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Filtering by: Creator Brevig, Rod E. Remove constraint Creator: Brevig, Rod E. Committee Member Wu, Qiao Remove constraint Committee Member: Wu, Qiao

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  • Design, fabrication, and characterization of the laser-imaged natural circulation (LINC) facility

    Creator:
    Goodrich, Sam S.
    Abstract:
    Currently there is a great amount of interest in the phenomena of natural circulation as a cooling mechanism for normal operation as well as emergency conditions in nuclear reactors and spent fuel pools. In order to better understand this phenomena for the specific geometry of vertical, heated rods in water,...
    Resource Type:
    Masters Thesis
    Full Text:
    of 100 mm along the entrance region between the two rods at one symmetrical rod power. In addition

  • Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

    Creator:
    Utberg, John E., Jr
    Abstract:
    The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the MHTGR will perform during a Depressurized Conduction Cooldown (DCC) accident, which generally can be divided into three phases: depressurization, air ingress, and natural circulation. After...
    Resource Type:
    Masters Thesis
    Full Text:
    Exchange Phenomenon in the High Temperature Test Facility AN ABSTRACT OF THE THESIS OF John E

  • Fuel Dispersal Under LOCA Conditions

    Creator:
    Latimer, Griffen D.
    Abstract:
    Most operating power reactors use oxide fuel in the form of uranium oxide (UO2) which is robust against high temperatures but suffers from poor mechanical performance at high levels of burnup. Currently, the maximum average burnup in light water reactors in the US is 62.5 GWd/t, which is partially imposed...
    Resource Type:
    Dissertation
    Full Text:
    ), unirradiated rod testing (group B), and irradiated rod testing (groups C, D, E, F, and G). For the

  • Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

    Creator:
    Goodrich, Sam S.
    Abstract:
    In recent years, the global nuclear industry has placed a greater emphasis on passively safe reactor designs. In particular, much attention and design work has been applied to engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent fuel pools. The...
    Resource Type:
    Dissertation
    Full Text:
    ..................... 130 Figure 5.6 Custom heater rod cross-sectional diagram example ............................ 134

  • System model of a natural circulation integral test facility

    Creator:
    Galvin, Mark Robert, 1967-
    Abstract:
    The Department of Nuclear Engineering and Radiation Health Physics (NE/RHP) at Oregon State University (OSU) has been developing an innovative modular reactor plant concept since being initiated with a Department of Energy (DoE) grant in 1999. This concept, the Multi-Application Small Light Water Reactor (MASLWR), is an integral pressurized water...
    Resource Type:
    Dissertation
    Full Text:
    Losses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 3.5 Rod Control Module

  • An experimental study of laminarization induced by acceleration and curvature

    Creator:
    Jackson, R. Brian
    Abstract:
    The Generation IV Very High Temperature Reactor (VHTR) design is being actively studied in various countries for application due to its inherent passive safe design, higher thermal efficiencies, and proposed capability of providing high temperature process heat. The pebble bed core is one of two core designs used in gas...
    Resource Type:
    Dissertation
    Full Text:
    UNCERTAINTY ANALYSIS ......................................... 185 E: CONVERGENCE OF PIV MEASUREMENTS

  • An Exploration of Used Fuel Sharing in Multi-Reactor Power Plants

    Creator:
    Lilley, Benjamin C.
    Abstract:
    Nuclear fuel management is an optimization problem on many levels. Finding “viable” solutions for the core reload design problem is difficult without expert knowledge and software automation. Small modular reactors with a shared used fuel pool demonstrate a novel opportunity for fuel cycle optimization. A Python package was developed and...
    Resource Type:
    Dissertation
    Full Text:
    Figure Page 1.1 A typical PWR fuel pellet, rod, and assembly. (Image: https://www. foronuclear.org/en

  • Development of a Rapid Power Transient Critical Heat Flux Model

    Creator:
    Brown, Emory G.
    Abstract:
    The understanding of critical heat flux is crucial for the safety of nuclear reactors. To this end, many studies have been carried out to understand various aspects of the boiling crisis phenomenon. Power transient critical heat flux trigger mechanisms is a small category that is relatively under-studied and not well...
    Resource Type:
    Dissertation
    Full Text:
    PWR fuel rod during a RIA is a perfect example of this complication. 1.1 Motivation One scenario

  • A New Approach of Computational Fluid Dynamics Studying Power Transient Critical Heat Flux

    Creator:
    Chen, Tsung-Wen
    Abstract:
    Power transient boiling has been studied for decades, however, the mechanistic understanding of phenomena which occur during such an event remains incomplete. Due to a dearth of systematic researches, the information of studied phenomenon, detailed physics and applicable hypothesis are very limited. Transient critical heat flux (CHF) is paramount in...
    Resource Type:
    Masters Thesis
    Full Text:
    ....................................................38 Fig. 20. Cross view of test section with different heater rod sets

  • Development of a binary mixture gas composition instrument for use in a confined high temperature environment

    Creator:
    Cadell, Seth R.
    Abstract:
    With recent advancements in material science, industrial operations are being conducted at higher and higher temperatures. This is apparent in the nuclear industry where a division of the field is working to develop the High Temperature Gas Reactor and the Very High Temperature Gas Reactor concurrently. Both of these facilities...
    Resource Type:
    Dissertation
    Full Text:
    ]. ....................................... 22 2-10: Diagram of the most common Cross-Capacitor geometries: Torodial (Left) and Rod (Right) [78