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- 저자 : Perez-Fero, (검색결과 1 건)
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M. Kir aly,Z. Hozer,M. Horvath,T. Novotny,E. Perez-Fero,N. Ver 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.2
The mechanical and corrosion behavior of the Russian zirconium fuel cladding alloy E110, predominantlyused in VVERs, has been investigated for many decades. The recent commercialization of a new, optimizedE110 alloy, produced on a sponge zirconium basis, gave the opportunity to compare the mechanicalproperties of the old and the new E110 fuel claddings. Axial and tangential tensile test experiments were performed with samples from both claddings in theMTA EK. Due to the anisotropy of the cladding tubes, the axial tensile strength was 10e15% higher thanthe tangential (measured by ring tensile tests). The tensile strength of the new E110G alloy was 11%higher than that of the E110 cladding at room temperature. Some samples underwent chemical treatment e slight oxidation in steam or hydrogenation e or heattreatment e in argon atmosphere at temperatures between 600 and 1000 C. The heat treatment duringthe oxidation had more significant effect on the tensile strength of the claddings than the oxidation itself,which lowered the tensile strength as the thickness of the metal decreased. The hydrogenation of thecladding samples slightly lowered the tensile strength and the samples but they remained ductile even atroom temperature.
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