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1
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0342385205
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Corrosion Behavior of Zircaloy-4 Cladding with Varying Tin Content in High-Temperature Pressurized Water Reactors
-
A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Garde, A. M., Pati, S. R., Krammen, M. A., Smith, G. P., and Endter, R. K., "Corrosion Behavior of Zircaloy-4 Cladding with Varying Tin Content in High-Temperature Pressurized Water Reactors," Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 760-778
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(1994)
Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245
, pp. 760-778
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-
Garde, A.M.1
Pati, S.R.2
Krammen, M.A.3
Smith, G.P.4
Endter, R.K.5
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2
-
-
0343689478
-
Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests
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L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Eucken, C. M., Finden, P. T., Trapp-Pritsching, S., and Weidinger, H. G., "Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests," Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 113-127.
-
(1989)
Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023
, pp. 113-127
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-
Eucken, C.M.1
Finden, P.T.2
Trapp-Pritsching, S.3
Weidinger, H.G.4
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3
-
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0342384201
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Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy-4 Fuel Cladding
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L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Shemel, J. H., Charquet, D., and Wadier, J.-F., "Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy-4 Fuel Cladding," Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 141-152.
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(1989)
Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023
, pp. 141-152
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-
Shemel, J.H.1
Charquet, D.2
Wadier, J.-F.3
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4
-
-
0342385305
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Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding
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L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Garzarolli, F., Steinberg, E., and Weidinger, H. G., "Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding," Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 202-212.
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(1989)
Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023
, pp. 202-212
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-
Garzarolli, F.1
Steinberg, E.2
Weidinger, H.G.3
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5
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0040703587
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Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements
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A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Garzarolli, F., Schumann, R., and Steinberg, E., "Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements," Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 709-723.
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(1994)
Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245
, pp. 709-723
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-
Garzarolli, F.1
Schumann, R.2
Steinberg, E.3
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6
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-
0009915273
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Corrosion Behavior of Zircaloy-4 Sheets Produced under Various Hot-rolling and Annealing Conditions
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A. M. Garde and E. R. Bradley Eds., American Society for Testing and Materials, West Conshohocken, PA
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Anada, H., Nomoto, K., and Shida, Y., "Corrosion Behavior of Zircaloy-4 Sheets Produced Under Various Hot-rolling and Annealing Conditions," Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245, A. M. Garde and E. R. Bradley Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 307-327.
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(1994)
Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245
, pp. 307-327
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-
Anada, H.1
Nomoto, K.2
Shida, Y.3
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7
-
-
0040703584
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Oxidation of Intermetallic Precipitates in Zircaloy-4: Impact of Irradiation
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A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Pecheur, D., Lefebvre, F., Motta, A. T., Lemaignan, C., and Charquet, D., "Oxidation of Intermetallic Precipitates in Zircaloy-4: Impact of Irradiation," Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 687-708.
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(1994)
Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245
, pp. 687-708
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-
Pecheur, D.1
Lefebvre, F.2
Motta, A.T.3
Lemaignan, C.4
Charquet, D.5
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8
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-
0026381514
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18
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C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA
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18," Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1991, pp. 416-436.
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(1991)
Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132
, pp. 416-436
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-
Godlewski, J.1
Gros, J.P.2
Lambertin, M.3
Wadier, J.F.4
Weidinger, H.5
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9
-
-
0026371569
-
Oxide Growth Mechanism on Zirconium Alloys
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C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Garzarolli, F., Seidel, H., Tricot, R., and Gros, J. P, "Oxide Growth Mechanism on Zirconium Alloys," Zirconium in the Nuclear industry (Ninth Volume), ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1991, pp. 395-415.
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(1991)
Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132
, pp. 395-415
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-
Garzarolli, F.1
Seidel, H.2
Tricot, R.3
Gros, J.P.4
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10
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-
0026386697
-
Microanalysis of the Matrix and the Oxide-Metal Interface of Uniformly Corroded Zircaloy
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C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Wadman, B. and Andren, H.-O., "Microanalysis of the Matrix and the Oxide-Metal Interface of Uniformly Corroded Zircaloy," Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1991, pp. 461-475.
