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Filtering by: Creator Santiago, José L. Remove constraint Creator: Santiago, José L. Advisor Reyes, Jose N. jr Remove constraint Advisor: Reyes, Jose N. jr

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  • The study of cold leg thermal stratification in APEX-CE

    Creator:
    Antoine, Stephanie Y. L. Antoine
    Abstract:
    This research presents an analysis of thermal stratification in the reactor cold leg of the Advanced Plant Experiment-Combustion Engineering (APEX-CE). This phenomenon may be a precursor leading to a Pressurized Thermal Shock (PTS) event in a nuclear power plant. This work was performed in support of the U.S. Nuclear Regulatory...
    Resource Type:
    Masters Thesis
    Full Text:
    defined as: -7.5 FrHP,CL (+ QL (2.12) QHPI) QHP! /ACL FrHPI CL = (2.13) ___1y L Where ACL is the flow

  • A general theory of flooding implementing the cuspoid catastrophe

    Creator:
    Lafi, Abd Y.
    Abstract:
    The flooding phenomenon can be defined as the maximum attainable flow condition beyond which the well defined countercurrent flow pattern can no longer exist. Thus the countercurrent flow limit (CCFL) or the flooding limit may be thought of as the flow condition at which the strong interaction between the two...
    Resource Type:
    Dissertation
    Full Text:
    Catastrophe. Abstract Approved: Redacted for Privacy Tr- J Jose N. Reyes, Jr. The flooding phenomenon can

  • SBLOCA analysis for nuclear plant shutdown operations

    Creator:
    Wang, Yi
    Abstract:
    A series of small break loss of coolant accident (SBLOCA) analyses in nuclear plant shutdown operations was simulated using the code RELAP5A,MOD3 version 8.0 to predict the SBLOCA phenomena in the Zion-l nuclear power plant The first objective is to study the impact of SBLOCA (1" and 2" breaks) on...
    Resource Type:
    Masters Thesis
    Full Text:
    Approved: Dr. Jose N. Re s, Jr. A series of small break loss of coolant accident (SBLOCA) analyses in

  • Assessment of level swell measurements in the OSU APEX Test Facility

    Creator:
    Ellis, Christopher P.
    Abstract:
    The purposes of this paper are to present the results of an experimental effort to measure the level swell in an air/water system and to generate a methodology for determining the volume-averaged void fraction within the Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility. The results were then...
    Resource Type:
    Masters Thesis
    Full Text:
    OSU APEX Test Facility. Abstract approve Jose N. Re~ Jr. ' The purposes of this paper are to

  • Axial development of two-phase flow parameters in a vertical column

    Creator:
    Abel, Kent C.
    Abstract:
    The next generation of nuclear safety analysis computer codes will include detailed modeling of the interfacial area concentration. The interfacial area concentration is the essence of the two-fluid model. It is the most accurate of the two-phase models since it considers each phase independently and links the two phases together...
    Resource Type:
    Masters Thesis
    Full Text:
    for Privacy W4Ii'p Ii:i I would like to take this opportunity to thank Dr. José N. Reyes, Jr. for

  • A study of return to saturation oscillations in the OSU APEX thermal hydraulic testing facility

    Creator:
    Franz, Scott C.
    Abstract:
    The purpose of this paper is to describe the flow oscillations which occur in the AP600 long term cooling test facility at Oregon State University. The AP600 system is an advanced pressurized water reactor design utilizing passive emergency cooling systems. A few hours after the initiation of a cold leg...
    Resource Type:
    Dissertation
    Full Text:
    Saturation Oscillations in the OSU APEX Thermal Hydraulic Testing Facility. Abstract approved: Jose N

  • 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:
    who made this thesis possible. First, I would like to thank Dr. Jose Reyes for the opportunity to be

  • 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:
    ACKNOWLEDGMENT I have had the honor and privilege to be a student of Dr. Jose N. Reyes, Jr. Through Dr

  • Study of interfacial condensation in a nuclear reactor core makeup tank

    Creator:
    Ma, Chang Chun
    Abstract:
    Steam interfacial condensation in a core makeup tank was simulated using the code RELAP5/MOD3 version 8.0 to predict the violent pressure oscillation phenomena in a core makeup tank. Six base cases were carried out to study the effects of back pressure and of vacuum conditions produced in the core makeup...
    Resource Type:
    Masters Thesis
    Full Text:
    Reactor Core Makeup Tank Abstract Approved:_Redacted for Privacy JR., Jose N. Reyes Steam interfacial

  • Characterization of the Advanced Plant Experiment (APEX) passive residual heat removal system heat exchanger

    Creator:
    Stevens, Owen L.
    Abstract:
    The Oregon State University (OSU) Radiation Center (RC) is the location of a one quarter scale model of the Westinghouse Electric Corporation advanced light-water nuclear reactor design called the AP-600. The full scale AP-600 is a 600 megawatt electric nuclear power plant that incorporates unique passive systems to perform the...
    Resource Type:
    Masters Thesis
    Full Text:
    ) passive residual heat removal system heat exchanger AN ABSTRACT OF THE THESIS OF Owen L. Stevens for