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  • Experimental investigation of condensation phenomena inside a U-tube steam generator

    Creator:
    Collins, Brian A.
    Abstract:
    Reflux condensation tests examining steam condensation in a PWR steam generator (SG) were conducted at the Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility from 2005 through 2007. The experimental data collected will provide a basis to assess TRACE steam generator modeling techniques and assist in development of...
    Resource Type:
    Masters Thesis

  • Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

    Creator:
    Mai, Anh T.
    Abstract:
    The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity....
    Resource Type:
    Masters Thesis
    Full Text:
    -Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water

  • Out-of-pile blowdown critical heat flux experiment

    Creator:
    Moussaoui, Musa A.
    Abstract:
    In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is not yet determined whether the use of steady-state CHF methods can accurately predict transient CHF under the conditions of a blowdown due...
    Resource Type:
    Dissertation
    Full Text:
    reached pressurized water reactor thermal-hydraulic conditions. CHF was repeatedly measured with

  • Blowdown transient critical heat flux

    Creator:
    Moussaoui, Musa A.
    Abstract:
    Occurring in the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is the primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is unclear whether the use of steady-state CHF correlations can accurately predict the gross thermal-hydraulic perturbations of a blowdown in a large...
    Resource Type:
    Masters Thesis
    Full Text:
    prototypic pressurized water reactor (PWR) conditions. Further, LOCA induced transient CHF is not well

  • Pressure losses across a 180 degree turn in the AP1000 cooling annulus

    Creator:
    Nelson, Roy K.
    Abstract:
    A one-sixth scaled facility was constructed at Oregon State University to determine the pressure losses around Westinghouse's AP1000 Passive Containment Cooling System. An explanation of the AP1000 Passive Containment Cooling System is given. This study examined the pressure loss and loss coefficient around the 180 degree turn of the Passive...
    Resource Type:
    Masters Thesis
    Full Text:
    pressurized water reactor (AP1000) under nominal conditions. Regulators and Designers need to ask how well

  • An analysis of core uncovery in the APEX test facility

    Creator:
    Rusher, Christopher deCastrique
    Abstract:
    The Department of Nuclear Engineering at Oregon State University has performed a series of confirmatory tests for the United States Nuclear Regulatory Commission (USNRC). These tests have been conducted in the Advanced Plant Experiment (APEX) Facility which is a one quarter height scaled simulation of the Westinghouse Advanced Passive 600...
    Resource Type:
    Masters Thesis
    Full Text:
    600 megawatt electric (AP600) pressurized water reactor. The purpose of the testing program is to

  • A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility

    Creator:
    Wachs, Daniel M.
    Abstract:
    The phenomena of interest in this work is the thermal stratification which occurs during the early stages of a loss of coolant accident (LOCA) in the OSU APEX Thermal Hydraulic Test Facility, which is a scaled model of the Westinghouse AP600 nuclear power plant. Thermal stratification has been linked to...
    Resource Type:
    Masters Thesis
    Full Text:
    actuated and this isolation is broken. The high density cold water falls into the reactor. As the CMT

  • RELAP5-3D modeling of ADS blowdown of MASLWR facility

    Creator:
    Bowser, Christopher Jordan
    Abstract:
    Oregon State University has hosted an International Atomic Energy Agency (IAEA) International Collaborative Standard Problem (ICSP) through testing conducted on the Multi-Application Small Light Water (MASLWR) facility. The MASLWR facility features a full-time natural circulation loop in the primary vessel and a unique pressure suppression device for accident scenarios. Automatic...
    Resource Type:
    Masters Thesis
    Full Text:
    Electric-Hitachi’s Economic Simple Boiling Water Reactor when the Fukushima accident happened, (ANS, April

  • 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:
    boiling phenomenon under the Pressurized Water Reactor (PWR) condition. Since the direct application of

  • Study on Depressurized Loss of Coolant Accident and its Mitigation Method Framework at Very High Temperature Gas Cooled Reactor

    Creator:
    Gutowska, Izabela
    Abstract:
    To understand how a Depressurized Loss of Forced Convection (D-LOFC) initiated from a double-ended guillotine break may affect further operation of a High Temperature Gas Cooled Rector (HTGR), thorough understanding of each specific stage of this event is required. Key considerations that need to be determined is the amount of...
    Resource Type:
    Dissertation
    Full Text:
    University PBMR Pebble Bed Modular Reactor P-LOFC Pressurized Loss of Forced Convection PCC