-
1
-
-
32144439766
-
Transmission electron microscopy examination of oxide layer formed on Zr alloys
-
Yilmazbayhan, A., Breval, E., Motta, A. T. and Comstock, R. J., "Transmission Electron Microscopy Examination of Oxide Layer Formed on Zr Alloys," J. Nucl. Mater., Vol.349, 2006, pp. 265-281.
-
(2006)
J. Nucl. Mater.
, vol.349
, pp. 265-281
-
-
Yilmazbayhan, A.1
Breval, E.2
Motta, A.T.3
Comstock, R.J.4
-
2
-
-
0030289361
-
Microstructure of oxides on Zircaloy-4, 1.0Nb Zircaloy-4 and Zircaloy-2 formed in 10.3-MPa steam at 673K
-
ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM Interna-tional, West Conshohocken, PA.
-
Anada, H. and Takeda, K., "Microstructure of Oxides on Zircaloy-4, 1.0Nb Zircaloy-4 and Zircaloy-2 Formed in 10.3-MPa Steam at 673K," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM Interna-tional, West Conshohocken, PA., 1996, pp. 35-54.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium
, pp. 35-54
-
-
Anada, H.1
Takeda, K.2
-
3
-
-
0026371569
-
Oxide growth mechanism on zirconium alloys
-
ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., ASTM International, 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 International Symposium, ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., ASTM International, West Conshohocken, PA, 1991, pp. 395-415.
-
(1991)
Zirconium in the Nuclear Industry: Ninth International Symposium
, pp. 395-415
-
-
Garzarolli, F.1
Seidel, H.2
Tricot, R.3
Gros, J.P.4
-
4
-
-
0030289887
-
Microstructure of oxide films formed during the waterside corrosion of the Zircaloy-4 cladding in lithiated environment
-
ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM International, West Conshohocken, PA
-
Pêcheur, D., Goldlewski, J., Billot, P. 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., ASTM International, West Conshohocken, PA, 1996, pp. 94-113.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium
, pp. 94-113
-
-
Pêcheur, D.1
Goldlewski, J.2
Billot, P.3
Thomazet, J.4
-
5
-
-
0000256403
-
Microstructure of oxide layers formed during autoclave testing of zirconium alloys
-
ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., ASTM International, 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 International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., ASTM International, West Conshohocken, PA, 1994, pp. 579-598.
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium
, pp. 579-598
-
-
Wadman, B.1
Lai, Z.2
Andren, H.-O.3
Nystrom, A.-L.4
Rudling, P.5
Pettersson, H.6
-
6
-
-
0000915131
-
Examinations of the corrosion mechanism of zirconium alloys
-
ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., ASTM International, West Conshohocken, PA
-
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: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., ASTM International, West Conshohocken, PA, 1994, pp. 615-643.
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium
, pp. 615-643
-
-
Beie, H.-J.1
Mitwalsky, A.2
Garzarolli, F.3
Ruhmann, H.4
Sell, H.-J.5
-
7
-
-
0035398807
-
Characterization of pre-transition oxides on zircaloys
-
Oskarsson, M., Ahlberg, E., Andersson, U. and Pettersson, K., "Characterization of Pre-Transition Oxides on Zircaloys," J. Nucl. Mater., Vol.297, 2001, pp. 77-88.
-
(2001)
J. Nucl. Mater.
, vol.297
, pp. 77-88
-
-
Oskarsson, M.1
Ahlberg, E.2
Andersson, U.3
Pettersson, K.4
-
8
-
-
1442359475
-
Effect of isothermal annealing on the corrosion behavior of Zr-xNb alloys
-
Kim, H. G., Jeong, Y. H. and Kim, T. H., "Effect of Isothermal Annealing on the Corrosion Behavior of Zr-xNb Alloys," J. Nucl. Mater., Vol.326, 2004, pp. 125-131.
-
(2004)
J. Nucl. Mater.
, vol.326
, pp. 125-131
-
-
Kim, H.G.1
Jeong, Y.H.2
Kim, T.H.3
-
9
-
-
4344563786
-
Electron microscopy study of oxide films formed on Zircaloy-2 in superheated steam
-
ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken Eds., ASTM International, West Conshohocken, PA ASTM STP 1023
-
Zhou, B.-X., "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. P. Van Swam and C. M. Eucken Eds., ASTM International, West Conshohocken, PA, 1989, pp. 360-373.
