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  • Pressurized water reactor (PWR) accident analysis using the EMERALD code

    Creator:
    Youssefnia, Mohammed Hossein
    Abstract:
    A detail study of a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor was conducted in order to estimate the consequences of the accident using the computer simulation code EMERALD. An effort was undertaken to modify the EMERALD code and to make it operable on the OSU CYBER...
    Resource Type:
    Masters Thesis
    Full Text:
    WATER REACTOR (PWR) ACCIDENT ANALYSIS USING THE EMERALD CODE I. INTRODUCTION Nuclear reactors, like

  • 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:
    . Moussaoui for the degree of Doctor of Philosophy in Nuclear Engineering presented on September 21, 2023

  • 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:
    testing and modeling are necessary to qualify new nuclear fuel and reactor designs through their

  • 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:
    Nuclear Regulatory Commission SMR Small Modular Reactor NSSS Nuclear Steam Supply System LOCA Loss of

  • 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

  • Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

    Creator:
    Utberg, John E., Jr
    Abstract:
    The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the MHTGR will perform during a Depressurized Conduction Cooldown (DCC) accident, which generally can be divided into three phases: depressurization, air ingress, and natural circulation. After...
    Resource Type:
    Masters Thesis
    Full Text:
    support codes, the HTTF is a non-nuclear reactor that uses electrical power to analogously represent the

  • Proof of concept of the use of RAVEN and RELAP5-3D for risk informed safety margin characterization

    Creator:
    Riley, Thomas H.
    Abstract:
    This project was a proof of concept of the use of the RAVEN software, a tool developed for the Risk Informed Safety Margin Characterization (RISMC) approach, with RELAP5-3D. This novel approach combines older probabilistic and mechanistic approaches to look at how and why the complex systems of a nuclear power...
    Resource Type:
    Masters Thesis
    Full Text:
    complex systems of a nuclear power plant might fail in an accident scenario in greater detail than 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

  • The missile hazard of surface traffic accidents to nuclear power plants

    Creator:
    Earle, Otis Keener
    Abstract:
    A method is presented for appraising the hazards to nuclear power plants from missiles from surface traffic accident explosions. Due to the infrequency with which surface traffic accident explosions occur and the poor records kept concerning them, a probabilistic method is chosen to investigate the overall hazards potential to nuclear...
    Resource Type:
    Masters Thesis
    Full Text:
    presented for appraising the hazards to nuclear power plants from missiles from surface traffic accident