A new mechanistic model of critical heat flux in forced-convection subcooled boiling

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Because of its practical importance and various industrial applications, the process of subcooled flow boiling has attracted a lot of attention in the research community in the past. However, the existing models are primarily phenomenological and are based on correlating experimental data rather than on a first-principle analysis of the governing physical phenomena. Even though the mechanisms leading to critical heat flux (CHF) are very complex, the recent progress in the understanding of local phenomena of multiphase flow and heat transfer, combined with the development of mathematical models and advanced Computational Fluid Dynamics (CFD) methods, makes analytical predictions of CHF ... continued below

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19 p.

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Alajbegovic, A.; Kurul, N.; Podowski, M.Z.; Drew, D.A. & Lahey, R.T. Jr. October 1, 1997.

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  • Knolls Atomic Power Laboratory
    Publisher Info: Knolls Atomic Power Lab., Schenectady, NY (United States)
    Place of Publication: Schenectady, New York

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Description

Because of its practical importance and various industrial applications, the process of subcooled flow boiling has attracted a lot of attention in the research community in the past. However, the existing models are primarily phenomenological and are based on correlating experimental data rather than on a first-principle analysis of the governing physical phenomena. Even though the mechanisms leading to critical heat flux (CHF) are very complex, the recent progress in the understanding of local phenomena of multiphase flow and heat transfer, combined with the development of mathematical models and advanced Computational Fluid Dynamics (CFD) methods, makes analytical predictions of CHF quite feasible. Various mechanisms leading to CHF in subcooled boiling have been investigated. A new model for the predictions of the onset of CHF has been developed. This new model has been coupled with the overall boiling channel model, numerically implemented in the CFX 4 computer code, tested and validated against the experimental data of Hino and Ueda. The predicted critical heat flux for various channel operating conditions shows good agreement with the measurements using the aforementioned closure laws for the various local phenomena governing nucleation and bubble departure from the wall. The observed differences are consistent with typical uncertainties associated with CHF data.

Physical Description

19 p.

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INIS; OSTI as DE99001885

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  • NURETH-8: 8. international topical meeting on nuclear reactor thermal-hydraulics, Kyoto (Japan), 30 Sep - 4 Oct 1997

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  • Other: DE99001885
  • Report No.: KAPL-P--000160
  • Report No.: K--97041;CONF-970922--
  • Grant Number: AC12-76SN00052
  • Office of Scientific & Technical Information Report Number: 319775
  • Archival Resource Key: ark:/67531/metadc683902

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  • October 1, 1997

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  • July 25, 2015, 2:20 a.m.

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  • May 16, 2016, 6:30 p.m.

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Alajbegovic, A.; Kurul, N.; Podowski, M.Z.; Drew, D.A. & Lahey, R.T. Jr. A new mechanistic model of critical heat flux in forced-convection subcooled boiling, article, October 1, 1997; Schenectady, New York. (digital.library.unt.edu/ark:/67531/metadc683902/: accessed August 14, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.