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Filtering by: Committee Member Pearson, G. D. Remove constraint Committee Member: Pearson, G. D. Contributor advisor sim Marcum, Wade R. Remove constraint Contributor advisor sim: Marcum, Wade R.

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  • A thermal hydraulics analysis of a molybdenum production element for implementation in TRIGA reactors

    Creator:
    Byfield, Patrick
    Abstract:
    The metastable isotope of technetium-99 (Tc-99m) is an important diagnostic tool used in the field of nuclear medicine due to the isotope's 6.0 hour half-life, 140.5 keV γ-decay mechanism, and multiple oxidation states [1,2]. Approximately 70% of the world’s nuclear medicine procedures involve the use of Tc-99m [3]. The conventional...
    Resource Type:
    Masters Thesis
    Full Text:
    exp X = −  (2-3) and ( )4 12H g f X D Xk exp exp XL ρ ρ

  • Fuel Dispersal Under LOCA Conditions

    Creator:
    Latimer, Griffen D.
    Abstract:
    Most operating power reactors use oxide fuel in the form of uranium oxide (UO2) which is robust against high temperatures but suffers from poor mechanical performance at high levels of burnup. Currently, the maximum average burnup in light water reactors in the US is 62.5 GWd/t, which is partially imposed...
    Resource Type:
    Dissertation
    Full Text:
    ), unirradiated rod testing (group B), and irradiated rod testing (groups C, D, E, F, and G). For the

  • Multi-Scale, Multi-Physics Reactor Pulse Simulation Method with Macroscopic and Microscopic Feedback Effects

    Creator:
    Zabriskie, Adam X.
    Abstract:
    The Transient Reactor Test facility (TREAT) at Idaho National Laboratory (INL) is a unique reactor capable of stressing test fuel during a power pulse transient. TREAT fuel is composed of high enriched uranium (HEU) heterogeneous fuel; microscopic UO₂ fuel grains with an average radius of 10 μm are randomly distributed...
    Resource Type:
    Dissertation
    Full Text:
    Appendix D MAMMOTH Micro-scale Input Example ........................................... 113 Appendix E