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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 518 - 525 (8page)
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초록· 키워드
오류제보하기
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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참고문헌 (19)
참고문헌 신청
J.P. Mardon / 2000 / Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy / Zirconium in the Nuclear Industry: 12th International Symposium :505~523
E. Perez-Fero / 2013 / High temperature oxidation experiments with sponge base E110G cladding / Proceedings, 10th International Conference on WWER Fuel Performance, Modelling and Experimental Support
Z. Hozer / 2015 / Experimental comparison of the behavior of E110 and E110G claddings at high temperature / Zirconium In The Nuclear Industry: 17th International Symposium STP1543:932~951
S. A. Nikulin / 2011 / Influence of chemical composition of zirconium alloy E110 on embrittlement under LOCA conditionsd Part 1 : oxidation kinetics and macrocharacteristics of structure and fracture / J. Nucl. Mater 418:1~7
P. Rudling / 2000 / Zirat Special Topical Report on Manufacturing (Zirat-5)
E. Perez-Fero / 2013 / High temperature oxidation experiments with sponge base E110G cladding / Proceedings, 10th International Conference on WWER Fuel Performance, Modelling and Experimental Support
Z. Hozer / 2015 / Experimental comparison of the behavior of E110 and E110G claddings at high temperature / Zirconium In The Nuclear Industry: 17th International Symposium STP1543:932~951
S. A. Nikulin / 2011 / Influence of chemical composition of zirconium alloy E110 on embrittlement under LOCA conditionsd Part 1 : oxidation kinetics and macrocharacteristics of structure and fracture / J. Nucl. Mater 418:1~7
P. Rudling / 2000 / Zirat Special Topical Report on Manufacturing (Zirat-5)
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