Abstract
This paper provides historical context and future direction on selected contributions to understanding zirconium-alloy deformation and corrosion in light water reactors. More detailed discussion of the relative importance of electrochemical potential and hydrogen pickup on nodular corrosion is provided. Since nodular corrosion was observed about 50 years ago, several explanations have been proposed. None have explained all the observations, especially the sharp transition between nodular-free and nodular-covered regions of some fuel rods, with the transition being reversed between high- and low-power regions. However, the effect of electrochemical potential dominates any effects of hydrogen, other than the effect of hydrogen on electrochemical potential.
Issue Section:
Research Papers
References
1.
Franklin
, D. G.
, Lucas
, G. E.
, and Bement
, A. L.
, Creep of Zirconium Alloys in Nuclear Reactors, ASTM STP 815
, ASTM International
, West Conshohocken, PA
, 1983
.2.
Erbacher
, F. J.
and Leistikow
, S.
, “Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 451
–488
.3.
Franklin
, D. G.
and Adamson
, R. B.
, “Implications of Zircaloy Creep and Growth to Light Water Reactor Performance
,” J. Nucl. Mater.
0022-3115, Vol. 159
, 1988
, pp. 12
–21
. https://doi.org/10.1016/0022-3115(88)90082-74.
Franklin
, D. G.
and Franz
, W. A.
, “Numerical Model for Anisotropic Creep of Zircaloy
,” Zirconium in the Nuclear Industry, ASTM STP 633
, A. L.
Lowe
Jr. and G. W.
Parry
, Eds., ASTM International
, West Conshohocken, PA
, 1977
, pp. 365
–384
. https://doi.org/10.1520/STP35581S5.
Nichols
, F. A.
, “Mechanistic Modeling of Zircaloy Deformation and Fracture in Fuel Element Analysis
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 5
–22
.6.
Tenckhoff
, E.
, “Review of Deformation Mechanisms, Texture, and Mechanical Anisotropy in Zirconium and Zirconium Base Alloys
,” Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467
, P.
Rudling
and B.
Kammenzind
, Eds., June 13-17, 2004, Stockholm, Sweden, ASTM International, West Conshohocken, PA, 2005
, pp. 25
–50
.7.
Gelebart
, L.
, Crepin
, J.
, Dexet
, M.
, Sauzay
, M.
, and Roos
, A.
, “Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys
,” Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467
, P.
Rudling
and B.
Kammenzind
, Eds., ASTM International, West Conshohocken, PA, 2005
, pp. 585
–603
.8.
Allen
, V. M.
, Quinta da Fonseca
, J.
, Preuss
, M.
, Robson
, J. D.
, Daymond
, M.
, and Comstock
, R. H.
, “Determination and Interpretation of Texture Evolution During Deformation of a Zirconium Alloy
,” Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
, B.
Kammenzind
and M.
Limback
, Eds., June 24-28, 2007, Sun River, OR, ASTM International, West Conshohocken, PA, 2009
, pp. 550
–563
.9.
Kass
, S.
, “The Development of the Zircaloys
,” Corrosion of Zirconium Alloys, ASTM STP 368
, ASTM International
, West Conshohocken, PA
, 1964
, pp. 3
–27
.10.
Hillner
, E.
, “Corrosion of Zirconium-Base Alloys—An Overview
,” Zirconium in the Nuclear Industry, ASTM STP 633
, A. L.
Lowe
Jr. and G. W.
Parry
, Eds., ASTM International
, West Conshohocken, PA
, 1977
, pp. 211
–235
. https://doi.org/10.1520/STP35573S11.
Cox
, B.
, “Some Thoughts on the Mechanisms of In-Reactor Corrosion of Zirconium Alloys
,” J. Nucl. Mater.
0022-3115, Vol. 336
, 2005
, pp. 331
–368
. https://doi.org/10.1016/j.jnucmat.2004.09.02912.
Tsai
, H.
and Billone
, M. C.
, “Thermal Creep of Irradiated Zircaloy Cladding
,” Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467
, P.
Rudling
and B.
Kammenzind
, Eds., June 24-28, 2007, Sun River, OR, ASTM International, West Conshohocken, PA, 2005
, pp. 632
–650
.13.
Alam
, A. M.
and Hellwig
, C.
, “Cladding Tube Deformation Test for Stress Reorientation of Hydrides
,” Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
, B.
Kammenzind
and M.
Limback
, Eds., June 24-28, 2007, Sun River, OR, ASTM International, West Conshohocken, PA, 2009
, pp. 635
–650
.14.
