-
1
-
-
0021602002
-
Effect of Lithium Hydroxide on the Corrosion Behavior of Zircaloy-4
-
D. G. Franklin and R. B. Adamson, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
McDonald, S. G., Sabol, G. P., and Sheppard, K. D., "Effect of Lithium Hydroxide on the Corrosion Behavior of Zircaloy-4," Zirconium in the Nuclear Industry: Sixth International Symposium, ASTM STP 824, D. G. Franklin and R. B. Adamson, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1984, pp. 519-530.
-
(1984)
Zirconium in the Nuclear Industry: Sixth International Symposium, ASTM STP 824
, pp. 519-530
-
-
McDonald, S.G.1
Sabol, G.P.2
Sheppard, K.D.3
-
2
-
-
5544224946
-
Influence of Various Additions to Water on Zircaloy-4 Corrosion in Autoclave Tests at 350°C
-
Portland, OR
-
Garzarolli, F., Pohlmeyer, J., Trapp-Pritsching, S., and Weidinger, H. G., "Influence of Various Additions to Water on Zircaloy-4 Corrosion in Autoclave Tests at 350°C," Proceedings, IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion of Zirconium-Base Alloys in Water Reactor Environment, 1989, Portland, OR.
-
(1989)
Proceedings, IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion of Zirconium-Base Alloys in Water Reactor Environment
-
-
Garzarolli, F.1
Pohlmeyer, J.2
Trapp-Pritsching, S.3
Weidinger, H.G.4
-
3
-
-
0026383972
-
Corrosion of Zircaloy-4 PWR Fuel Cladding in Lithiated and Borated Water Environments
-
C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Bramwell, I. L., Parsons, P. D., and Tice, D. R., "Corrosion of Zircaloy-4 PWR Fuel Cladding in Lithiated and Borated Water Environments," Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1991, pp. 628-642.
-
(1991)
Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132
, pp. 628-642
-
-
Bramwell, I.L.1
Parsons, P.D.2
Tice, D.R.3
-
4
-
-
0004671269
-
Effect of Elevated Lithium on the Waterside Corrosion of Zircaloy-4: Experimental and Predictive Studies
-
Řež near Prague, Czech
-
Pêcheur, D., Giordano, A., Picard, E., Billot, P., and Thomazet, J., "Effect of Elevated Lithium on the Waterside Corrosion of Zircaloy-4: Experimental and Predictive Studies," Proceedings, IAEA Technical Committee Meeting on Influence of Water Chemistry on Fuel Cladding Behaviour, 1993, Řež near Prague, Czech.
-
(1993)
Proceedings, IAEA Technical Committee Meeting on Influence of Water Chemistry on Fuel Cladding Behaviour
-
-
Pêcheur, D.1
Giordano, A.2
Picard, E.3
Billot, P.4
Thomazet, J.5
-
5
-
-
0003068496
-
Aqueous Chemistry of Lithium Hydroxide and Boric Acid and Corrosion of Zircaloy-4 and Zr-2.5Nb Alloys
-
A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Ramasubramanian, N. and Balakrishnan, P. V., "Aqueous Chemistry of Lithium Hydroxide and Boric Acid and Corrosion of Zircaloy-4 and Zr-2.5Nb Alloys," 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, West Conshohocken, PA, 1994, pp. 378-399.
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
, pp. 378-399
-
-
Ramasubramanian, N.1
Balakrishnan, P.V.2
-
6
-
-
0345382494
-
Lithium and Boron Effects in the Corrosion Mechanism of Zirconium Alloys under Coolant Chemistry Conditions
-
BNES, UK
-
Ramasubramanian, N., "Lithium and Boron Effects in the Corrosion Mechanism of Zirconium Alloys under Coolant Chemistry Conditions," Proceedings, Water Chemistry of Nuclear Reactor Systems 7, BNES, 1996, UK.
-
(1996)
Proceedings, Water Chemistry of Nuclear Reactor Systems 7
-
-
Ramasubramanian, N.1
-
7
-
-
0004647462
-
Experimental and Theoretical Studies of Parameters that Influence Corrosion of Zircaloy-4
-
A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Billot, P., Robin, J.-C., Giordano, A., Peybernès, J., Thomazet, J., and Amanrich, H., "Experimental and Theoretical Studies of Parameters that Influence Corrosion of Zircaloy-4," 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, West Conshohocken, PA, 1994, pp. 351-377.
