Influence of Structure¿̐ưPhase State of Nb Containing Zr Alloys on Irradiation-Induced Growth / VN. Shishov, MM. Peregud, AV. Nikulina, YV. Pimenov, GP. Kobylyansky, AE. Novoselov, ZE. Ostrovsky, AV. Obukhov
- Conference Author:
- Zirconium in the Nuclear Industry: Fourteenth International Symposium (14th : 2004 : Stockholm)
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- 1 online resource (20 pages) : illustrations, figures, tables
- Additional Creators:
- Shishov, VN., Kobylyansky, GP., Nikulina, AV., Novoselov, AE., Obukhov, AV., Ostrovsky, ZE., Peregud, MM., Pimenov, YV., American Society for Testing and Materials, and ASTM International
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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¿̐ư350 %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¿̐ư90 % 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¿̐ư350 ¿̐ưC). 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.
- Dates of Publication and/or Sequential Designation:
- Volume 2005, Issue 1467 (January 2005)
- Other Subject(s):
- 9780803155190 (e-ISBN)
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- Includes bibliographical references 14.
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