Aomi
, M.
, Baba
, T.
, Miyashita
, T.
, Kamimura
, K.
, Yasuda
, T.
, Shinohara
, Y.
, and Takeda
, T.
, “Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage
,” Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
, B.
Kammenzind
and M.
Limback
, Eds., June 24-28, 2007, Sun River, OR, ASTM International, West Conshohocken, PA, 2009
, pp. 651
–673
.15.
Ribis
, J.
, Onimus
, F.
, Bechade
, J.-L.
, Doriont
, S.
, Cappelaere
, C.
, Lemaignan
, C.
, Barbu
, A.
, and Rabouille
, O.
, “Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress
,” Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
, B.
Kammenzind
and M.
Limback
, Eds., June 24-28, 2007, Sun River, OR, ASTM International, West Conshohocken, PA, 2009
, pp. 674
–695
.16.
Hillner
, E.
, Franklin
, D. G.
, and Smee
, J. D.
, “Long-Term Corrosion of Zircaloy Before and After Irradiation
,” J. Nucl. Mater.
0022-3115, Vol. 278
, 2000
, pp. 334
–345
. https://doi.org/10.1016/S0022-3115(99)00230-517.
Garzarolli
, F.
, Jung
, W.
, Schoenfeld
, H.
, Garde
, A. M.
, Parry
, G. W.
, and Smerd
, P. G.
, “Waterside Corrosion of Zircaloy Fuel Rods
,” Report No. EPRI NP-2789, Electric Power Research Institute, Palo Alto, CA, December 1982
.18.
Cheng
, B. C.
, Kruger
, R. M.
, and Adamson
, R. B.
, “Corrosion Behavior of Irradiated Zircaloy
,” Zirconium in the Nuclear Industry: 10th International Symposium, ASTM STP 1245
, A. M.
Garde
and E. R.
Bradley
, Eds., June 21-24, 1993, Baltimore, MD, ASTM International, West Conshohocken, PA, 1994
, pp. 400
–418
.19.
Iltis
, X.
, Lefebvre
, F.
, and Lamaignan
, C.
, “Microstructure Evolutions and Iron Redistribution in Zircaloy Oxide Layers: Comparative Effects of Neutron Irradiation Flux and Irradiation Damages
,” Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295
, E. R.
Bradley
and G. P.
Sabol
, Eds., September 11–14, 1995, Garmisch-Partenkirchen, Germany, ASTM International, West Conshohocken, PA, 1996
, pp. 242
–264
.20.
Cheng
, B.
and Adamson
, R. B.
, “Mechanistic Studies of Zircaloy Nodular Corrosion
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 387
–416
.21.
Rosecrans
, P. M.
, “Application of Alternating-Current Impedance Measurements to Characterize Zirconium Alloy Oxidation Films
,” ASTM STP 824
, ASTM International
, West Conshohocken, PA
, 1984
, pp. 531
–553
.22.
Mergerth
, F. H.
, Ruiz
, C. P.
, and Wolff
, U. E.
, “Zircaloy-Clad UO2 Fuel Rod Evaluation Program
,” Report No. GEAP-10371, U.S. AEC Research and Development, Washington, DC, June 1971
.23.
Johnson
, A. B.
, “Effect of Nuclear Radiation on the Corrosion, Hydriding, and Oxide Properties of Six Zirconium Alloys
,” Applications-Related Phenomena for Zirconium and Its Alloys, ASTM STP 458
, ASTM International
, West Conshohocken, PA
, 1969
, pp. 301
–324
. https://doi.org/10.1520/STP43835S24.
Trowse
, F. W.
, Summerling
, R.
, and Garlick
, A.
, “Nodular Corrosion of Zircaloy-2 and Some Other Zirconium Alloys in Steam Generating Heavy Water Reactors and Related Environments
,” Zirconium in the Nuclear Industry, ASTM STP 633
, A. L.
Lowe
Jr. and G. W.
Parry
, Eds., ASTM International
, West Conshohocken, PA
, 1977
, pp. 236
–257
. https://doi.org/10.1520/STP35574S25.
Garzarolli
, F.
, Diez
, W.
, Francke
, K. P.
, and Fricke
, W.
, “Corrosion and Hydriding of Zircaloy-2 and Other Zirconium Alloys in BWRs
,” Effect of Environment on Material Properties in Nuclear Systems
, Institution of Civil Engineers
, London
, 1971
, pp. 15
–20
.26.