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
, pp. 351-377
-
-
Billot, P.1
Robin, J.-C.2
Giordano, A.3
Peybernès, J.4
Thomazet, J.5
Amanrich, H.6
-
8
-
-
0038925652
-
PWR Zircaloy Fuel Cladding Corrosion Performance, Mechanisms, and Modeling
-
E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Cheng, B., Gilmore, P. M., and Klepfer, H. H., "PWR Zircaloy Fuel Cladding Corrosion Performance, Mechanisms, and Modeling," 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, West Conshohocken, PA, 1996, pp. 137-160.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
, pp. 137-160
-
-
Cheng, B.1
Gilmore, P.M.2
Klepfer, H.H.3
-
9
-
-
0342385305
-
Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding
-
L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
F. Garzarolli Steinberg, E., and Weidinger, H. G., "Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1989, p. 202.
-
(1989)
Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
, pp. 202
-
-
Garzarolli, F.1
Steinberg, E.2
Weidinger, H.G.3
-
10
-
-
0342820106
-
Developments of Remote-controlled Electron Probe Micro Analyzer and Secondary Ion Mass Spectrometer
-
Caderache, France
-
Yamaguchi, Y., Takeda, Y., Iwamura, T., Abeta, S., Nishioka, H., and Aoki, T., "Developments of Remote-controlled Electron Probe Micro Analyzer and Secondary Ion Mass Spectrometer," Proceeding, IAEA Technical Committee Meeting on Recent Developments on PIE Techniques for Water Reactor Fuel, 1994, Caderache, France.
-
(1994)
Proceeding, IAEA Technical Committee Meeting on Recent Developments on PIE Techniques for Water Reactor Fuel
-
-
Yamaguchi, Y.1
Takeda, Y.2
Iwamura, T.3
Abeta, S.4
Nishioka, H.5
Aoki, T.6
-
11
-
-
0030289887
-
Microstructure of Oxide Films Formed during the Waterside Corrosion of the Zircaloy-4 Cladding in Lithiated Environment
-
E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Pêcheur, D., Godlewski, J., Billot, Ph., and Thomazet, J., "Microstructure of Oxide Films Formed during the Waterside Corrosion of the Zircaloy-4 Cladding in Lithiated Environment," 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, West Conshohocken, PA, 1996, pp. 94-113.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
, pp. 94-113
-
-
Pêcheur, D.1
Godlewski, J.2
Billot, Ph.3
Thomazet, J.4
-
12
-
-
0018480171
-
The Cyclic Nature of Corrosion of Zircaloy-4 in 633 K Water
-
Bryner, J. S., "The Cyclic Nature of Corrosion of Zircaloy-4 in 633 K Water," Journal of Nuclear Materials, Vol. 82, 1979, pp. 84-101.
-
(1979)
Journal of Nuclear Materials
, vol.82
, pp. 84-101
-
-
Bryner, J.S.1
-
13
-
-
18444402688
-
Porosimeter for Determining the Sizes of Flaws in Zirconia or Other Insulating Films 'in Situ'
-
Cox, B., "Porosimeter for Determining the Sizes of Flaws in Zirconia or Other Insulating Films 'In Situ'," Journal of Nuclear Materials, Vol. 27, 1968, pp. 1-11.
-
(1968)
Journal of Nuclear Materials
, vol.27
, pp. 1-11
-
-
Cox, B.1
-
14
-
-
0023349752
-
Pore Structure in Oxide Films on Irradiated and Unirradiated Zirconium Alloys
-
Cox, B., "Pore Structure in Oxide Films on Irradiated and Unirradiated Zirconium Alloys," Journal of Nuclear Materials, Vol. 148, 1987, pp. 332-343.
-
(1987)
Journal of Nuclear Materials
, vol.148
, pp. 332-343
-
-
Cox, B.1
-
15
-
-
0028761206
-
The Development of Porosity in Thick Zirconia Films
-
Cox, B. and Yamaguchi, Y., "The Development of Porosity in Thick Zirconia Films," Journal of Nuclear Materials, Vol. 210, 1994, pp. 303-317.
-
(1994)
Journal of Nuclear Materials
, vol.210
, pp. 303-317
-
-
Cox, B.1
Yamaguchi, Y.2
|