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Showing 1 to 12 of 12 for “"Zircaloy-2"”.

  1. Steam oxidation of FeCrAl coated Zircaloy-2

    … calorimetry (DSC). Bare and FeCrAl coated Zircaloy-2 nuclear fuel cladding and FeCrAl coated single crystal Yttria stabilized Zirconia (YSZ) samples were oxidized in an argon/steam environment at 700 C and 1100 C. FeCrAl coated Zircaloy-2 was also heated to 1200 C in an inert environment. …

    uiuc Repository record for Steam oxidation of FeCrAl coated Zircaloy-2 (opens in a new tab)

  2. An analysis of second phase particles in zircaloy 2

    Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Materials Science and Engineering, 1980.

    mit Repository record for An analysis of second phase particles in zircaloy 2 (opens in a new tab)

  3. Lattice Strain and Texture of Plastically Deformed Zircaloy-2 at 77K

    Zircaloy-2 is used extensively in the nuclear industry as a structural material for the reactor core in both light and heavy water reactors. The intergranular strains and texture greatly affect the mechanical properties of the material while in operation. Understanding the plastic deformation of …

    queens Repository record for Lattice Strain and Texture of Plastically Deformed Zircaloy-2 at 77K (opens in a new tab)

  4. Characterization of Iron-Chromium-Aluminum surface coated Zircaloy-2 under high temperature steam

    … (FeCrAl) thin films have been deposited on Zircaloy-2 (Zry2) and yttria-stabilized zirconia (YSZ) by magnetron sputtering, and they have been tested with respect to the oxidation weight gain in high temperature steam. In 700C steam environment, the FeCrAl-coated Zry2 samples have …

    uiuc Repository record for Characterization of Iron-Chromium-Aluminum surface coated Zircaloy-2 under high temperature steam (opens in a new tab)

  5. High temperature steam oxidation of titanium-coated Zircaloy-2 and Titanium-Zirconium Alloys

    … reaction of high temperature steam and the Zircaloy fuel cladding within the reactor during a Loss-of -Coolant Accident (LOCA). The hydrogen, which collected in the reactor vessel and containment buildings, caused devastating hydrogen gas explosions which lead to the release of radioactive …

    uiuc Repository record for High temperature steam oxidation of titanium-coated Zircaloy-2 and Titanium-Zirconium Alloys (opens in a new tab)

  6. Response of chromium and chromium-aluminum coatings on zircaloy-2 to high temperature steam

    … Our approach is to apply CrAl or Cr coatings on Zircaloy by magnetron sputtering to improve the oxidation resistance of cladding materials. The goal of this research is to characterize the oxidation kinetics and microstructure of CrAl and Cr coatings on Zircaloy-2 in high temperature steam (HTS) …

    uiuc Repository record for Response of chromium and chromium-aluminum coatings on zircaloy-2 to high temperature steam (opens in a new tab)

  7. Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl

    … water reactor design that included Case I: Zircaloy-2 cladding, and Case II: FeCrAl cladding. The results from these two cases were analyzed using a one-way coupling approach with Thermochimica to demonstrate potential areas for the improvement o fMELCOR’s current material modelling …

    uoit Repository record for Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl (opens in a new tab)

  8. Cracking of zirconium alloys at constant load with and without applied potentials

    Cladding materials, namely Zircaloy-2 (Zr-2) and Zircaloy-4 (Zr-4), were tested for evaluation of their resistance to stress corrosion cracking (SCC), delayed hydride cracking (DHC), and localized corrosion (pitting and crevice) in neutral and acidic environments at ambient temperature and 90°C. …

    unlv Repository record for Cracking of zirconium alloys at constant load with and without applied potentials (opens in a new tab)

  9. Evaluation of cracking and localized corrosion behavior of cladding materials

    … (pitting and crevice) susceptibility of zircaloy-2 and zircaloy-4 in neutral and acidic solutions at 30, 60, 90°C. Constant-load and slow-strain-rate (SSR) testing methods were used to evaluate the SCC and HE behavior of both alloys by use of smooth and notched tensile specimens. …

    unlv Repository record for Evaluation of cracking and localized corrosion behavior of cladding materials (opens in a new tab)

  10. Enhanced corrosion of zirconium-based alloys in proximity to other metals : the "shadow effect"

    … high and low beta emitters, inert material and Zircaloy-2 in contact and non-contact at various separation distances. Post-irradiation examination of the cladding pieces showed: * Beta-radiation is not the main mechanism for the shadow effect. * Shadow corrosion is partly dominated by an …

    mit Repository record for Enhanced corrosion of zirconium-based alloys in proximity to other metals : the "shadow effect" (opens in a new tab)

  11. Assessing thermo-mechanical performance of ThO₂ and SiC clad light water reactor fuel rods with a modular simulation tool

    … the accelerated oxidation and hydrogen pickup by Zircaloy-2 have been investigated and incorporated. In developing the ThO2-based RBWR concept, three designs have been proposed based on different goals and applied assumptions. With the exception of hydrogen uptake, none of the predicted parameters …

    mit Repository record for Assessing thermo-mechanical performance of ThO₂ and SiC clad light water reactor fuel rods with a modular simulation tool (opens in a new tab)