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Filtering by: Subject Nuclear fuels Remove constraint Subject: Nuclear fuels Degree Name Doctor of Philosophy (Ph.D.) Remove constraint Degree Name: Doctor of Philosophy (Ph.D.)

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  • Optimization of in-core nuclear fuel management in a pressurized water reactor

    Creator:
    Stout, Richard Bartholomew
    Abstract:
    Fuel loading patterns which have a minimum power peak are economically desirable to allow power reactors to operate at the highest possible power density and to minimize the possibility of fuel failure. A computer code called SHUFLE was developed for pressurized water reactors which shuffles the fuel in search of...
    Resource Type:
    Dissertation
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    : OPTIMIZATION OF IN-CORE NUCLEAR FUEL MANAGE- MENT IN A PRESSURIZED WATER REACTOR Redacted for privacy

  • An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel

    Creator:
    Wen, Xianfei
    Abstract:
    High-energy delayed γ-rays from photofission were demonstrated to be signatures for detection and identification of special nuclear materials. Such γ-rays were measured in between linac pulses using independent data acquisition systems. A list-mode system was developed to measure low-energy delayed γ-rays after irradiation. Photofission product yields of ²³⁸U and ²³⁹Pu...
    Resource Type:
    Dissertation
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    address the high-rate challenge in used nuclear fuel assay based on photofission technique. First, a

  • Numerical solutions of the neutron transport equation

    Creator:
    Skeen, David Roy
    Abstract:
    Because of the high cost of fuel for nuclear reactors, fuel cycle costs must be predicted accurately. This leads to the high cost computer computations and a search for cheaper yet still accurate methods. For this paper we have chosen to study an alternate method for calculating thermal neutron cell...
    Resource Type:
    Dissertation
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    . Robinson) Because of the high cost of fuel for nuclear reactors, fuel cycle costs must be predicted

  • A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication

    Creator:
    Azarfar, Mohammad Ali
    Abstract:
    This study focuses on the development of a methodology to evaluate safeguardability of various processes in the nuclear fuel cycle. National and international implementation of safeguards systems has been investigated. It was concluded that proliferation is purely a political question that, hopefully, can be prevented by international norms and diplomacy;...
    Resource Type:
    Dissertation
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    safeguardability of various processes in the nuclear fuel cycle. National and international implementation of

  • Modeling of the thermal behavior of irradiated sphere-pac mixed carbide fuel

    Creator:
    Ades, Maurice
    Abstract:
    Several fuels are being investigated for fast breeder reactor applications. One promising concept is sphere-pac mixed carbide fuel. As a part of the development of this fuel concept it is necessary to determine the behavior of the irradiated fuel for safe and reliable operation on a sound economic basis. It...
    Resource Type:
    Dissertation
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    mixed carbide fuel AN ABSTRACT OF THE THESIS OF Maurice Ades for the degree of Doctor of Philosophy

  • A two-group study on the gadolinium particle depletion in light water reactor fuel rods

    Creator:
    Lee, Chungchan
    Abstract:
    The effect of gadolinia particles on the assembly criticality of a light water reactor was investigated using two 2-group models. The particle effect was calculated by comparing the criticalities of two fuel assemblies, each containing one gadolinia-poisoned rod. For purposes of comparison, both rods contained an equal quantity of gadolinia,...
    Resource Type:
    Dissertation
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    also like to express my thanks to Dr. C. W. Lindenmeier and the Advanced Nuclear Fuel Corporation for

  • A model for the mechanical behavior of irradiated mixed carbide sphere pac fuel pins

    Creator:
    George, Thomas L.
    Abstract:
    A model is developed that allows the prediction of the stress-strain distribution in a mixed carbide sphere pac fuel pin during irradiation. The model is coupled with a previously developed model for the thermal behavior of the pin. The one-dimensional (radial at various axial locations) solution is for quasi-steady pin...
    Resource Type:
    Dissertation
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    carbide sphere pac fuel pins AN ABSTRACT OF THE THESIS OF Thomas L. George for the degree of Doctor of

  • A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors

    Creator:
    Almarshad, Abdullah I. A.
    Abstract:
    A model has been developed to predict the long-term oxidation rate of Zircaloy-4 for ex-reactor (autoclave) and in-reactor (PWR) environments and operating conditions. A computer program has been written to solve the oxygen diffusion equation by employing a fully implicit finite difference method for a one dimensional cylindrical geometry. The...
    Resource Type:
    Dissertation
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    fuel rod discharge burnups, obtain higher coolant inlet tempera- tures to increase the nuclear plant

  • Design and analysis of a nuclear reactor core for innovative small light water reactors

    Creator:
    Soldatov, Alexey I.
    Abstract:
    In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design...
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    Dissertation
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    MASLWR and PWR fuel burnup ………………………………………………….. 79 4-1.3.2. Uranium 235 depletion nuclear

  • Extension of fuel burnup in light water reactors by using a strict in-out refueling scheme

    Creator:
    Yen, Julian Yu-liang
    Abstract:
    To utilize energy resources as efficiently as possible has become a necessity today. The purpose of this study is to see how this can be done by extending burnup in a light water reactor. Specifically, an in-out refueling scheme might extract the maximum energy from nuclear fuel during its redidence...
    Resource Type:
    Dissertation
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    from nuclear fuel during its redidence in the reactor. In principle, a reactor loading with minimum