-
(1989)
Zirconium in the Nuclear Industry: Eighth International Symposium
, pp. 360-373
-
-
Zhou, B.-X.1
-
10
-
-
0006240813
-
The effect of water chemistry on the corrosion behavior of zirconium alloys
-
Chinese
-
Zhou, B.-X., Li, Q., Huang, Q., Miao, Z., Zhao, W.-J. and Li, C., "The Effect of Water Chemistry on the Corrosion Behavior of Zirconium Alloys," Nuclear Power Engineering, Vol.21, 2000, pp. 439-447 (in Chinese).
-
(2000)
Nuclear Power Engineering
, vol.21
, pp. 439-447
-
-
Zhou, B.-X.1
Li, Q.2
Huang, Q.3
Miao, Z.4
Zhao, W.-J.5
Li, C.6
-
11
-
-
12444276723
-
Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys
-
DOI 10.1016/j.jnucmat.2004.09.029, PII S002231150400875X
-
[11] Cox, B., "Some Thoughts on the Mechanisms of In-Reactor Corrosion of Zirconium Alloys," J. Nucl. Mater., Vol.336, 2005, pp. 331-368. (Pubitemid 40141825)
-
(2005)
Journal of Nuclear Materials
, vol.336
, Issue.2-3
, pp. 331-368
-
-
Cox, B.1
-
12
-
-
0004214749
-
-
IAEA-TECDOC-996, IAEA, Vienna, ISSN 1011-4289, Jan. 1998.
-
IAEA-TECDOC-996, "Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants," IAEA, Vienna, 1998, ISSN 1011-4289, Jan. 1998.
-
(1998)
Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants
-
-
-
13
-
-
26944500578
-
Microstructure evolution of oxide films formed on Zircaloy-4 during autoclave tests
-
Chinese
-
Zhou, B.-X., Li, Q., Yao, M.-Y. and Liu, W.-Q., "Microstructure Evolution of Oxide Films Formed on Zircaloy-4 during Autoclave Tests," Nuclear Power Engineering, Vol.26, 2005, pp. 364-371 (in Chinese).
-
(2005)
Nuclear Power Engineering
, vol.26
, pp. 364-371
-
-
Zhou, B.-X.1
Li, Q.2
Yao, M.-Y.3
Liu, W.-Q.4
-
14
-
-
33748164374
-
Effects of water chemistry and composition on the microstructure evolution of oxide films on zirconium alloys during autoclave tests
-
[14] Zhou, B.-X., Li, Q., Liu, W.-Q., Yao, M.-Y. and Zhu, Y.-L., "The Effect of Water Chemistry and Composition on the Microstructure Evolution of Oxide Films on Zirconium Alloys," Rare Metal Materials and Engineering, Vol.35, 2006, pp. 1009-1016. (in Chinese). (Pubitemid 44313344)
-
(2006)
Xiyou Jinshu Cailiao Yu Gongcheng/Rare Metal Materials and Engineering
, vol.35
, Issue.7
, pp. 1009-1016
-
-
Zhou, B.1
Li, Q.2
Liu, W.3
Yao, M.4
Chu, Y.5
-
15
-
-
18444402688
-
A porosimeter for determining the size of flaws in zirconia or other insulating films
-
Cox, B., "A Porosimeter for Determining the Size of Flaws in Zirconia or Other Insulating Films," J. Nucl. Mater., Vol.27, 1968, pp. 1-11.
-
(1968)
J. Nucl. Mater.
, vol.27
, pp. 1-11
-
-
Cox, B.1
-
16
-
-
0009644849
-
Processes occurring during the breakdown of oxide films on zirconium alloys
-
Cox, B., "Processes Occurring During the Breakdown of Oxide Films on Zirconium Alloys," J. Nucl. Mater., Vol.29, 1969, pp. 50-66.
-
(1969)
J. Nucl. Mater.
, vol.29
, pp. 50-66
-
-
Cox, B.1
-
17
-
-
0042164664
-
The grains morphology of oxide films for Zircaloy-4
-
[17] Zhou, B.-X., Li, Q., Yao, M.-Y. et al., "The Grain Morphology of Oxide Films on Zircaloy-4," Rare Metal Materials and Engineering, Vol.32, 2003, pp. 417-419 (in Chinese). (Pubitemid 41268152)
-
(2003)
Xiyou Jinshu Cailiao Yu Gongcheng/Rare Metal Materials and Engineering
, vol.32
, Issue.6
, pp. 417-419
-
-
Zhou, B.1
Li, Q.2
Yao, M.3
Liu, W.4
-
18
-
-
0018480171
-
The Cyclic Nature of Corrosion of Zircaloy-4 in 633K, Water
-
Bryner, J. S., "The Cyclic Nature of Corrosion of Zircaloy-4 in 633K, Water," J. Nucl. Mater., Vol.82, 1979, pp. 84-101.
