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  • 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

  • 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

  • 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

  • Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown

    Creator:
    Colpo, Sarah E.
    Abstract:
    Counter Current Flow Limitation (CCFL) was observed in the pressurizer surge line of the Oregon State University APEX facility during test NRC-10. This test simulated a one-inch diameter cold leg break with a failure of three of four of the fourth-stage Automatic Depressurization System (ADS) valves. The result was a...
    Resource Type:
    Masters Thesis
    Full Text:
    Counter Current Flow Limitation (CCFL) in the primary system of a Pressurized Water Reactor (PWR) has

  • 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