Search Results - "Sabharwall, P."

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  1. 1

    An experimental study of solid and liquid aerosol transport in a horizontal square channel by Chavez, R., Orea, D., Choi, B., Nguyen, T. D., Anand, N. K., Hassan, Y., Sabharwall, P.

    Published in Aerosol science and technology (01-12-2020)
    “…Various industrial applications such as medical/pharmaceutical sprays, heating, ventilation and air conditioning systems, and other solid/liquid atomization…”
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  2. 2

    Comparative analysis of compact heat exchangers for application as the intermediate heat exchanger for advanced nuclear reactors by Bartel, N., Chen, M., Utgikar, V.P., Sun, X., Kim, I.-H., Christensen, R., Sabharwall, P.

    Published in Annals of nuclear energy (01-07-2015)
    “…•Compact heat exchanger designs evaluated for advanced nuclear reactor applications.•Wavy channel PCHE compared with offset strip-fin heat exchanger…”
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  3. 3

    PARTICLE DEPOSITION STUDY IN A HORIZONTAL SQUARE CHANNEL USING HIGH-RESOLUTION IMAGING by Orea, D., Chavez, R., Nguyen, D.T., Vaghetto, R., Anand, N. K., Hassan, Y. A., Sabharwall, P.

    Published in EPJ Web of conferences (01-01-2021)
    “…The ongoing research at Texas A&M University (TAMU) aims to develop and implement measurement techniques to quantify fission product transport and related…”
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  4. 4

    Scaling analysis for the direct reactor auxiliary cooling system for FHRs by Lv, Q., Wang, X., Kim, I.H., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., Sabharwall, P.

    Published in Nuclear engineering and design (15-04-2015)
    “…•A scaling analysis for the direct reactor auxiliary cooling system is performed.•Key dimensionless numbers are developed and similarity laws are proposed.•A…”
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  5. 5

    Modeling and simulation of control system response to temperature disturbances in a coupled heat exchangers-AHTR system by Skavdahl, I., Utgikar, V.P., Christensen, R., Sabharwall, P., Chen, M., Sun, X.

    Published in Nuclear engineering and design (15-04-2016)
    “…•Control architecture defined for nuclear reactor-coupled heat exchangers system.•MATLAB code developed for simulation of system response for various…”
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  6. 6

    DRACS thermal performance evaluation for FHR by Lv, Q., Lin, H.C., Kim, I.H., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G.L., Wilson, D.F., Sabharwall, P.

    Published in Annals of nuclear energy (01-03-2015)
    “…•A computer code for DRACS thermal performance evaluation for FHR is developed.•The code is validated using available experimental data from the…”
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  7. 7

    Optical Absorption of Fused Silica and Sapphire Exposed to Neutron and Gamma Radiation with Simultaneous Thermal Annealing by Morgan, B.W., Van Zile, M.P., Petrie, C.M., Sabharwall, P., Burger, M., Jovanovic, I.

    Published in Journal of nuclear materials (01-11-2022)
    “…•Radiation-induced attenuation in fused silica and sapphire was measured with post-irradiation thermal annealing and with thermal annealing during…”
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  8. 8

    Radiation-induced negative optical nonlinearities in fused silica, sapphire, and borosilicate glass by Morgan, B.W., Van Zile, M.P., Petrie, C.M., Sabharwall, P., Burger, M., Jovanovic, I.

    Published in Journal of nuclear materials (15-08-2023)
    “…Negative nonlinear absorption is reported in neutron- and gamma-irradiated high-OH content fused silica, low-OH content fused silica, sapphire, borosilicate…”
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  9. 9

    Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor by Bhowmik, P.K., Sabharwall, P., Johnson, J.T., Retamales, M.E.T., Wang, C., O'Brien, J.E., Lietwiler, C., Wu, Q.

    Published in Nuclear engineering and design (01-08-2024)
    “…•Presents scaling analysis and similarity criteria for water-cooled small modular reactor systems.•Formulates governing equations and nondimensional parameters…”
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  10. 10

    Challenges in the development of high temperature reactors by Sabharwall, Piyush, Bragg-Sitton, Shannon M., Stoots, Carl

    Published in Energy conversion and management (01-10-2013)
    “…•Challenges for advance reactor concepts (such as VHTR and AHTR) are discussed.•Both the VHTR and AHTR design offer promising performance characteristics and…”
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  11. 11
  12. 12

    Scaling analysis for the direct reactor auxiliary cooling system for FHRs by Lv, Q., Wang, X., Kim, I. H., Sun, X., Christensen, R. N., Blue, T. E., Yoder, G., Wilson, D., Sabharwall, P.

    Published in Nuclear engineering and design (04-02-2015)
    “…The Direct Reactor Auxiliary Cooling System (DRACS) is a passive residual heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor…”
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  13. 13
  14. 14

    DRACS thermal performance evaluation for FHR by Lv, Q., Lin, H. C., Kim, I. H., Sun, X., Christensen, R. N., Blue, T. E., Yoder, Graydon L., Wilson, Dane F., Sabharwall, P.

    Published in Annals of nuclear energy (24-11-2014)
    “…Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor (FHR)…”
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    Journal Article