-
(1979)
J. Nucl. Mater.
, vol.82
, pp. 84-101
-
-
Bryner, J.S.1
-
19
-
-
0006320698
-
In-reactor corrosion performance of zirlo and zircaloy-4
-
ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., ASTM International, West Conshohocken, PA
-
Sabol, G. P., Costock, R. J., Weiner, R. A., Larouere, P. and Stanutz, R. N., "In-Reactor Corrosion Performance of ZIRLO and Zircaloy-4," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., ASTM International, West Conshohocken, PA, 1994, pp. 724-744.
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium
, pp. 724-744
-
-
Sabol, G.P.1
Costock, R.J.2
Weiner, R.A.3
Larouere, P.4
Stanutz, R.N.5
-
20
-
-
76649096600
-
Oxidation of zircaloy-2 in air from 500°c to 800°c, high temperature corrosion and protection
-
26-30 June 1990, Shenyang, China, H.-R. Guan, W.-T. Wu, J.-N. Shen and T.-F. Li, Eds., Liaoning Science and Technology Publishing House, China
-
Zhou, B.-X. and Jiang, Y.-R., "Oxidation of Zircaloy-2 in Air from 500°C to 800°C, High Temperature Corrosion and Protection," Proceedings of the International Symposium on High Temperature Corrosion and Protection, 26-30 June 1990, Shenyang, China, H.-R. Guan, W.-T. Wu, J.-N. Shen and T.-F. Li, Eds., Liaoning Science and Technology Publishing House, China, 1991, pp. 121-124.
-
(1991)
Proceedings of the International Symposium on High Temperature Corrosion and Protection
, pp. 121-124
-
-
Zhou, B.-X.1
Jiang, Y.-R.2
-
21
-
-
0343090847
-
Contribution to the understanding of the effect of the water chemistry on the oxidation kinetics of zircaloy-4 cladding
-
ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., ASTM International, West Conshohocken, PA
-
Pêcheur, D., Godlewski, J., Peybernes, J., Faytte, L., Noe, M., Frichet, A. and Kerrec, O., "Contribution to the Understanding of the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., ASTM International, West Conshohocken, PA, 2000, pp. 793-811.
-
(2000)
Zirconium in the Nuclear Industry: Twelfth International Symposium
, pp. 793-811
-
-
Pêcheur, D.1
Godlewski, J.2
Peybernes, J.3
Faytte, L.4
Noe, M.5
Frichet, A.6
Kerrec, O.7
-
22
-
-
0343442636
-
Lithium uptake and the accelerated corrosion of zirconium alloys
-
ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., ASTM International, West Conshohocken, PA
-
Ramasubramania, N., Precoanin, N. and Ling, V. C., "Lithium Uptake and the Accelerated Corrosion of Zirconium Alloys," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds., ASTM International, West Conshohocken, PA, 1989, pp. 187-201.
-
(1989)
Zirconium in the Nuclear Industry: Eighth International Symposium
, pp. 187-201
-
-
Ramasubramania, N.1
Precoanin, N.2
Ling, V.C.3
-
23
-
-
0033316520
-
Cation incorporation into zirconium oxide in lioh, naoh, and KOH solutions
-
Jeong, Y. H., Kim, K. H. and Baek, J. H., "Cation Incorporation into Zirconium Oxide in LiOH, NaOH, and KOH Solutions," J. Nucl. Mater., Vol.275, 1999, pp. 221-224.
-
(1999)
J. Nucl. Mater.
, vol.275
, pp. 221-224
-
-
Jeong, Y.H.1
Kim, K.H.2
Baek, J.H.3
-
24
-
-
0035336756
-
Oxidation of zircaloy-2 and zircaloy-4 in water and lithiated water at 360 °c
-
Oskarsson, M., Ahlberg, E. and Pettersson, K., "Oxidation of Zircaloy-2 and Zircaloy-4 in Water and Lithiated Water at 360 °C," J. Nucl. Mater., Vol.295, 2001, pp. 97-108.
-
(2001)
J. Nucl. Mater.
, vol.295
, pp. 97-108
-
-
Oskarsson, M.1
Ahlberg, E.2
Pettersson, K.3
-
25
-
-
4344693883
-
Mechanism of LIOH aqueous solution accelerating corrosion rate of zircaloy-4
-
Chinese
-
Zhou, B.-X., Liu, W.-Q., Li, Q. and Yao, M.-Y., "Mechanism of LiOH Aqueous Solution Accelerating Corrosion Rate of Zircaloy-4," Chinese Journal of Materials Research, Vol.18, 2004, pp. 225-231 (in Chinese).