Cox
, B.
, “Assessment of In-Reactor Corrosion Models and Data for Zircaloys in Water
,” Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors
, Monterey, CA, Sept. 9–12, International Atomic Energy Agency, Vienna, Austria, 1985
, pp. 219
–226
.27.
International Atomic Energy Agency,
1998
, “Waterside Corrosion of Zirconium Alloys in Nuclear Poser Plants
,” IAEA-TECDOC-996, Vienna, Austria.28.
Nishino
, Y.
, Endo
, M.
, Ibe
, E.
, and Yasuda
, T.
, “Formation and Dissolution of Oxide Film on Zirconium Alloys in 288°C Pure Water Under γ-Ray Irradiation
,” J. Nucl. Mater.
0022-3115, Vol. 248
, 1997
, pp. 292
–298
. https://doi.org/10.1016/S0022-3115(97)00126-829.
Franklin
, D. G.
and Li
, C. Y.
, “Effects of Heat Flux and Irradiation-Induced Changes in Water Chemistry on Zircaloy Nodular Oxidation
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 206
–223
.30.
Urquhart
, A. W.
and Vermilyea
, D. A.
, “A Preliminary Correlation Between the Accelerated Corrosion of Zircaloy in BWRs and in High Temperature, High Pressure Steam
,” J. Nucl. Mater.
0022-3115, Vol. 62
, 1976
, pp. 111
–114
. https://doi.org/10.1016/0022-3115(76)90289-031.
Marlowe
, M. O.
, Armijo
, J. S.
, Cheng
, B.
, and Adamson
, R. B.
, “Nuclear Fuel Cladding Localized Corrosion
,” Light Water Reactor Fuel Performance, ANS Topical Meeting
, Vol. 1
, Orlando, FL, April 21–24, American Nuclear Society, La Grange Park, IL, 1985
, pp. 3-72
–3-90
.32.
Mishima
, Y.
and Aoki
, T.
, “Proving Test on the Reliability of BWR 8×8 Fuel Assemblies in Japan
,” Improvements in Water Reactor Fuel Technology and Utilization Symposium
, Stockholm, Sweden, Sept. 15, International Atomic Energy Agency, Vienna, Austria, 1986
, pp. 81
–99
.33.
Etoh
, Y.
, “Effects of Operational Parameters on Nodular Corrosion Characteristics
,” J. Nucl. Sci. Technol.
0022-3131, Vol. 26
(8
), 1989
, pp. 752
–759
. https://doi.org/10.3327/jnst.26.75234.
Sell
, H.-J.
, Trapp-Pritsching
, S.
, and Garzarolli
, F.
, “Effect of Alloying Elements and Impurities on In-BSWR Corrosion of Zirconium Alloys
,” Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467
, P.
Rudling
and B.
Kammenzind
, Eds., June 13-17, 2004, Stockholm, Sweden, ASTM International, West Conshohocken, PA, 2005
, pp. 404
–417
.35.
Etoh
, Y.
, Kikuchi
, K.
, Yasuda
, T.
, Koizumi
, S.
, and Oishi
, M.
, “Neutron Irradiation Effects on the Nodular Corrosion of Zircaloy-2
,” Proceedings of the ANS International Topical Meeting on LWR Fuel Performance
, Vol. 2
, Avignon, France, April 21–24, American Nuclear Society, La Grange Park, IL, 1991
, pp. 691
–700
.36.
Draley
, J. E.
and Ruther
, W. E.
, “Some Unusual Effects of Hydrogen in Corrosion Reactions
,” J. Electrochem. Soc.
0013-4651, Vol. 104
(6
), 1957
, pp. 329
–333
. https://doi.org/10.1149/1.242857537.
Urquhart
, A. W.
, Vermilyea
, D. A.
, and Rocco
, W. A.
, “A Mechanism for the Effect of Heat Treatment on the Accelerated Corrosion of Zircaloy-4 in High Temperature High Pressure Steam
,” J. Electrochem. Soc.
0013-4651, Vol. 125
, 1978
, pp. 199
–204
. https://doi.org/10.1149/1.213141438.
Rudling
, P.
and Wikmark
, G.
, “A Unified Model of Zircaloy BWR Corrosion and Hydriding Mechanisms
,” J. Nucl. Mater.
0022-3115, Vol. 265
, 1999
, pp. 44
–59
. https://doi.org/10.1016/S0022-3115(98)00613-839.
Ramasubramanian
, N.
