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    A comparison of thermal hydraulic models for pressurized water reactors

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    Author
    Stanley, Thomas Patrick, 1963-
    Issue Date
    1993
    Keywords
    Engineering, Nuclear.
    Advisor
    Seale, Robert L.
    
    Metadata
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    Publisher
    The University of Arizona.
    Rights
    Copyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.
    Abstract
    This thesis compares a new dynamic moving boundary thermal hydraulics fuel pin model (FUELPIN) to a known thermal hydraulics code (COBRA) for the following relationships: (1) Minimum Departure from Nucleate Boiling Ratio (MDNBR) versus time for transient conditions in a Pressurized Water Reactor (PWR) channel, and (2) Position of Minimum DNBR versus time for transient conditions. Relationships between MDNBR and position of MDNBR versus time were analyzed by comparing: (1) output of COBRA, a steady state thermal hydraulics model, with inputs from a PWR simulation code (CEPAC-L), (2) output of CEPAC-L linked FUELPIN. CEPAC-L computer model was shown to be a good simulation of a PWR during steady state conditions and a loss of all primary coolant flow casualty by comparison with an accepted PWR simulation code (CEPAC). FUELPIN was shown to predict larger thermal margins than COBRA for loss of all primary coolant flow transients in PWRs.
    Type
    text
    Thesis-Reproduction (electronic)
    Degree Name
    M.S.
    Degree Level
    masters
    Degree Program
    Graduate College
    Degree Grantor
    University of Arizona
    Collections
    Master's Theses

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