-
(2004)
Chinese Journal of Materials Research
, vol.18
, pp. 225-231
-
-
Zhou, B.-X.1
Liu, W.-Q.2
Li, Q.3
Yao, M.-Y.4
-
26
-
-
0345016313
-
Structure of zirconium alloy oxides formed in prre water studied with synchrotron radiation and optical microscopy: Relation to corrosion rate
-
Yilmazbayhan, A., Motta, A. T., Comstock, R. J., Sabol, G. P., Laiq, B. and Cai, Z. H., "Structure of Zirconium Alloy Oxides Formed in Prre Water Studied with Synchrotron Radiation and Optical Microscopy: Relation to Corrosion Rate," J. Nucl. Mater., Vol.324, 2004, pp. 6-22.
-
(2004)
J. Nucl. Mater.
, vol.324
, pp. 6-22
-
-
Yilmazbayhan, A.1
Motta, A.T.2
Comstock, R.J.3
Sabol, G.P.4
Laiq, B.5
Cai, Z.H.6
-
27
-
-
0142072057
-
The Cyclic nature of corrosion of Zr and Zr-Sn in high-temperature water (633k), a long-term in situ impedance spectroscopic study
-
Schefold, J., Lincot, D., Ambard, A. and Kerrec, O., "The Cyclic Nature of Corrosion of Zr and Zr-Sn in High-Temperature Water (633K), A Long-Term in situ Impedance Spectroscopic Study," J. Electrochem. Soc., Vol.150, 2003, pp. B451-B461.
-
(2003)
J. Electrochem. Soc.
, vol.150
-
-
Schefold, J.1
Lincot, D.2
Ambard, A.3
Kerrec, O.4
-
28
-
-
38749118962
-
A superior corrosion behavior of zircaloy-4 in lithiated water at 360°c/18.6 mpa by β-quenching
-
to be published.
-
Yao, M.-Y., Zhou, B.-X., Li, Q., Chu, Y.-L., Liu, W.-Q. and Lu, Y.-P., "A Superior Corrosion Behavior of Zircaloy-4 in Lithiated Water at 360°C/18.6 MPa by β-Quenching," J. Nucl. Mater. (to be published).
-
J. Nucl. Mater.
-
-
Yao, M.-Y.1
Zhou, B.-X.2
Li, Q.3
Chu, Y.-L.4
Liu, W.-Q.5
Lu, Y.-P.6
-
29
-
-
0037805752
-
The effect of microstructure on the corrosion behavior for ZIRLO alloy
-
Chinese.
-
Liu, W.-Q., Li, Q., Zhou, B.-X. and Yao, M.-Y., "The Effect of Microstructure on the Corrosion Behavior for ZIRLO Alloy," Nuclear Power Engineering, Vol.24, 2003, pp. 33-36. (in Chinese).
-
(2003)
Nuclear Power Engineering
, vol.24
, pp. 33-36
-
-
Liu, W.-Q.1
Li, Q.2
Zhou, B.-X.3
Yao, M.-Y.4
-
30
-
-
0348236941
-
Effect of deformation and heat treatment on the decomposition of β-Zr in Zr-Sn-Nb alloys
-
Chinese.
-
Li, Q., Liu, W.-Q. and Zhou, B.-X., "Effect of Deformation and Heat Treatment on the Decomposition of β-Zr in Zr-Sn-Nb Alloys," Rare Metal Materials and Engineering, Vol.31, 2002, pp. 389-392 (in Chinese).
-
(2002)
Rare Metal Materials and Engineering
, vol.31
, pp. 389-392
-
-
Li, Q.1
Liu, W.-Q.2
Zhou, B.-X.3
-
31
-
-
0030287903
-
Influence of processing variables and alloy chemistry on the corrosion behavior of ZIRLO nuclear fuel cladding
-
ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM International, West Conshohocken, PA
-
Comstock, R. J., Schoenberger, G. and Sabol, G. P., "Influence of Processing Variables and Alloy Chemistry on the Corrosion Behavior of ZIRLO Nuclear Fuel Cladding," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM International, West Conshohocken, PA, 1996, pp. 710-725.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium
, pp. 710-725
-
-
Comstock, R.J.1
Schoenberger, G.2
Sabol, G.P.3
|