Predictions of one-group interfacial area transport in TRACE

Ted Worosz, Justin D. Talley, Seungjin Kim, Stephen M. Bajorek, Andrew Ireland

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

    Abstract

    In current nuclear reactor system analysis codes utilizing the two-fluid model, flow regime dependent correlations are used to specify the interfacial area concentration (a i). This approach does not capture the continuous evolution of the interfacial structures, and thus, it can pose issues near the transition boundaries. Consequently, a pilot version of the system analysis code TRACE is being developed that employs the interfacial area transport equation (IATE). In this approach, dynamic estimation of a i is provided through mechanistic models for bubble coalescence and breakup. The implementation of the adiabatic, one-group IATE into TRACE is assessed against experimental data from 50 air-water, two-phase flow conditions in pipes ranging in inner diameter from 2.54 to 20.32 cm for both vertical co-current upward and downward flows. Predictions of pressure, void fraction, bubble velocity, and a i data are made. TRACE employing the conventional flow regime-based approach is found to underestimate a i and can only predict linear trends since the calculation is governed by the pressure. Furthermore, trends opposite to that of the data are predicted for some conditions. In contrast, TRACE with the one-group IATE demonstrates a significant improvement in predicting the experimental data with an average disagreement of ± 13%. Additionally, TRACE with the one-group IATE is capable of predicting nonlinear axial development of a, by accounting for various bubble interaction mechanisms, such as coalescence and disintegration.

    Original languageEnglish (US)
    Title of host publicationInternational Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012
    Pages1988-1998
    Number of pages11
    StatePublished - Nov 19 2012
    EventInternational Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 - Chicago, IL, United States
    Duration: Jun 24 2012Jun 28 2012

    Publication series

    NameInternational Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012
    Volume3

    Other

    OtherInternational Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012
    CountryUnited States
    CityChicago, IL
    Period6/24/126/28/12

    Fingerprint

    Coalescence
    Systems analysis
    Void fraction
    Disintegration
    Nuclear reactors
    Bubbles (in fluids)
    Two phase flow
    Pipe
    Fluids
    Air
    Water

    All Science Journal Classification (ASJC) codes

    • Energy Engineering and Power Technology
    • Nuclear Energy and Engineering

    Cite this

    Worosz, T., Talley, J. D., Kim, S., Bajorek, S. M., & Ireland, A. (2012). Predictions of one-group interfacial area transport in TRACE. In International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 (pp. 1988-1998). (International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012; Vol. 3).
    Worosz, Ted ; Talley, Justin D. ; Kim, Seungjin ; Bajorek, Stephen M. ; Ireland, Andrew. / Predictions of one-group interfacial area transport in TRACE. International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012. 2012. pp. 1988-1998 (International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012).
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    title = "Predictions of one-group interfacial area transport in TRACE",
    abstract = "In current nuclear reactor system analysis codes utilizing the two-fluid model, flow regime dependent correlations are used to specify the interfacial area concentration (a i). This approach does not capture the continuous evolution of the interfacial structures, and thus, it can pose issues near the transition boundaries. Consequently, a pilot version of the system analysis code TRACE is being developed that employs the interfacial area transport equation (IATE). In this approach, dynamic estimation of a i is provided through mechanistic models for bubble coalescence and breakup. The implementation of the adiabatic, one-group IATE into TRACE is assessed against experimental data from 50 air-water, two-phase flow conditions in pipes ranging in inner diameter from 2.54 to 20.32 cm for both vertical co-current upward and downward flows. Predictions of pressure, void fraction, bubble velocity, and a i data are made. TRACE employing the conventional flow regime-based approach is found to underestimate a i and can only predict linear trends since the calculation is governed by the pressure. Furthermore, trends opposite to that of the data are predicted for some conditions. In contrast, TRACE with the one-group IATE demonstrates a significant improvement in predicting the experimental data with an average disagreement of ± 13{\%}. Additionally, TRACE with the one-group IATE is capable of predicting nonlinear axial development of a, by accounting for various bubble interaction mechanisms, such as coalescence and disintegration.",
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    year = "2012",
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    Worosz, T, Talley, JD, Kim, S, Bajorek, SM & Ireland, A 2012, Predictions of one-group interfacial area transport in TRACE. in International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012. International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, vol. 3, pp. 1988-1998, International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, Chicago, IL, United States, 6/24/12.

    Predictions of one-group interfacial area transport in TRACE. / Worosz, Ted; Talley, Justin D.; Kim, Seungjin; Bajorek, Stephen M.; Ireland, Andrew.

    International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012. 2012. p. 1988-1998 (International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012; Vol. 3).

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

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    Worosz T, Talley JD, Kim S, Bajorek SM, Ireland A. Predictions of one-group interfacial area transport in TRACE. In International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012. 2012. p. 1988-1998. (International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012).