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  • Multi application small light water reactor containment analysis and design

    Creator:
    Haugh, Brandon Patrick
    Abstract:
    This thesis presents the assessment of the Multi Application Small Light Water Reactor (MASLWR) containment design during steady-state and transient conditions. The MASLWR project is a joint effort between Idaho National Environmental and Engineering Laboratory (INEEL), NEXANT Bechtel, and Oregon State University. The project is funded under a Nuclear Energy...
    Resource Type:
    Masters Thesis
    Full Text:
    Small Light Water Reactor Containment Analysis and Design Abstract Approva __ ( / Jose I. Reyes, Jr

  • High Pressure Condensation in an SMR Containment

    Creator:
    Mullin, Etienne M.
    Abstract:
    The Oregon State University Multi-Application Small Light Water Reactor test facility is employed in a series tests to evaluate condensation heat transfer in small, high pressure containment vessels characteristic of small modular reactor designs under development. This integral system test facility was constructed to demonstrate the feasibility of a pioneering...
    Resource Type:
    Masters Thesis
    Full Text:
    containment vessels characteristic of small modular reactor designs under development. This integral system

  • Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

    Creator:
    Lee, Dongyoung
    Abstract:
    There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and Tsunami with the height of 15 m on March 11, 2011. Small Modular Reactors (SMRs) have been developed to improve safety systems by utilizing passive...
    Resource Type:
    Dissertation
    Full Text:
    Small Light Water Reactor NRC Nuclear Regulatory Commission ODE Ordinary Differential Equation OSU

  • High pressure condensation heat transfer in the evacuated containment of a small modular reactor

    Creator:
    Casey, Jason R.
    Abstract:
    At Oregon State University the Multi-Application Small Light Water Reactor (MASLWR) integral effects testing facility is being prepared for safety analysis matrix testing in support of the NuScale Power Inc. (NSP) design certification progress. The facility will be used to simulate design basis accident performance of the reactor's safety systems....
    Resource Type:
    Masters Thesis
    Full Text:
    .                                                                                                                                                                                                                                                                                                                                     2 The primary containment structure of a modern nuclear reactor serves not only as a barrier

  • Flat Plate Free Convective Heat Transfer

    Creator:
    Bristol, Benjanmin R.
    Abstract:
    The OSU MASLWR Test facility is a scaled integral systems LOCA and proof-of-concept test facility for the Multi-Application Small Light Water Reactor design concept. A unique feature of this design is to utilize a small high pressure containment vessel to provide the safety containment function for an integral reactor pressure...
    Resource Type:
    Masters Thesis
    Full Text:
    Reactor design concept. A unique feature of this design is to utilize a small high pressure containment

  • 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:
    Reactor (MASLWR) facility at Oregon State University (OSU) which was funded by the Nuclear Energy

  • Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

    Creator:
    Lenhof, Renae
    Abstract:
    A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the...
    Resource Type:
    Masters Thesis
    Full Text:
    Utilized in a Generation IV Gas-Cooled Fast Reactor Nuclear Power Plant AN ABSTRACT OF THE

  • One and two dimensional space-energy flux synthesis with spatially discontinuous trial functions

    Creator:
    Olson, Willard Orvin
    Abstract:
    The development of nuclear reactors as an energy source requires a substantial investment in capital and effort. This development depends heavily on accurate calculational methods. Space-energy flux synthesis, also variously called the spectral synthesis method, modal method, and overlapping group method, is one possible method. In this method the energy...
    Resource Type:
    Dissertation
    Full Text:
    DOCTOR OF PHILOSOPHY (NaMe of'Student) (Degree) in Nuclear Engineering presented on (Major Department

  • Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles

    Creator:
    Park, Jin Yong
    Abstract:
    This thesis consists of two parts. Part I (Chapters 1, 2, 3) of this thesis concerns finding the best way of running a reactor whose catalyst decays with use, and must consequently be replaced or regenerated at regular intervals. Chapter 1 introduces the problem, and Chapter 2 develops a one...
    Resource Type:
    Dissertation

  • Development of an object-oriented expert system for PWR core reload

    Creator:
    Greek, Kevin J.
    Abstract:
    Reactor refueling is a computationally intensive problem solving process that requires automation since significant resources are expended upon the search for an optimal core loading. Without imposing some constraints upon the configurations investigated, an extremely large number of prototype loadings may be generated without discovery of an improved loading. As...
    Resource Type:
    Dissertation
    Full Text:
    Nuclear Engineering presented on December 12, 1989. Title: Development of an Object-Oriented Expert