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

Le Saux et al., 2020 - Google Patents

Breakaway oxidation of zirconium alloys exposed to steam around 1000 C

Le Saux et al., 2020

View PDF
Document ID
4640463776138910824
Author
Le Saux M
Brachet J
Vandenberghe V
Ambard A
Chosson R
Publication year
Publication venue
Corrosion Science

External Links

Snippet

The breakaway oxidation of Zircaloy-4 and M5 Framatome alloys oxidized in flowing steam around 1000° C was studied. The influences of oxidation temperature between 950 and 1050° C, one-side versus two-side oxidation and chemical variations around the nominal …
Continue reading at www.sciencedirect.com (PDF) (other versions)

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2004/00—SOLUTION
    • G21Y2004/10—Compositions
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2002/00—PROBLEM
    • G21Y2002/104—Inadequate performance, deformation, cracks, rupture
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2004/00—SOLUTION
    • G21Y2004/40—Improving a procedure

Similar Documents

Publication Publication Date Title
Le Saux et al. Breakaway oxidation of zirconium alloys exposed to steam around 1000 C
Duriez et al. Zircaloy-4 and M5® high temperature oxidation and nitriding in air
Steinbrück et al. Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600–1200 C
Geelhood et al. PNNL stress/strain correlation for Zircaloy
Ensor et al. The role of hydrogen in zirconium alloy corrosion
Le Saux et al. Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 and M5Framatome alloys
Kammenzind et al. Neutron irradiation effects on the corrosion of zircaloy-4 in a pressurized water reactor environment
Chabretou et al. Ultra Low Tin Quaternary Alloys PWR Performance--Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties
Guilbert-Banti et al. Effect of pre-oxide on Zircaloy-4 high temperature steam oxidation
Schroer et al. Corrosion in iron and Steel T91 caused by flowing lead–bismuth eutectic at 400 C and 10− 7 mass% dissolved oxygen
Zino et al. Breakaway characterization of Zircaloy-4 oxidized in steam and in oxygen at high temperatures using HT-XRD analysis
Billone et al. Ductile-to-Brittle Transition Temperature for High Burnup Zircaloy-4 and ZIRLO (TM) Cladding Alloys Exposed to Simulated Drying Storage Conditions.
Duriez et al. Zircaloy-4 high temperature oxidation in atmospheres representative of SFP-LOCA: Investigation of the influence of a low temperature pre-oxidation scale
Chosson et al. Creep flow and fracture behavior of the oxygen-enriched alpha phase in zirconium alloys
Guilbert et al. Effect of pre-oxide on Zircaloy-4 high temperature steam oxidation and post-quench mechanical properties
Yan et al. High-temperature oxidation kinetics of sponge-based E110 cladding alloy
Duriez et al. Characterization of oxygen distribution in LOCA situations
Lin et al. Microstructural understanding of general and localized corrosion of Fe13Cr4Al2Mo1. 2Nb alloy in high temperature aerated water and superheated steam
Liu et al. Self-toughening mechanism of the ZrO2 scale and the precipitation of Sn during the steam oxidation of ZIRLO™ at 1200° C
Le Hong et al. Combined effects of temperature and of high hydrogen and oxygen contents on the mechanical behavior of a zirconium alloy upon cooling from the βZr phase temperature range
Huang et al. Effects of thermomechanical processing on in-reactor corrosion and post-irradiation mechanical properties of Zircaloy-2
Samanta et al. Susceptibility of Zr-2.5 (wt.%) Nb alloy to undergo nodular corrosion in water and steam environments: Effect of surface, cold work, temperature
Sagat et al. Deformation and failure of zircaloy fuel sheaths under LOCA conditions
Guilbert-Banti et al. Hafnium oxidation at high temperature in steam
Turque et al. Mechanical behavior at high temperature of highly oxygen-or hydrogen-enriched α and (prior-) $\beta $ phases of zirconium alloys