Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System

Fan-bill B. Cheung, J. Yang, M. B. Dizon, J. L. Rempe, K. Y. Suh, S. B. Kim

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    15 Citations (Scopus)

    Abstract

    As part of joint U.S.-Korean International Nuclear Engineering Research Initiative (INERI) investigating methods to enhance external cooling of advanced reactor vessel under severe accident conditions, a scaling analysis has been performed to study the phenomena of external cooling of an advanced reactor vessel under severe accident conditions. Five key transfer processes have been considered and the characteristic time for each of these processes has been determined and compared with the residence time for external reactor vessel cooling (ERVC) in the flow channel. To complement the scaling analysis, an ERVC upward co-current two-phase flow model has been developed to predict the total mass flow rate induced in the annular channel by the process of downward facing boiling on the vessel outer surface. The model takes into account the wall heat flux level, the geometry of the vessel/insulation system, the local variation of the cross-sectional flow area, and the pressure drops through various segments of the channel. Based on the results of the ERVC flow calculations and the scaling analysis, criteria for experimental simulation have been established to assure that the ERVC phenomena simulated in laboratory-scale experiments would have the same effects as those anticipated for the full-scale reactor system.

    Original languageEnglish (US)
    Title of host publicationProceedings of the 2003 ASME Summer Heat Transfer Conference, Volume 2
    Pages393-401
    Number of pages9
    StatePublished - Dec 1 2003
    Event2003 ASME Summer Heat Transfer Conference (HT2003) - Las Vegas, NV, United States
    Duration: Jul 21 2003Jul 23 2003

    Publication series

    NameProceedings of the ASME Summer Heat Transfer Conference
    Volume2003

    Other

    Other2003 ASME Summer Heat Transfer Conference (HT2003)
    CountryUnited States
    CityLas Vegas, NV
    Period7/21/037/23/03

    Fingerprint

    Boiling liquids
    Insulation
    Steam
    Cooling
    Accidents
    Nuclear engineering
    Engineering research
    Channel flow
    Two phase flow
    Pressure drop
    Heat flux
    Flow rate
    Geometry
    Experiments

    All Science Journal Classification (ASJC) codes

    • Engineering(all)

    Cite this

    Cheung, F. B., Yang, J., Dizon, M. B., Rempe, J. L., Suh, K. Y., & Kim, S. B. (2003). Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System. In Proceedings of the 2003 ASME Summer Heat Transfer Conference, Volume 2 (pp. 393-401). (Proceedings of the ASME Summer Heat Transfer Conference; Vol. 2003).
    Cheung, Fan-bill B. ; Yang, J. ; Dizon, M. B. ; Rempe, J. L. ; Suh, K. Y. ; Kim, S. B. / Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System. Proceedings of the 2003 ASME Summer Heat Transfer Conference, Volume 2. 2003. pp. 393-401 (Proceedings of the ASME Summer Heat Transfer Conference).
    @inproceedings{8035b3884243482bb0877bde7d4826c5,
    title = "Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System",
    abstract = "As part of joint U.S.-Korean International Nuclear Engineering Research Initiative (INERI) investigating methods to enhance external cooling of advanced reactor vessel under severe accident conditions, a scaling analysis has been performed to study the phenomena of external cooling of an advanced reactor vessel under severe accident conditions. Five key transfer processes have been considered and the characteristic time for each of these processes has been determined and compared with the residence time for external reactor vessel cooling (ERVC) in the flow channel. To complement the scaling analysis, an ERVC upward co-current two-phase flow model has been developed to predict the total mass flow rate induced in the annular channel by the process of downward facing boiling on the vessel outer surface. The model takes into account the wall heat flux level, the geometry of the vessel/insulation system, the local variation of the cross-sectional flow area, and the pressure drops through various segments of the channel. Based on the results of the ERVC flow calculations and the scaling analysis, criteria for experimental simulation have been established to assure that the ERVC phenomena simulated in laboratory-scale experiments would have the same effects as those anticipated for the full-scale reactor system.",
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    Cheung, FB, Yang, J, Dizon, MB, Rempe, JL, Suh, KY & Kim, SB 2003, Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System. in Proceedings of the 2003 ASME Summer Heat Transfer Conference, Volume 2. Proceedings of the ASME Summer Heat Transfer Conference, vol. 2003, pp. 393-401, 2003 ASME Summer Heat Transfer Conference (HT2003), Las Vegas, NV, United States, 7/21/03.

    Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System. / Cheung, Fan-bill B.; Yang, J.; Dizon, M. B.; Rempe, J. L.; Suh, K. Y.; Kim, S. B.

    Proceedings of the 2003 ASME Summer Heat Transfer Conference, Volume 2. 2003. p. 393-401 (Proceedings of the ASME Summer Heat Transfer Conference; Vol. 2003).

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

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    AU - Suh, K. Y.

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    AB - As part of joint U.S.-Korean International Nuclear Engineering Research Initiative (INERI) investigating methods to enhance external cooling of advanced reactor vessel under severe accident conditions, a scaling analysis has been performed to study the phenomena of external cooling of an advanced reactor vessel under severe accident conditions. Five key transfer processes have been considered and the characteristic time for each of these processes has been determined and compared with the residence time for external reactor vessel cooling (ERVC) in the flow channel. To complement the scaling analysis, an ERVC upward co-current two-phase flow model has been developed to predict the total mass flow rate induced in the annular channel by the process of downward facing boiling on the vessel outer surface. The model takes into account the wall heat flux level, the geometry of the vessel/insulation system, the local variation of the cross-sectional flow area, and the pressure drops through various segments of the channel. Based on the results of the ERVC flow calculations and the scaling analysis, criteria for experimental simulation have been established to assure that the ERVC phenomena simulated in laboratory-scale experiments would have the same effects as those anticipated for the full-scale reactor system.

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    Cheung FB, Yang J, Dizon MB, Rempe JL, Suh KY, Kim SB. Scaling of Downward Facing Boiling and Steam Venting in a Reactor Vessel/Insulation System. In Proceedings of the 2003 ASME Summer Heat Transfer Conference, Volume 2. 2003. p. 393-401. (Proceedings of the ASME Summer Heat Transfer Conference).