 정확한 형상과 냉각제의 냉각조건이 강재의 과냉과도 비등열전달에 미치는 영향, $A_1$변태점 부근의 $A_1$냉각속도와 상변태열량광의 관계, 그리고 상변태열이 냉각곡선에 미치는 영향 등을 규명하고자 한다.

환상유로에 있어서 수직고온관의 과도적 냉각과정에 관한 연구 (A study on the transient cooling process of a vertical-high temperature tube in an annular flow channel)

  • 정대인;김경근
    • Journal of Advanced Marine Engineering and Technology
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    • 제10권2호
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    • pp.156-164
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    • 1986
  • In the case of boiling on high temperature wall, vapor film covers fully or parcially the surface. This phenomenon, film boiling or transition boiling, is very important in the surface heat treatment of metal, design of cryogenic heat exchanger and emergency cooling of nuclear reactor. Mainly supposed hydraulic-thermal accidents in nuclear reactor are LCCA (Loss of Coolant Accident) and PCM (Power-Cooling Mismatch). Recently, world-wide studies on reflooding of high temperature rod bundles after the occurrence of the above accidents focus attention on wall temperature history and required time in transient cooling process, wall superheat at rewet point, heat flux-wall superheat relationship beyond the transition boiling region, and two-phase flow state near the surface. It is considered that the further systematical study in this field will be in need in spite of the previous results in ref. (2), (3), (4). The paper is the study about the fast transient cooling process following the wall temperature excursion under the CHF (Critical Heat Flux) condition in a forced convective subcooled boiling system. The test section is a vertically arranged concentric annulus of 800 mm long and 10 mm hydraulic diameter. The inner tube, SUS 304 of 400 mm long, 8 mm I.D, and 7 mm O.D., is heated uniformly by the low voltage AC power. The wall temperature measurements were performed at the axial distance from the inlet of the heating tube, z=390 mm. 6 chromel- alumel thermocouples of 76 .mu.m were press fitted to the inner surface of the heating tube periphery. To investigate the heat transfer characteristics during the fast transient cooling process, the outer surface (fluid side) temperature and the surface heat flux are computed from the measured inner surface temperature history by means of a numerical method for inverse problems of transient heat conduction. Present cooling (boiling) curve is sufficiently compared with the previous results.

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