Journal Published Online: 04 November 2008
Volume 5, Issue 10

Investigation of Irradiation Hardening and Embrittlement of Zr-2.5%Nb Alloy with High-Energy (e,γ)-Beams

CODEN: JAIOAD

Abstract

The paper researches into the effect of the initial structural condition of Zr-2.5%Nb alloy, which is widely used in reactor engineering to manufacture reactor core components (mainly as a structural material for RBMK and CANDU pressure tubes), and of irradiation conditions (temperature, applied stress) on irradiation hardening and embrittlement. The reactor damage of Zr-2.5%Nb alloy was modeled with a method of high-energy 225 MeV (e,γ)-beam irradiation, which allows samples to be irradiated under strictly controlled stress conditions. The research has been carried out on Zr-2.5%Nb alloy exposed to four types of thermo-mechanical treatment. It has been found that the alloy is susceptible to intensive irradiation embrittlement irrespective of its initial condition, and the intensity of Zr-2.5%Nb irradiation hardening greatly depends on pre-treatment. In contrast to other conditions, Zr-2.5%Nb alloy is virtually not susceptible to irradiation hardening after high-speed high-frequency (SHF) heating, quenching, and subsequent annealing in the high-temperature range of the α-region, during which the double-phase α+βNb state with high dispersion of βNb (∼1023 m−3) precipitates develops. The obtained results are in good agreement with the post-reactor irradiation tensile test results. The study demonstrates the efficiency of high-energy (e,γ)-beam irradiation for investigating the irradiation hardening and embrittlement of zirconium alloys.

Author Information

Parkhomenko, O.
Materials Science and Technologies, National Science Center Kharkov Institute of Physics and Technology, Kharkov, Ukraine
Grytsyna, V.
“Nuclear Fuel Cycle” Science and Technology Establishment National Science Center Kharkov Institute of Physics and Technology, Kharkov, Ukraine
Chernyayeva, T.
“Nuclear Fuel Cycle” Science and Technology Establishment National Science Center Kharkov Institute of Physics and Technology, Kharkov, Ukraine
Azhazha, V.
Institute of Solid-State Physics, Materials Science and Technologies, National Science Center Kharkov Institute of Physics and Technology, Kharkov, Ukraine
Krasnorutskyy, V.
“Nuclear Fuel Cycle” Science and Technology Establishment National Science Center Kharkov Institute of Physics and Technology, Kharkov, Ukraine
Ozhigov, L.
Institute of Solid-State Physics, Materials Science And Technologies, National Science Center Kharkov Institute of Physics and Technology, Kharkov, Ukraine
Savchenko, V.
Institute of Solid-State Physics, Materials Science And Technologies, National Science Center Kharkov Institute of Physics and Technology, Kharkov, Ukraine
Pages: 11
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Stock #: JAI101494
ISSN: 1546-962X
DOI: 10.1520/JAI101494