, “Out-Reactor Nodular Corrosion Behavior of Zircaloys
,” J. Nucl. Mater.
0022-3115, Vol. 119
, 1983
, pp. 208
–218
. https://doi.org/10.1016/0022-3115(83)90197-640.
Garzarolli
, F.
and Manzel
, R.
, Korrosionbestandigkeit von Zircaloy in KWU-Leistungsreaktoren
, Reaktor Tagung
, Berlin
, 1977
.41.
Aomi
, M.
, Kogai
, T.
, Shimada
, S.
, Ichikawa
, N.
, Ibe
, E.
, Ishii
, Y.
, Cheng
, B.
, and Lutz
, D.
, “Evaluation of Zircaloy Corrosion Under Various Water Chemistries in a BWR Simulation Loop
,” Water Chemistry of Nuclear Reactor Systems 7
, BNES
, London, England
, 1996
, pp. 284
–286
.42.
Takagawa
, Y.
, Ishimoto
, S.
, Etoh
, Y.
, Kubo
, T.
, Ogata
, K.
, and Kubota
, O.
, “The Correlation Between Microstructures and In-BWR Corrosion Behavior of Highly Irradiated Zr-Based Alloys
,” Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467
, P.
Rudling
and B.
Kammenzind
, Eds., June 13-17, 2004, Stockholm, Sweden, ASTM International, West Conshohocken, PA, 2005
, pp. 386
–403
.43.
Huang
, P. Y.
, Mahmood
, T. S.
, and Adamson
, R. B.
, “Effects of Thermomechanical Processing on In-Reactor Corrosion of Post-Irradiation Mechanical Properties of Zircaloy-2
,” Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295
, E. R.
Bradley
and G. P.
Sabol
, Eds., September 11–14, 1995, Garmisch-Partenkirchen, Germany, ASTM International, West Conshohocken, PA, 1996
, pp. 726
–757
.44.
Tagstrom
, P.
, Limback
, M.
, Dahlback
, M.
, Andersson
, T.
, and Pettersson
, H.
, “Effects of Hydrogen Pickup and Second-Phase Particle Dissolution on the In-Reactor Corrosion Performance of BWR Claddings
,” Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423
, G. D.
Moan
and P.
Rudling
, Eds., June 10-14, 2001, Annecy, France, ASTM International, West Conshohocken, PA, 2002
, pp. 96
–118
.45.
Kakiuchi
, K.
, Itagaki
, N.
, Furuya
, T.
, Miyazaki
, A.
, Ishii
, Y.
, Suzuki
, S.
, Terai
, T.
, and Yamawaki
, M.
, “Role of Iron for Hydrogen Absorption Mechanism in Zirconium Alloys
,” Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467
, P.
Rudling
and B.
Kammenzind
, Eds., June 13-17, 2004, Stockholm, Sweden, ASTM International, West Conshohocken, PA, 2005
, pp. 349
–366
.46.
Rudling
, P.
, Lundblad Vannesjo
, K.
, Vesterlund
, G.
, and Massih
, A. R.
, “Influence of Second-Phase Particles on Zircaloy Corrosion in BWR Environment
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 292
–306
.47.
Maussner
, G.
, Steinberg
, E.
, and Tenckhoff
, E.
, “Nucleation and Growth of Intermetallic Precipitates in Zircaloy-2 and Zircaloy-4 and Correlation to Nodular Corrosion Behavior
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 307
–320
.48.
Andersson
, T.
and Thorvaldsson
, T.
, “Nodular Corrosion Resistance of Zircaloy-2 in Relation to Second-Phase Particle Distribution
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 321
–337
.49.
Bangaru
, N. V.
, Busch
, R. A.
, and Schemel
, J. H.
, “Effect of Beta Quenching on the Microstructure and Corrosion of Zircaloys
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 341
–363
.50.
Weidinger
, H. G.
, Garzarolli
, F.
, Euchen
, C. M.
, and Baroch
, E. F.
, “Effect of Chemistry on Elevated Temperature Nodular Corrosion
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 364
–386
.51.
Garzarolli
, F.
, Stehle
, H.
, Steinberg
, E.
, and Weidinger
, H.
, “Progress in the Knowledge of Nodular Corrosion
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 417
–430
.52.
Ogata
, K.
, “Effects of Alloying Element Distribution on the Nodular Corrosion of Zircaloy-2
,” Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
, L. F. R.
Van Swam
and C. M.
Eucken
, Eds., June 19–23, 1988, San Diego, CA, ASTM International, West Conshohocken, PA, 1989
, pp. 346
–359
.53.
