Investigation of variables that influence corrosion of zirconium alloys during irradiation
Author : V. F. Urbanic
Publisher :
Page : 0 pages
File Size : 10,54 MB
Release : 1992
Category :
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Author : V. F. Urbanic
Publisher :
Page : 0 pages
File Size : 10,54 MB
Release : 1992
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Author : Craig M. Eucken
Publisher : ASTM International
Page : 794 pages
File Size : 45,75 MB
Release : 1991
Category : Nuclear fuel claddings
ISBN : 080311463X
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Author : Marc Tupin
Publisher :
Page : 41 pages
File Size : 21,21 MB
Release : 2014
Category : Corrosion
ISBN :
The irradiation damage in the fuel cladding material is mainly caused by the neutron flux resulting from the fission reactions occurring in the fuel. From an experimental point of view, the neutrons have the disadvantage to activate materials by neutron capture rendering them difficult to handle. To avoid these constraints inherent in the handling of radioactive material, the radiation effects on the corrosion resistance of zirconium alloys can be studied by irradiating the materials with ions. A new experimental approach using ion irradiation was performed in the Microscopy and Irradiation Damage Studies Laboratory of the CEA in Saclay, with the aim to study more specifically the influence of the irradiation damages in the oxide on the corrosion rate of the zirconium alloys. This study was, moreover, focused on a particular distribution of defects in the oxide layer, basically, localised close to the metal/oxide interface. From the results of the irradiation of the metal/oxide interface, it was clearly shown that, whatever the incident ion, the irradiation of the internal interface results in a significant increase of the oxygen diffusion flux ratios between the most irradiated Zircaloy-4 and the unirradiated one, whereas that of the oxide formed on M5TM induces a big decrease of the oxygen diffusion flux in the film. These effects are less marked with helium ions compared to protons (M5TM is a trademark of AREVA NP registered in the United States and in other countries). Finally, the oxide irradiation impact on the oxygen diffusion through the layer could explain the corrosion acceleration factor observed on Zy4 during the first cycles of irradiation, but cannot alone explain observed corrosion accelerations under high burn-up conditions. The discussion on the oxide irradiation effects puts forward the probable role of the residual charge left by ion implantation.
Author : George P. Sabol
Publisher : ASTM International
Page : 953 pages
File Size : 12,53 MB
Release : 2000
Category : Microstructure
ISBN : 0803124996
Author : Gerry D. Moan
Publisher : ASTM International
Page : 891 pages
File Size : 15,1 MB
Release : 2002
Category : Nuclear fuel claddings
ISBN : 0803128959
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Author : VF. Urbanic
Publisher :
Page : 27 pages
File Size : 11,99 MB
Release : 2002
Category : Corrosion
ISBN :
Current CANDU2 reactors use Zr-2.5Nb pressure tubes that are extruded at 1088 K, cold-drawn 27%, and autoclaved at 673 K for 24 h. This results in a metastable, two-phase microstructure consisting of elongated ?-Zr grains surrounded by a network of ?-Zr filaments. To develop a mathematical model of corrosion and deuterium ingress in pressure tubes, we have considered the impact of variables including: fast neutron flux, temperature, and the asfabricated microstructure and its evolution during irradiation.
Author : VF. Urbanic
Publisher :
Page : 17 pages
File Size : 34,43 MB
Release : 2000
Category : Corrosion
ISBN :
The in-reactor corrosion and hydrogen pickup of Zircaloy-2 and Zr-2.5Nb pressure tube materials are being studied in two test loops: a light water loop in the NRU research reactor, and a new heavy water loop in the Halden reactor. The complimentary test programs examine the corrosion behavior of small specimens as a function of fast neutron flux and fluence, temperature, water chemistry, and specimen pre-oxidation.
Author : A. M. Garde
Publisher : ASTM International
Page : 805 pages
File Size : 42,82 MB
Release : 1994
Category : Nuclear fuel claddings
ISBN : 0803120117
Author :
Publisher :
Page : 654 pages
File Size : 36,9 MB
Release : 1993
Category : Power resources
ISBN :
Author :
Publisher :
Page : 644 pages
File Size : 45,22 MB
Release : 1991
Category : Nuclear energy
ISBN :
Includes English language abstracts from Japanese articles in Nihon Genshiryoku Gakkai Shi (Journal of the Atomic Energy Society of Japan)