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Evaluation of Hydrides Effects on Corrosion and Tensile Properties of Stress-relieved Zirconium Claddings  

Bang, Je-Geon (Zirconium Cladding Development Team, Korea Atomic Energy Research Institute)
Baek, Jong Hyuk (Zirconium Cladding Development Team, Korea Atomic Energy Research Institute)
Lee, Myung Ho (Zirconium Cladding Development Team, Korea Atomic Energy Research Institute)
Jeong, Yong Hwan (Zirconium Cladding Development Team, Korea Atomic Energy Research Institute)
Publication Information
Journal of the Korean Society for Heat Treatment / v.17, no.6, 2004 , pp. 356-364 More about this Journal
Abstract
The hydrides in cladding affect the corrosion and tensile properties. In this study corrosion and tensile properties were evaluated with varying the hydrogen concentration. The charged hydrogen contents were ranged from 200 to 1000 ppm. The corrosion rate in water and LiOH solution increases with the hydrogen concentration. The hydride did not affect the corrosion mechanism in the pre-transition region, but in the post-transition region the corrosion rate was accelerated. Cladding E contained higher Niobium content was slowly accelerated compared with other claddings. The yield and ultimate strengths were independent on the hydrogen content. However, the total elongation decreased gradually with increasing the hydrogen content. SEM observation of fracture surface showed that an average of depth of voids decreased with increasing the hydrogen content and small secondary crack are observed.
Keywords
Hydride; Zirconium; Corrosion; Cladding; Niobium;
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  • Reference
1 A. M. Garde, ASTM STP 1132, 566 (1991)
2 T. Kido, Proceedings, 6th International Symposium on Environmental Degradation of Materials in the Nuclear Power System, 745 (1993)
3 M. Blat and D. Noel, ASTM STP 1295, 319 (1996)
4 M. Blat, L. Legras, D. Noel, and H. Amanrich, ASTM STP 1354, 563 (2000)
5 G. Smith, EPRI-TR-103302, Vol. 1 (1994)
6 M. Blat and J. Bourgoin, International Topical Meeting on Light Water Reactor Fuel Performance, ANS, Portland, OR, March 1997, pp. 250-257
7 B. Cheng, ASTM STP 1295, 137 (1996)
8 L. G. Bell, R.G. Duncan, AECL Report, AECL-5110 (1975)
9 J. H. Hwang and M.S. Yeh, 6th International Symposium on environment Degradation of Materials in Nuclear Power Systems-Water Reactor, 1993
10 H. H. Burton, HW-61077 (1959)
11 R. L. Mehan and F. W. Wiesinger, KAPL-2110, (1961)
12 M. P. Puls, Metall. Trans A, Vol. 22A, 2327 (1991)
13 R. Choubey and M. P. Puls, Metall. Trans. A. Vol. 25A. 993 (1994)
14 W. E. Berry, D.A. Vaughan, E.L. White, Corrosion 109 (1961)