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Filtering by: Creator Lizarraga-Arciniega, Jose R. Remove constraint Creator: Lizarraga-Arciniega, Jose R. Advisor Wu, Qiao Remove constraint Advisor: Wu, Qiao

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  • On the effects of centrifugal forces in air-water two-phase flow regime transitions of an adiabatic helical geometry

    Creator:
    Young, Eric P.
    Abstract:
    Two-phase flow in helical conduits is important in many industries where reaction between components, heat transfer, and mass transport are utilized as processes. The helical design is chosen for the effects of secondary flow patterns that reduce axial dispersion, increased heat transfer, and also their compact design. The first is...
    Resource Type:
    Dissertation
    Full Text:
    Geometry. Abstract approved: José Reyes Qiao Wu Two-phase flow in helical conduits is important in many

  • Performance and stability analysis of gas-injection enhanced natural circulation in heavy-liquid-metal-cooled systems

    Creator:
    Yoo, Yeon-Jong
    Abstract:
    The purpose of this study is to investigate the performance and stability of the gas-injection enhanced natural circulation in heavy-liquid-metal-cooled systems. The target system is STAR-LM, which is a 400-MWt-class advanced lead-cooled fast reactor under development by Argonne National Laboratory and Oregon State University. The primary loop of STAR-LM relies...
    Resource Type:
    Dissertation
    Full Text:
    Systems. Abstract approved: José N. Iéyes, Jr. _ Qiao Wu The purpose of this study is to investigate

  • Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification

    Creator:
    Abel, Kent C.
    Abstract:
    The next generation of nuclear safety analysis computer codes will require detailed modeling of two-phase fluid flow. The most complete and fundamental model used for these calculations is known as the two-fluid model. It is the most accurate of the two-phase models since it considers each phase independently and links...
    Resource Type:
    Dissertation
    Full Text:
    . Abstract approved: José N. Rey9 Jr. Qiao Wu The next generation of nuclear safety analysis computer codes

  • Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe

    Creator:
    Welter, Kent B.
    Abstract:
    Under simulated accident conditions, tees in the primary coolant loop of a Pressurized Water Reactor (PWR) can deviate from their original design purpose and become separators that effectively remove core heat sink capacity. This method of primary coolant removal is a phenomelogical subset of phase separation known as liquid entrainment,...
    Resource Type:
    Dissertation
    Full Text:
    Jose' N. Reyes, Jr. Under simulated accident conditions, tees in the primary coolant loop of a

  • The Development of a Mechanistic Critical Heat Flux Correlation

    Creator:
    Luitjens, Jeffrey M.
    Abstract:
    A mechanistic based critical heat flux (CHF) correlation has been developed derived from a mass, momentum, and energy balance at a nucleation site for water. The trigger mechanism for the CHF condition is postulated to be related to the maximum boiling frequency on a heated surface. It is observed that...
    Resource Type:
    Dissertation
    Full Text:
    contact angle θr receding contact angle θs static contact angle ξ non-dimensional temperature A area

  • Quantified PIRT and uncertainty quantification for computer code validation

    Creator:
    Luo, Hu
    Abstract:
    This study is intended to investigate and propose a systematic method for uncertainty quantification for the computer code validation application. Uncertainty quantification has gained more and more attentions in recent years. U.S. Nuclear Regulatory Commission (NRC) requires the use of realistic best estimate (BE) computer code to follow the rigorous...
    Resource Type:
    Dissertation
    Full Text:
    appreciation to Dr. Jose Reyes, Dr. Brian Woods, Dr. Deborah Pence, Dr. Weidong Wang and Dr. Julia Zhang for

  • Dynamic System Scaling Application to Accelerated Nuclear Fuel Testing

    Creator:
    Yoshiura, Ramon K.
    Abstract:
    The development of nuclear fuel and materials requires is a continuous effort to investigate the acute and prolonged effects of irradiation, thermal-material stress, chemical change, or other conceivable damage mechanics acquired during normal operation or accident scenarios throughout its lifetime. As in-core fuel property measurement techniques advance to support in...
    Resource Type:
    Dissertation
    Full Text:
    unknown. I'd also like to thank Dr. Daniel Wachs, Dr. Jose Reyes, and fellow scholar Alexan- der Duenas

  • Flat Plate Free Convective Heat Transfer

    Creator:
    Bristol, Benjanmin R.
    Abstract:
    The OSU MASLWR Test facility is a scaled integral systems LOCA and proof-of-concept test facility for the Multi-Application Small Light Water Reactor design concept. A unique feature of this design is to utilize a small high pressure containment vessel to provide the safety containment function for an integral reactor pressure...
    Resource Type:
    Masters Thesis
    Full Text:
    AN ABSTRACT OF THE THESIS OF Benjanmin R. Bristol for

  • SMR full-power scaling analysis and numerical simulation for nuclear hybrid energy system testing

    Creator:
    Hoover, Kyle J.
    Abstract:
    A scaling analysis of the Oregon State University (OSU) - Multi-Application Small Light Water Reactor (MASLWR) system has been developed, and an existing RELAP5-3D model of the facility was improved. The purpose of this study is to support the research of hybrid energy systems, being led by Idaho National Laboratory...
    Resource Type:
    Masters Thesis
    Full Text:
    the scaling factors are presented for this study. ΠR = Πm Πp (4.13) 36 4.1.1 Definition of

  • Design and testing of intrusive conductivity probes for the measurement of two-phase flow parameters

    Creator:
    McCreary, David M.
    Abstract:
    This thesis examines two techniques for measuring two-phase flow parameters in an air/water system using intrusive conductivity probes. Specifically, the theoretical derivation for measuring void fraction and interfacial area using a two-sensor needle-type probe is derived, and a statistical analysis of the accuracy using the two-sensor probe for measuring interfacial...
    Resource Type:
    Masters Thesis
    Full Text:
    be a source of inspiration for me. I especially thank Dr. José Reyes, Jr., Principal Investigator of