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Münch C., Blavius D. and Hoffmann P., Ursachanalyse zu Erhöhten Biegung von
Brennelementen , KTG Jahrestagung Kerntechnik, Hamburg, 2008.
Nagase F. and Fuketa T., 'Investigation of Hydride Rim Effect on Failure of Zircaloy-4
Cladding with Tube Burst Test', J. Nucl. Sci. Technol ., 42 , pp. 58-65, 2005, Taylor
and Francis, www.tandfonline.com.
Nikulina A. V., Markelov V. A., Peregud M. M., Bibilashvili Yu. K., Kotrekhov V. A.,
Lositsky A. F., Kuzmenko N. V., Shevnin Yu. P., Shamardin V. K., Kobylyansky
G. P. and Novoselov A. E., ' Zirconium Alloy E635 as a Material for Fuel Rod
Cladding and Other Components of VVER and RBMK Reactors ', Zirconium
in the Nuclear Industry: Eleventh International Symposium, ASTM STP
1295, E. R. Bradley and G. P. Sabol, Eds, American Society for Testing and
Materials,Garmisch-Parkenkirchen, Germany, pp. 785-804, 1996.
Nikulina A., Shishov S., Cox B., Garzarolli F. and Rudling P., ' Manufacturing of
Zr-Nb Alloys ', ZIRAT11 Special Topics Report, ANT International, Mölnlycke,
Sweden, 2006.
Nystrand A-C. and Bergquist H., ' Investigation of <c> Component Dislocation Density
in Irradiated ZIRLO and Zry-4 ', Zirconium in the Nuclear Industry: Twelfth
International Symposium, ASTM, Toronto, Canada, Poster Presentation, 2000.
Onimus F., Bechade J-L., Doriot S., Monnet I., Gilbon D., Verhaegue B., Prioul
C., Pilvin P. H., Robert L., Legras L. and Mardon J-P., 'Plastic Deformation
of Irradiated Zirconium Alloys: TEM Investigation and Micro-Mechanical
Modeling', J. ASTM Int ., 2 (8), Paper JAI12424, September, 2005.
Onimus F., Monnet I., Bechade J-L., Prioul C. and Pilvin P. H., 'A Statistical TEM
Investigation of Dislocation Channeling Mechanism in Neutron Irradiated
Zirconium Alloys', J. Nucl. Mater ., 328 , 165-179, 2004.
Pierron O. N., Koss D. A., Motta A. T. and Chan K. S., 'The Infl uence of Hydride
Blister on Fracture of Zircaloy-4', J. Nucl. Mater ., 322 , pp. 21-35, 2003.
Potts G. A., ' Recent GE Fuel Experience ', International Topical Meeting on Light Water
Fuel Performance, American Nuclear Society, Park City, Utah, April 10-13, 2000.
Rebeyrolle V., Mardon J.-P., Charquet D., Soniak A., Robert L. and Bouffi oux P.,
' Infl uence of Sulfur Addition on Irradiation Creep of M5 Alloy ', Poster,14th
International Symposium on Zirconium in the Nuclear Industry, Stockholm,
Sweden, June, 2004.
Regnard C., Verhaeghe B., Lefebvre- Joud F. and Lemaignan, C., ' Activated Slip
Systems and Localized Straining of Irradiated Zr Alloys in Circumferential
Loadings ', Zirconium in the Nuclear Industry: Thirteenth International
Symposium, ASTM 1423, Annecy, France, pp. 384-399, 11-14 June 2001.
Ribis J., Onimus F., Bechade J-L., Doriot S., Cappelaere C., Lemaignan C., Barbu
A. and Rabouille O., 'Experimental and Modelling Approach of Irradiation
Defects Recovery in Zirconium Alloys Impact of Applied Stress', (ASTM Zr
meeting, Sunriver, June, 2007), J. ASTM Int ., June, 2007.
Rickover, H. G., ' The Decision to Use Zirconium in Nuclear Reactors ', Zirconium
Production and Technology: The Kroll Medal Papers, ASTM RPS2, R. B.
Adamson, Ed., ASTM International, West Conshohocken,PA, USA, p. 9, 2010.
Rogerson A., 'Irradiation Growth of Annealed and 25% Cold Worked Zircaloy-2
Between 353 and 673K', J. Nucl. Mater ., 154 , pp. 276-285, 1988.
Rudling P., Adamson R., Bairiot H., Cox B., Ford P. Garzarolli F., Riess R. and
Strasser A., ' Fuel Material Technology Report, Vol. II ', ANT International,
Mölnlycke, Sweden, 2007.
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