Nothing Special   »   [go: up one dir, main page]

Sayers et al., 2019 - Google Patents

A high-resolution characterization of the oxide-metal interface in Zircaloy-4 and its relation to the oxidation and hydrogen pickup mechanisms

Sayers et al., 2019

View PDF
Document ID
635564988085919235
Author
Sayers J
Lozano-Perez S
Nicholls R
Ortner S
Publication year
Publication venue
Journal of Nuclear Materials

External Links

Snippet

Oxide growth and hydrogen pickup have been measured for Zircaloy-4 in environments of different pH. The metal-oxide interface has been studied at high-resolution over sufficient lengths to show meaningful trends in the behaviour of the ZrO and oxygen-saturated metal …
Continue reading at ora.ox.ac.uk (PDF) (other versions)

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/40Other aspects relating to nuclear fission
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/022Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G21C17/0225Chemical surface treatment, e.g. corrosion
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E60/00Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation
    • Y02E60/50Fuel cells

Similar Documents

Publication Publication Date Title
Couet et al. Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics
Hu et al. Hydrogen pickup during oxidation in aqueous environments: The role of nano-pores and nano-pipes in zirconium oxide films
Yu et al. Irradiation-induced Nb redistribution of ZrNb alloy: An APT study
Moorehead et al. Comprehensive investigation of the role of Nb on the oxidation kinetics of Zr-Nb alloys
Rudling et al. A unified model of Zircaloy BWR corrosion and hydriding mechanisms
Allen et al. 5.03 corrosion of zirconium alloys
Hu et al. Effect of neutron and ion irradiation on the metal matrix and oxide corrosion layer on Zr-1.0 Nb cladding alloys
Couet et al. Effect of alloying elements on hydrogen pickup in zirconium alloys
Kautz et al. Investigating zirconium alloy corrosion with advanced experimental techniques: A review
Sayers et al. A high-resolution characterization of the oxide-metal interface in Zircaloy-4 and its relation to the oxidation and hydrogen pickup mechanisms
Hu et al. Hydrogen desorption kinetics from zirconium hydride and zirconium metal in vacuum
Jiang et al. High-temperature corrosion of Zr–Nb alloy for nuclear structural materials
Kammenzind et al. Neutron irradiation effects on the corrosion of zircaloy-4 in a pressurized water reactor environment
Couet et al. An integrated modeling and experimental approach to study hydrogen pickup mechanism in zirconium alloys
Wang et al. Emulation of neutron damage with proton irradiation and its effects on microstructure and microchemistry of Zircaloy-4
Liu et al. Characterisation of deuterium distributions in corroded zirconium alloys using high-resolution SIMS imaging
Harlow et al. Determination of the initial oxidation behavior of Zircaloy-4 by in-situ TEM
Yu et al. Irradiation damage reduces alloy corrosion rate via oxide space charge compensation effects
Yu et al. STEM/EDS and APT study on the microstructure and microchemistry of neutron irradiated ZIRLOTM
Rittenhouse et al. Effect of grain refinement on high temperature steam oxidation of an FeCrAl alloy
Lin et al. Effect of Zr2+ irradiation on microstructure and corrosion behavior of 90Nb-10Zr binary alloy in 360° C lithiated water
Urbanic et al. Growth and characterization of oxide films on zirconium-niobium alloys
Ensor et al. Microbeam synchrotron radiation diffraction and fluorescence of oxide layers formed on zirconium alloys at different corrosion temperatures
Yu et al. Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion
Umretiya et al. Evolution of microstructure and surface characteristics of FeCrAl alloys when subjected to flow boiling testing