In Situ HVEM Studies of Phase Transformation in Zr Alloys and Compounds Under Irradiation

In Situ HVEM Studies of Phase Transformation in Zr Alloys and Compounds Under Irradiation PDF Author:
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Languages : en
Pages :

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In Situ HVEM Studies of Phase Transformation in Zr Alloys and Compounds Under Irradiation

In Situ HVEM Studies of Phase Transformation in Zr Alloys and Compounds Under Irradiation PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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In Situ Studies of Phase Transformations in Zirconium Alloys and Compounds Under Irradiation

In Situ Studies of Phase Transformations in Zirconium Alloys and Compounds Under Irradiation PDF Author: JA. Faldowski
Publisher:
ISBN:
Category : Amorphization
Languages : en
Pages : 23

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The High Voltage Electron Microscope (HVEM)/Tandem facility at Argonne National Laboratory has been used to conduct detailed studies of the phase stability and microstructural evolution in zirconium alloys and compounds under ion and electron irradiation. Detailed kinetic studies of the crystalline-to-amorphous transformation of the intermetallic compounds Zr3(Fe1-x,Nix), Zr(Fe1-x,Crx)2, Zr3Fe, and Zr1.5Nb1.5Fe, both as second phase precipitates and in bulk form, have been performed using the in situ capabilities of the Argonne facility under a variety of irradiation conditions (temperature, dose rate). Results include a verification of a dose rate effect on amorphization and the influence of material variables (stoichiometry x, presence of stacking faults, crystal structure) on the critical temperature and on the critical dose for amorphization.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907

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Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 930

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Phase Transformation Studies of Zr Alloys Using DTA

Phase Transformation Studies of Zr Alloys Using DTA PDF Author: Yuntian Zhu
Publisher:
ISBN:
Category : Phase transformations (Statistical physics)
Languages : en
Pages : 160

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Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys

Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys PDF Author: C. Lemaignan
Publisher:
ISBN:
Category : Corrosion
Languages : en
Pages : 10

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The phenomena involved in the corrosion enhancement of Zr alloys under irradiation are analyzed. Among the basic mechanisms concerned, some are related to changes in microstructure of the alloy due to irradiation (precipitate evolution under irradiation and amorphous transformation), others to the transformation of the oxide layer (ZrO2) induced by neutron damage (irradiation-induced phase transformation of the zirconia). The effect of water chemistry and of the ionizing ? photons on the insulating zirconia will also be discussed.

Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys

Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys PDF Author: Clment Lemaignan
Publisher:
ISBN: 9780803184213
Category : Corrosion
Languages : en
Pages : 12

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The phenomena involved in the corrosion enhancement of Zr alloys under irradiation are analyzed. Among the basic mechanisms concerned, some are related to changes in microstructure of the alloy due to irradiation (precipitate evolution under irradiation and amorphous transformation), others to the transformation of the oxide layer (ZrO2) induced by neutron damage (irradiation-induced phase transformation of the zirconia). The effect of water chemistry and of the ionizing ? photons on the insulating zirconia will also be discussed. The original paper was published by ASTM International in STP 1423, Zirconium in the Nuclear Industry: Thirteenth International Symposium, 2002, pp. 2029.

Influence of Structure--Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth

Influence of Structure--Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth PDF Author: VN. Shishov
Publisher:
ISBN:
Category : Dislocation
Languages : en
Pages : 20

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On account of the search for the optimal composition and structure-phase state of Zr alloys much attention is paid to upgrade the E110 (Zr-1 %Nb) and E635 (Zr-1 %Nb-0.35 %Fe-1.2 %Sn) alloys that have proved well in terms of irradiation-induced creep and growth, high strength characteristics, and corrosion. The difference between the alloy properties is determined by their states related to their compositions. The structure-phase state of the Zr-Nb and Zr-Nb-Fe-Sn systems has been studied after heat treatment in the ?-- and ? + ?- regions and its influence on the irradiation-induced growth (IIG) during BOR-60 irradiation at T =315-350 %C was investigated. A substantial difference has been shown in the deformation effected by IIG of those alloys; it is less for Zr-Nb-Fe-Sn alloys in dissimilar structure-phase states. The incubation period of the accelerated growth stage is determined by the ?-matrix composition, the phase state and the initial dislocation structure. Neutron irradiation leads to a redistribution of alloying elements between the matrix and the precipitates, and to changes in the ?-solid solution composition. These changes affect accumulation and mobility of irradiation defects, anisotropy and formation of vacancy c-component dislocation loops. The appearance of c-loops usually correlates with an axial direction acceleration of the IIG of tubes conforming to their texture. The basic regularities of the phase transformation have been established: a) ?-Nb precipitates in Zr-Nb alloys are altered in composition to reduce the Nb content from 85-90 % to ~ 50 %, fine precipitates likely enriched in Nb are formed; b) ?-Zr precipitates are subject to irradiation-stimulated decomposition; c) Laves phase precipitates change composition (the content of Fe decreases) and crystal structure, HCP to BCC (?-Nb); d) (Zr,Nb)2Fe precipitates having the FCC lattice retain their composition and crystal structure; e) no amorphization of any secondary phase precipitates is observable under the given conditions of irradiation (T = 315-350 °C). Based on the dpa, the results were compared pertaining to Zr-alloy IIG deformation vs. fluence in various reactors at different energies of fast neutrons. The presented graphs enable comparison between the results of numerous experiments and enable predictions of Zr-material behavior in long-term operation and at high burn-up in commercial reactors.

Irradiation-induced Phase Transformations in Zirconium Alloys

Irradiation-induced Phase Transformations in Zirconium Alloys PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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[Sup 40]Ar and [sup 209]Bi ion irradiations of Zr[sub 3]Fe were performed at 35--725 K using 15-1500 keV ions. Results are presented on role of deposited-energy density on nature of the damaged regions in individual cascades produced by ion bombardment of Zr[sub 3]Fe. Comparison is also made between irradiation-induced amorphization of Zr[sub 3]Fe during electron irradiation and under ion bombardments. Dependence of damage production on incident electron energy in Zr[sub 3]Fe was also determined. Preliminary results are also discussed for amorphization of ZrFe[sub 2], Zr(Cr, Fe)[sub 2] and ZrCr[sub 2] by electron irradiation. Results of a recent investigation on amorphization of Zr(Cr, Fe)[sub 2] and Zr[sub 2](Ni, Fe) precipitates in Zircaloy-4 are discussed in context of previous experimental results of neutron and electron irradiations and likely amorphization mechanisms are proposed.

Government Reports Announcements & Index

Government Reports Announcements & Index PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 586

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