Properties of zirconium alloys and their applications in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 173

Lemaignan C., 'Impact of Beta Radiolysis and Transient Products on Irradiation-
Enhanced Corrosion of Zr Alloys', J. Nucl. Mater ., 187 , pp. 122-130, 1992.
Lysell G., Nystrand A-C. and Ullberg M., ' On the Shadow Corrosion Mechanism for
Zirconium Alloys ', TopFuel 2001, P2-13, Stockholm, Sweden, 2001.
Lysell G., Nystrand A-C., and Ullberg M., 'Shadow Corrosion Mechanism of
Zircaloy', J. ASTM Int ., 2 (6), Paper JAI12374, 2005.
Mahmood S. T., Cantonwine P. E., Lin Y-P. and Crawford D. C., ' Shadow
Corrosion-Induced Bow of Zircaloy-2 Channels ', 16th International Symposium
on Zirconium in the Nuclear Industry, Chengdu, China, 2010.
Mahmood S. T., Edsinger K. W., Farkas D. M. and Adamson R. B., ' Effects of SPP
Dissolution on Mechanical Properties of Zircaloy-2 ', Proc., Int. Topical Meeting
on LWR Fuel Performance, ANS, Portland, pp. 440-451, 2-6 March, 1997.
Mahmood S. T., Farkas D. M., Adamson R. B. and Etoh Y., Post Irradiation
Characterization of Ultra-High-Fluence Zircaloy-2 Plate , Zirconium in the
Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, Sabol
G. P. and Moan G. D., Eds, American Society for Testing and Materials, West
Conshohocken, PA, pp. 139-169, 2000.
Mahmood S.T., Lin Y-P, Dubecky M. A., Edsinger K. and Mader E. V., ' Channel
Bow in Boiling Water Reactors - Hot Cell Examination Results and Correlation
to Measured Bow ', Proc. of the 2007 International LWR Fuel Performance
Meeting, Paper 1061, American Nuclear Society, San Francisco, CA, pp. 124-
133, 2007.
Mardon Jean Paul and Bordy Michel, ' Performance of M5™ Alloy as Cladding
Tube and Structural Component Material ', Proc: 14th Pacifi c Basin Nuclear
Conference, Honolulu, Hawaii, 21-25 March 2004.
Marlowe M. O., Armijo J. S., Cheng B. and Adamson R. B., ' Nuclear Fuel Cladding
Localised Corrosion ', Proc. ANS Int'l Topical Meeting LWR Fuel Perform.,
Orlando, FL, 3-73-3-90, 21-24 April 1985.
Matthews J. R. and Finnis M. W. 'Irradiation Creep Models - An Overview', J. Nucl.
Mater ., 159 , pp. 257-285, 1988.
Miyashita T. et al. , ' Corrosion and Hydrogen Pick-Up Behavior of Zircaloy Component
of BWR High Burnup 9 X 9 Lead Use Assemblies ', IAEA Technical Meeting on
High Burnup Fuel Experience and Economics, Sofi a, Bulgaria, 2006.
Miyashita T. et al ., ' Corrosion and Hydrogen Pick-Up Behaviors of Cladding and
Structural Components in BWR High Burnup 9x9 Lead Use Assemblies ',
Proceedings of the 2007 International LWR Fuel Performance Meeting, Paper
1015, San Francisco, California, 2007.
Möckel A, Cremer I., Kratzer A. and Walter D., ' Controlled Beta Quenching of Fuel
Channels Using Inert Gas ', KTG Jahrestagung Kerntechnik, Hamburg, 2008.
Morize P., Baicry J. and Mardon J. P., ' Effect of Irradiation at 588°K on Mechanical
Properties and Deformation Behavior of Zirconium Alloy Strip ', Zirconium in
the Nuclear Industry: Seventh Int'l Symposium, ASTM STP 939, R. B. Adamson
and L. F. P. Van Swam, Eds, American Society for Testing and Materials,
Philadelphia, pp. 101-119, 1987.
Motta A., 'Amorphization of Intermetallic Compounds Under Irradiation -
A Review', J. Nucl. Mater ., 244 , pp. 227-250, 1997.
Motta A. and Lemaignan C., 'A Ballistic Mixing Model for the Amorphization of
Precipitates in Zircaloy under Neutron Irradiation', J. Nucl. Mater ., 195 , pp.
277-285, 1992.

￿ ￿ ￿ ￿ ￿ ￿