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http://dx.doi.org/10.3365/KJMM.2010.48.08.717

Evaluation of Hydride Effect on Fuel Cladding Degradation  

Kim, Hyun-Gil (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Kim, Il-Hyun (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Park, Sang-Yoon (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Park, Jeong-Yong (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Jeong, Yong-Hwan (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
Publication Information
Korean Journal of Metals and Materials / v.48, no.8, 2010 , pp. 717-723 More about this Journal
Abstract
The degradation behavior of fuel cladding is a very import concern in nuclear power generation, because the operation of nuclear plants can be limited by fuel cladding degradation. In order to evaluate the hydride effect on failure of zirconium fuel claddings, a ring tensile test for the circumferential direction was carried out at room temperature for claddings having different hydride characteristics such as density and orientation; microstructural evaluation was also performed for those claddings. The circumferential failure of the claddings was promoted by increasing the hydride concentration in the matrix; however, the failure of the claddings was affected by the hydride orientation rather than by the hydride concentration in the matrix. From fracture surface observation, the cladding failure during the ring tensile test was matched with the hydride orientation.
Keywords
metals; deformation; microstructure; tensile test; nuclear;
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Times Cited By KSCI : 2  (Citation Analysis)
Times Cited By SCOPUS : 0
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1 J. P. Mardon, A. Lesbros, C. Bernaudat, and N. Waeckel, Proc. of the 2004 Int. Meeting on LWR Fuel Performance, p. 507, Orland, FL (2004).
2 W. H. Erickson and D. Hardie, J. Nucl. Mater. 13, 254 (1964).   DOI   ScienceOn
3 J. J. Kearns, J. Nucl. Mater. 22, 292 (1967).   DOI   ScienceOn
4 M. H. Lee, J. H. Kim, S. Y. Park, B. K. Choi, and Y. H. Jeong, Met. Mater. Int. 15, 539 (2009).   DOI   ScienceOn
5 R. O. Meyer, R. K. McCardell, H. M. Chung, D. J. Diamond, and H. H. Scott, Nuclear Safety 37, 271 (1996).
6 K. Kllstrm, Scandinavian Journal of Metallurgy 4, 65 (1975).
7 K. Ito, K. Kamimura, and Y. Tsukuda, Proc. of the 2004 Int. Meeting on LWR Fuel Performance, Orland, FL (2004).
8 H. G. Kim, B. K. Choi, and Y. H. Jeong, J. Kor. Inst. Met. & Mater. 45, 500 (2007).
9 H. Chung, R. Daum, J. Miller, and M. Billone, Zirconium in the Nuclear Industry, ASTM STP 1423, 561 (2002).
10 W. Evans and J. A. L. Robertson, The Physical Metallurgy of Zirconium Alloys, p.48, Chalk River Nuclear Lab. (1975).