Search Results - "Kamerman, David W."

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  1. 1

    The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads by Kamerman, David W.

    Published in Engineering failure analysis (16-08-2023)
    “…This study is motivated by the desire to conduct a separate effects test replicating specific aspects of an in-pile pulse reactor test on high exposure light…”
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    Journal Article
  2. 2

    Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding by Nelson, Malachi, Samuha, Shmuel, Kamerman, David, Hosemann, Peter

    Published in Journal of nuclear materials (01-07-2024)
    “…This work evaluates deformation activity in textured zircaloy-4 cladding with the aim of elucidating the mechanisms that govern mechanical behavior across a…”
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    Journal Article
  3. 3

    Enhanced stress relaxation behavior via basal $\langle a \rangle$ dislocation activity in Zircaloy-4 cladding by Nelson, Malachi Michael, Samuha, Shmuel, Kombaiah, Boopathy, Kamerman, David W., Hosemann, Peter

    Published in Journal of nuclear materials (08-08-2024)
    “…Herein this work evaluates the stress relaxation behavior of textured Zircaloy-4 cladding to understand how mechanical anisotropy influences pellet-cladding…”
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    Journal Article
  4. 4

    Evaluation of the ring tension test (RTT) for robust determination of material strengths by Hansen, Robert S., Kamerman, David W., Petersen, Philip G., Cappia, Fabiola

    “…[Display omitted] •Two ring tension test configurations are compared using finite element analysis.•‘Dogbone’ tests underpredict strengths due to premature…”
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    Journal Article
  5. 5

    Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding by Nelson, Malachi Michael, Kamerman, David W

    Published 07-03-2024
    “…This work evaluates deformation activity in textured zircaloy-4 cladding with the aim of elucidating the mechanisms that govern mechanical behavior across a…”
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    Conference Proceeding
  6. 6

    Evaluation of the ring tension test (RTT) for robust determination of material strengths by Hansen, Robert S., Kamerman, David W., Petersen, Philip G., Cappia, Fabiola

    “…The ring tension test (RTT) is an experimental method for determining mechanical behavior in a material’s circumferential or hoop direction. It is a crucial…”
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    Journal Article
  7. 7

    Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes by Kamerman, David W., Bachhav, Mukesh, Yao, Tiankai, Pu, Xiaofei, Burns, Jatuporn

    Published in Journal of nuclear materials (06-08-2023)
    “…Zirconium alloy tubes used as nuclear fuel cladding are subject to oxidation and subsequent hydrogen pickup during their long service in commercial light water…”
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    Journal Article
  8. 8

    On the Role of Zirconium Hydrides and Hydride Rim Features in Causing Low Strain Ruptures in Stress Relieved Zirconium Alloy Cladding Tubes in Pulse Reactor Tests by Kamerman, David W

    Published 01-01-2023
    “…Stress relieved zirconium alloys are the most widely used material to construct light water reactor fuel cladding tubes. Circumferential zirconium hydride…”
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    Dissertation
  9. 9

    Resumption of water capsule reactivity-initiated accident testing at TREAT by Folsom, Charles P., Schulthess, Jason L., Kamerman, David W., Hansen, Robert S., Woolstenhulme, Nicolas E., Jensen, Colby B., Astle, Leigh A., Ocampo Giraldo, Luis, Fleming, Austin, Wachs, Daniel M.

    Published in Nuclear engineering and design (01-11-2023)
    “…•Water-based reactivity initiated accident testing of light water reactor fuel rods in the Transient REActor Test facility.•In-pile experiments along with…”
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    Journal Article
  10. 10

    Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT by Woolstenhulme, Nicolas E., Fleming, Austin D., Kamerman, David W., Jensen, Colby B., Wachs, Daniel M., Holschuh, Tommy V.

    Published in Annals of nuclear energy (17-10-2019)
    “…For this study, a series of experiments was conducted in the Transient Reactor Test (TREAT) Facility following a decades-long operational hiatus. A series of…”
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    Journal Article