• Title/Summary/Keyword: Valve reynold number

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A Study on the Design of Liquid Flow Control Valves for the Pants and Ships(II) (플랜트 및 선박의 액체용 우량제어밸브 설계에 관한 연구(II))

  • 최순호;배윤영;김태한;한기남;주경인
    • Journal of Advanced Marine Engineering and Technology
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    • v.19 no.2
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    • pp.1-9
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    • 1995
  • The processing paper has devoted to the theory of the flow equations, the basic derivative procedure, the meaning of a valve flow coefficient $C_v$, the valve Reynolds R$R_{ev}$ and its application for liquid control valves, which applicable under the condition of a non-critical flow and the case of piping geometry factor $F_p$=1.0. However there is no information on the effects of fittings, a critical flow and the flow resistance coefficient of a valve equivalent to that of pipe which is conveniently used in the piping design. Since the piping systems of plants or ships generally contain various fittings such as expanders and reducers due to different size between pipes and valves and there may occur a critical flow, that a mass flowrate is maintained to be constant, due to the pressure drop in a piping when a liquid is initially maintainder ar a saturated temperature or at nearby corresponding to upstream pressure, system designer should have a knowledge of the effect to flow due to fittings and the critical flow phenomenon of a liquid. This study is performed to inform system designers with the critical flow phenomenon of a liquid, a valve resistance coefficient, a valve geometry factor and their applications.

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Experimental Research for Identification of Thermal Stratification Phenomena in The Nuclear Powerplant Emergency Core Coolant System(ECCS). (원전 비상 노심냉각계통 배관 열성층화 현상 규명을 위한 실험적 연구)

  • Song, Dho-In;Choi, Young-Don;Park, Min-Su
    • Proceedings of the KSME Conference
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    • 2001.11b
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    • pp.735-740
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    • 2001
  • In the nuclear power plant, emergency core coolant system(ECCS) is furnished at reactor coolant system(RCS) in order to cool down high temperature water in case of emergency. However, in this coolant system, it occurs thermal stratification phenomena in case that there is the mixing of cooling water and high temperature water due to valve leakage in ECCS. This thermal stratification phenomena raises excessive thermal stresses at pipe wall. Therefore, this phenomena causes the accident that reactor coolant flows in reactor containment in the nuclear power plant due to the deformation of pipe and thermal fatigue crack(TFC) at the pipe wall around the place that it exists. Hence, in order to fundamental identification of this phenomena, it requires the experimental research of modeling test in the pipe flow that occurs thermal stratification phenomena. So, this paper models RCS and ECCS pipe arrangement and analyzes the mechanism of thermal stratification phenomena by measuring of temperature in variance with leakage flow rate in ECCS modeled pipe and Reynold number in RCS modeled pipe. Besides, results of this experiment is compared with computational analysis which is done in advance.

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