Cox
, B.
, “Oxidation of Zirconium and Its Alloys
,” Advances in Corrosion Science and Technology
, Plenum Press
, New York
, 1976
.54.
Zhou
, B.
, “Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated Steam
,” Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
, L. F. R.
Van Swam
and C. M.
Eucken
, Eds., June 19–23, 1988, San Diego, CA, ASTM International, West Conshohocken, PA, 1989
, pp. 360
–373
.55.
Bibb
, A. E.
and Faxcia
, J. R.
, “Aqueous Corrosion of Zirconium Single Crystals
,” KAPL-2257, Knolls Atomic Power Laboratory, Schenectady, NY, October 1962
.56.
Charquet
, D.
, Tricot
, R.
, and Wadier
, J.-F.
, “Heterogeneous Scale Growth During Steam Corrosion of Zircaloy-4 and 500°C
,” Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
, L. F. R.
Van Swam
and C. M.
Eucken
, Eds., ASTM International, West Conshohocken, PA, 1989
, pp. 374
–391
.57.
Cox
, B.
, “Rate Controlling Processes During the Pre-Transition Oxidation of Zirconium Alloys
,” J. Nucl. Mater.
0022-3115, Vol. 31
, 1969
, pp. 48
–66
. https://doi.org/10.1016/0022-3115(69)90043-958.
Urquhart
, A. W.
and Vermilyea
, D. A.
, “Characterization of Zircaloy Oxidation Films
,” Zirconium in the Nuclear Industry: ASTM STP 551
, ASTM International
, West Conshohocken, PA
, 1974
, pp. 463
–478
.59.
International Atomic Energy Agency,
1993
, “Corrosion of Zirconium Alloys in Nuclear Power Plants
,” IAEA-TECDOC-684,Vienna, Austria.60.
Cowan
, R. L.
, “BWR Water Chemistry…a Delicate Balance
,” Water Chemistry of Nuclear Reactor Systems 8
, British Nuclear Engineering Society
, London, England
, 2000
, pp. 97
–102
.61.
Hettiarachchi
, S.
, Law
, R. J.
, Diaz
, T. P.
, Miller
, W. D.
, Cowan
, R. L.
, Keith
, W.
, Kriege
, L.
, and Pathania
, R. S.
, “Application of Noble Metal Chemical Addition Technology to an Operating BWR to Mitigate IGSCC of Reactor Internals
,” CORROSION 98
, March 22-27, 1998 San Diego, CA, National Association of Corrosion Engineers, Houston, TX, 1998
, pp. 142/1–142/15.62.
Hettiarachchi
, S.
, Law
, R. J.
, Miller
, W. D.
, Diaz
, T. P.
, and Cowan
, R. L.
, “First Application of NOBLECHEM™ to an Operating BWR
,” Japan Atomic Industrial Forum Meeting
, Kashiwazaki, Japan, October 13-16, 1998, Japan Atomic Industrial Forum, Tokyo, Japan, 1998
.63.
Rishel
, D. M.
, Eklund
, K. L.
, and Kammenzind
, B. F.
, “In Situ EIS Measurements of Irradiated Zircaloy-4 Post-Transition Corrosion Kinetic Behavior
,” Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
, B.
Kammenzind
and M.
Limback
, Eds., June 24-28, 2007, Sun River, OR, ASTM International, West Conshohocken, PA, 2009
, pp. 326
–359
.64.
Ruiz
, C. P.
, Lin
, C. C.
, Robinson
, R. N.
, Burns
, W. G.
, Henshaw
, J.
, and Pathania
, R.
, “Model Calculations of Water Radiolysis and Electrochemical Potentials in BWR Primary Coolant II
,” Water Chemistry of Nuclear Reactor Systems 6
, BNES
, London
, 1992
, pp. 141
–152
.65.
Hurst
, P.
and Tyzack
, C.
, “The Effect of Environment on the In-Pile Corrosion and Hydrogen Pick-Up of Some Zirconium Alloys
,” Effects of Environment on Material Properties in Nuclear Systems
, Institution of Civil Engineers
, London
, 1971
, pp. 37
–49
.66.
Cheng
, B.
, Levin
, H. A.
, Adamson
, R. B.
, Marlowe
, M. O.
, and Monroe
, V. L.
, “Development of a Sensitive and Reproducible Steam Test for Zircaloy Nodular Corrosion
,” Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, R. B.
Adamson
and L. F. P.