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(1991)
Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132
, pp. 461-475
-
-
Wadman, B.1
Andren, H.-O.2
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11
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0026367147
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Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion Resistance
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C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Kubo, T. and Uno, M., "Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion Resistance," Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1991, pp. 476-498.
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(1991)
Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132
, pp. 476-498
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-
Kubo, T.1
Uno, M.2
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12
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0000256403
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Microstructure of Oxide Layers Formed during Autoclave Testing of Zirconium Alloys
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A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Wadman, B., Lai, Z., Andren, H.-O., Nystrom, A.-L. Rudling, P., and Pettersson, H., "Microstructure of Oxide Layers Formed During Autoclave Testing of Zirconium Alloys," Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 579-598.
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(1994)
Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245
, pp. 579-598
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-
Wadman, B.1
Lai, Z.2
Andren, H.-O.3
Nystrom, A.-L.4
Rudling, P.5
Pettersson, H.6
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13
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0342820137
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On the Initial Corrosion Mechanism of Zirconium Alloy: Interaction of Oxygen and Water with Zircaloy at Room Temperature and 450°C Evaluated by X-ray Absorption Spectroscopy and Photoelectron Spectroscopy
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A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Dobler, U., Knop, A, Ruhmann, H., and Beie, H.-J., "On the Initial Corrosion Mechanism of Zirconium Alloy: Interaction of Oxygen and Water with Zircaloy at Room Temperature and 450°C Evaluated by X-ray Absorption Spectroscopy and Photoelectron Spectroscopy," Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 644-662.
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(1994)
Zirconium in the Nuclear Industry (Tenth Volume), ASTM STP 1245
, pp. 644-662
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-
Dobler, U.1
Knop, A.2
Ruhmann, H.3
Beie, H.-J.4
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14
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5544237915
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Characterization of Zircaloy Corrosion Films by Analytical Transmission Electron Microscopy
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Portland, OR
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Bradley, E. R. and Perkins, R. A., "Characterization of Zircaloy Corrosion Films by Analytical Transmission Electron Microscopy," Proceedings, IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion of Zr-Base Alloys in Water Reactor Environments. 1989, Portland, OR.
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Proceedings, IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion of Zr-Base Alloys in Water Reactor Environments
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Bradley, E.R.1
Perkins, R.A.2
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Diffusion of Oxygen in Growing Zirconia Films
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Relationship between Uniform Corrosion Resistance and Crystal Structure of Oxide on Zircaloy-4
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to be presented
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Takeda, K., Anada, H., and Kajimura, H., "Relationship Between Uniform Corrosion Resistance and Crystal Structure of Oxide on Zircaloy-4," to be presented to Journal of the Japan Journal of Metals.
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Anada, H.2
Kajimura, H.3
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0000915132
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How the Tetragonal Zirconia is Stabilized in the Oxide Scale that is Formed on a Zirconium Alloy Corroded at 400°C in Steam
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A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Godlewski, J., "How the Tetragonal Zirconia is Stabilized in the Oxide Scale that is Formed on a Zirconium Alloy Corroded at 400°C in Steam," Zirconium in the Nuclear Industry (Tenth Symposium), ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 663-683.
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(1994)
Zirconium in the Nuclear Industry (Tenth Symposium), ASTM STP 1245
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24
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4344563786
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Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated Steam
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Zhou, B.-X., "Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated Steam," Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 360-373.
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Zirconium in the Nuclear Industry (Eighth Symposium), ASTM STP 1023
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Zhou, B.-X.1
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0028761206
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The Development of Porosity in Thick Zirconia Films
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Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-Based Alloys in 360°C Water and 400°C Steam
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C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials. West Conshohocken, PA
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Harada M., Kimpara, M., and Abe, K., "Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-Based Alloys in 360°C Water and 400°C Steam," Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials. West Conshohocken, PA, 1991, pp. 368-391.
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(1991)
Zirconium in the Nuclear Industry (Ninth Volume), ASTM STP 1132
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Harada, M.1
Kimpara, M.2
Abe, K.3
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