Properties of zirconium alloys and their applications in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 169

STP 939, Adamson R. B. and Van Swam L. F. P., Eds, ASTM, Philadelphia, pp.
257-283, 1987.
Cheng B-C., Krüger R. M. and Adamson R. B., ' Corrosion Behaviour of Irradiated
Zircaloy', Proc. 10th Int. Symp. in the Nucl. Ind., ASTM STP 1245, pp. 400-418,
1994.
Christien F. and Barbu A., 'Cluster Dynamics Modeling of Irradiation Growth of
Zirconium Single Crystals', J. Nucl. Mater. , 393 , pp. 153-161, 2009.
Chu H., Wu S. and Kuo R., 'Hydride Reorientation in Zircaloy-4 Cladding', J. Nucl.
Mater. , 373 , pp. 319-327, 2008.
Chu H. C., Wu S. K., Kuo R. C. and Cheng S. C., ' Effect of Radial Hydrides on
Mechanical Properties of Zircaloy-4 Cladding', Proc. Water Reactor Fuel
Performance Meeting, Kyoto, Japan, October 2-6, 2005.
Coleman C. E., 'Cracking of Hydride-Forming Metals and Alloys', Comprehensive
Structural Integrity , Vol. 6 , Environmentally Assisted Failure, F. Petit and
P. Scott, Eds, chapter 6-03, pp. 103-161, Oxford, UK, 2003.
Coleman C. E. and Theaker J. R., ' Effect of Ingot Preparation Method on Irradiation
Response of Zr-2.5Nb', Proc. 14th ASTM Symposium on Zirconium in the
Nuclear Industry, Stockholm, 2004.
Comstock R. J., Schoenberger G. and Sabol G. P., ' Infl uence of Processing Variables
and Alloy Chemistry on the Corrosion Behavior of ZIRLO Nuclear Fuel
Cladding', Zirconium in the Nuclear Industry: 11th Int'l Symposium, ASTM
STP 1295, E. R. Bradley and G. P. Sabol, Eds, American Society for Testing and
Materials, pp. 710-725, 1996.
Cox B., 'Some Thoughts on the Mechanisms of In-Reactor Corrosion of Zirconium
Alloys', J. Nucl. Mater. , 336 , pp. 331-368, 2005.
Cox B., Garzarolli F., Adamson R., Rudling P. and Strasser A., ' Fuel Material
Technology Report Vol. I', ANT International, Mölnlycke, Sweden, 2006.
Cox B., Garzarolli F. and Rudling R., ' Corrosion of Zr-Nb Alloys', ZIRAT9 Special
Topics Report, ANT International, Mölnlycke, Sweden, 2004.
Cox B., Garzarolli F., Strasser A. and Rudling P., ' Structural Behavior of Fuel and Fuel
Channel Components', ZIRAT10 Special Topics Report, ANT International,
Mölnlycke, Sweden, 2005.
Cox B. and Rudling P., ' Hydriding Mechanisms and Impact on Fuel Performance',
ZIRAT5, Special Topics Report, ANT International, Mölnlycke, Sweden, 2000.
Dahlbäck M, Limbäck M., Hallstadius L., Barberis P., Bunel G., Simonot C.,
Andersson T., Askeljung P., Flygar J., Lehtinen B. and Massih A. R., 'The Effect
of Beta Quenching in Final Dimension on the Irradiation Growth of Tubes and
Channels', J. ASTM Int ., 2 , June 2005, paper JAI12337, 2005.
Daum RS., Majumdar S., Liu Y. and Billone MC., ' Mechanical Testing of High-Burnup
Zircaloy-4 Fuel Cladding under Conditions Relevant to Drying Operations and
Dry-Cask Storage ', Proc. Water Reactor Fuel Performance Meeting, Kyoto,
Japan, pp. 498-531, October 2-6, 2005.
Davies P. H., Hosbons R. R., Griffi ths M. and Chow C. K., ' Correlation Between
Irradiated and Unirradiated Fracture Toughness of Zr-2.5Nb Pressure Tubes ',
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM
STP 1245, A. M. Garde and E. R. Bradley, Eds, American Society for Testing
and Materials, Philadelphia, 135-167, 1994.
Doriot Sylvie, Gilbon Didier, Béchade Jean-Luc, Mathon Marie-Hélène, Legras
Laurent, and Mardon Jean-Paul, 'Microstructural Stability of M5TM Alloy

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