Van Swam
, Eds., June 24-27, 1985, Strasbourg, France, ASTM International, West Conshohocken, PA, 1987
, pp. 257
–283
.67.
Greene
, C. A.
, Brossia
, C. S.
, Dunn
, D. S.
, and Cragnolino
, G. A.
, “Environmental and Electrochemical Factors on the Localized Corrosion of Zircaloy-4
,” Corrosion 2000
, March 26-31, 2000, Orlando, FL, National Association of Corrosion Engineers, Houston, TX, 2000
.68.
Brossia
, C. S.
, Cragnolino
, G. A.
, and Dunn
, D. S.
, “Effect of Oxide Thickness on the Localized Corrosion of Zircaloy
,” Corrosion 2002
, April 7–11, 2002, Denver, CO, National Association of Corrosion Engineers, Houston, TX, 2002
.69.
Maguire
, M.
, “The Pitting Susceptibility of Zirconium in Aqueous Cl-, Br-, and I-Solutions
,” ASTM STP 850
, ASTM International
, West Conshohocken, PA
, 1984
, pp. 175
–189
.70.
Andresen
, P. L.
, “Mitigation of Stress Corrosion Cracking by Underwater Thermal Spray Coating of Noble Metals
,” CORROSION 95
, March 26–31, 1995 Orlando, FL, National Association of Corrosion Engineers, Houston, TX, 1995
, pp. 412/1–412/30.71.
Beie
, H.-J.
, Mitwalsky
, A.
, Garzarolli
, F.
, Ruhmann
, H.
, and Sell
, H.-J.
, “Examinations of the Corrosion Mechanism of Zirconium Alloys
,” Zirconium in the Nuclear Industry: 10th International Symposium, ASTM STP 1245
, A. M.
Garde
and E. R.
Bradley
, Eds., June 21–24, 1993, Baltimore, MD, ASTM International, West Conshohocken, PA, 1994
, pp. 615
–643
.72.
Taylor
, D. F.
, “An Oxide-Semiconductance Model of Nodular Corrosion and Its Application to Zirconium Alloy Development
,” J. Nucl. Mater.
0022-3115, Vol. 184
, 1991
, pp. 65
–77
. https://doi.org/10.1016/0022-3115(91)90534-E73.
Harding
, J. H.
, “The Effect of Alloying Elements on Zircaloy Corrosion
,” J. Nucl. Mater.
0022-3115, Vol. 202
, 1993
, pp. 216
–221
. https://doi.org/10.1016/0022-3115(93)90390-K74.
Iltis
, X.
, Viennot
, M.
, David
, D.
, Hertz
, D.
, and Michel
, H.
, “Special Kinetic and Microstructural Features Associated with Zircaloy-4 Oxidation Between 520 and 620 K in the Post-Discharge of an Argon-Oxygen Microwave Discharge
,” J. Nucl. Mater.
0022-3115, Vol. 209
, 1994
, pp. 180
–190
. https://doi.org/10.1016/0022-3115(94)90294-175.
Petrik
, N. G.
, Alexandrov
, A. B.
, and Vall
, A. I.
, “Interfacial Energy Transfer During Gamma Radiolysis of Water on the Surface of ZrO2 and Some Other Oxides
,” J. Phys. Chem. B
1089-5647, Vol. 105
, 2001
, pp. 5935
–5944
. https://doi.org/10.1021/jp004440o76.
Beie
, H.-J.
, Mitwalsky
, A.
, Garzarolli
, F.
, Ruhmann
, H.
, and Sell
, H.-J.
, “Examinations of the Corrosion Mechanism of Zirconium Alloys
,” Zirconium in the Nuclear Industry: 10th International Symposium, ASTM STP 1245
, A. M.
Garde
and E. R.
Bradley
, Eds., ASTM International, West Conshohocken, PA, 1994
, pp. 6615
–6643
.77.
Anghel
, C.
, Hulquist
, G.
, Limback
, M.
, and Szakalos
, P.
, “Effects of Pt Surface Coverage on Oxidation of Zr and Other Materials
,” Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
, B.
Kammenzind
and M.
Limback
, Eds., June 21–24, 1993, Baltimore, MD, ASTM International, West Conshohocken, PA, 2009
, pp. 285
–302
.
This content is only available via PDF.
All rights reserved. This material may not be reproduced or copied, in whole or in part, in any printed, mechanical, electronic, film, or other distribution and storage media, without the written consent of ASTM International.
You do not currently have access to this content.
