-
2
-
-
33744816490
-
ZIRLO™ - An alloy development success
-
Rudling P, Kammenzind B, editors ASTM STP 1467. West Conshohocken, PA: ASTM International
-
Sabol GP. ZIRLO™ - An alloy development success. In: Rudling P, Kammenzind B, editors. Zirconium in the nuclear industry: fourteenth international symposium, ASTM STP 1467. West Conshohocken, PA: ASTM International; 2005.
-
(2005)
Zirconium in the Nuclear Industry: Fourteenth International Symposium
-
-
Sabol, G.P.1
-
3
-
-
0000882280
-
Oxidation of zirconium and its alloys
-
M.G. Fontana, R.W. Staehle, Plenum New York
-
B. Cox Oxidation of zirconium and its alloys M.G. Fontana, R.W. Staehle, Advances in corrosion science and technology 1976 Plenum New York
-
(1976)
Advances in Corrosion Science and Technology
-
-
Cox, B.1
-
4
-
-
80052559162
-
Zirconium alloy performance in light water reactors: A review of UK and Scandinavian experience
-
Garde AM, Bradley ER, editors West Conshohocken, PA: ASTM International
-
Pickman DO. Zirconium alloy performance in light water reactors: a review of UK and Scandinavian experience. In: Garde AM, Bradley ER, editors. Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245. West Conshohocken, PA: ASTM International; 1994.
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
-
-
Pickman, D.O.1
-
7
-
-
0000915131
-
Examinations of the corrosion mechanism of zirconium alloys
-
A.M. Garde, E.R. Bradley, ASTM International West Conshohocken, PA
-
H.-J. Beie, A. Mitwalsky, F. Garzarolli, H. Ruhmann, and H.-J. Sell Examinations of the corrosion mechanism of zirconium alloys A.M. Garde, E.R. Bradley, Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245 1994 ASTM International West Conshohocken, PA
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
-
-
Beie, H.-J.1
Mitwalsky, A.2
Garzarolli, F.3
Ruhmann, H.4
Sell, H.-J.5
-
9
-
-
84868202448
-
-
13C corrosion: environments and industries
-
Lemaignan C. ASM handbook 2006; 13C corrosion: environments and industries; 2006. p. 415.
-
(2006)
ASM Handbook 2006
, pp. 415
-
-
Lemaignan, C.1
-
12
-
-
0035575804
-
-
H.I. Yoo, B.J. Koo, J.O. Hong, I.S. Hwang, and Y.H. Jeong J Nucl Mater 299 2001 235
-
(2001)
J Nucl Mater
, vol.299
, pp. 235
-
-
Yoo, H.I.1
Koo, B.J.2
Hong, J.O.3
Hwang, I.S.4
Jeong, Y.H.5
-
18
-
-
70450252204
-
-
M. Steinbruck, J. Birchley, A.V. Boldyrev, A.V. Goryachev, M. Grosse, and T.J. Haste Prog Nucl Energy 52 2010 19
-
(2010)
Prog Nucl Energy
, vol.52
, pp. 19
-
-
Steinbruck, M.1
Birchley, J.2
Boldyrev, A.V.3
Goryachev, A.V.4
Grosse, M.5
Haste, T.J.6
-
20
-
-
0030563158
-
-
A.J.G. Maroto, R. Bordoni, M. Villegas, A.M. Olmedo, M.A. Blesa, and A. Iglesias J Nucl Mater 229 1996 79
-
(1996)
J Nucl Mater
, vol.229
, pp. 79
-
-
Maroto, A.J.G.1
Bordoni, R.2
Villegas, M.3
Olmedo, A.M.4
Blesa, M.A.5
Iglesias, A.6
-
24
-
-
33744914993
-
Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiation
-
P. Rudling, B. Kammenzind, ASTM International West Conshohocken, PA
-
A.T. Motta, A. Yilmazbayhan, R.J. Comstock, J. Partezana, G.P. Sabol, and B. Lai Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiation P. Rudling, B. Kammenzind, Zirconium in the nuclear industry: fourteenth international symposium, ASTM STP 1467 2004 ASTM International West Conshohocken, PA
-
(2004)
Zirconium in the Nuclear Industry: Fourteenth International Symposium, ASTM STP 1467
-
-
Motta, A.T.1
Yilmazbayhan, A.2
Comstock, R.J.3
Partezana, J.4
Sabol, G.P.5
Lai, B.6
-
28
-
-
0345016313
-
-
A. Yilmazbayhan, A.T. Motta, R.J. Comstock, G.P. Sabol, B. Lai, and Z.H. Cai J Nucl Mater 324 2004 6
-
(2004)
J Nucl Mater
, vol.324
, pp. 6
-
-
Yilmazbayhan, A.1
Motta, A.T.2
Comstock, R.J.3
Sabol, G.P.4
Lai, B.5
Cai, Z.H.6
-
29
-
-
0030285164
-
Long-term in situ corrosion investigation of Zr alloys in simulated PWR environment by electrochemical measurements
-
E.R. Bradley, G.P. Sabol, ASTM International West Conshohocken, PA
-
H. Göhr, J. Schaller, H. Ruhmann, and F. Garzarolli Long-term in situ corrosion investigation of Zr alloys in simulated PWR environment by electrochemical measurements E.R. Bradley, G.P. Sabol, Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295 1996 ASTM International West Conshohocken, PA
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
-
-
Göhr, H.1
Schaller, J.2
Ruhmann, H.3
Garzarolli, F.4
-
30
-
-
80053452155
-
-
N. Ni, S. Lozano-Perez, J.M. Sykes, G.D.W. Smith, and C.R.M. Grovenor Corros Sci 53 2011 4073
-
(2011)
Corros Sci
, vol.53
, pp. 4073
-
-
Ni, N.1
Lozano-Perez, S.2
Sykes, J.M.3
Smith, G.D.W.4
Grovenor, C.R.M.5
-
31
-
-
0035276358
-
-
M. Oskarsson, E. Ahlberg, U. Sodervall, U. Andersson, and K. Pettersson J Nucl Mater 289 2001 315
-
(2001)
J Nucl Mater
, vol.289
, pp. 315
-
-
Oskarsson, M.1
Ahlberg, E.2
Sodervall, U.3
Andersson, U.4
Pettersson, K.5
-
33
-
-
38749118962
-
-
M.Y. Yao, B.X. Zhou, Q. Li, W.Q. Liu, X. Geng, and Y.P. Lu J Nucl Mater 374 2008 197
-
(2008)
J Nucl Mater
, vol.374
, pp. 197
-
-
Yao, M.Y.1
Zhou, B.X.2
Li, Q.3
Liu, W.Q.4
Geng, X.5
Lu, Y.P.6
-
34
-
-
0030289887
-
Microstructure of oxide films formed during the waterside corrosion of the Zircaloy-4 cladding in lithiated environment
-
E.R. Bradley, G.P. Sabol, ASTM International West Conshohocken, PA
-
D. Pêcheur, J. Godlewski, P. Billot, and J. Thomazet Microstructure of oxide films formed during the waterside corrosion of the Zircaloy-4 cladding in lithiated environment E.R. Bradley, G.P. Sabol, Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295 1996 ASTM International West Conshohocken, PA
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
-
-
Pêcheur, D.1
Godlewski, J.2
Billot, P.3
Thomazet, J.4
-
35
-
-
0026371569
-
Oxide growth mechanism on zirconium alloys
-
C.M. Eucken, A.M. Garde, ASTM International West Conshohocken, PA
-
F. Garzarolli, H. Stehle, R. Tricot, and J.P. Gros Oxide growth mechanism on zirconium alloys C.M. Eucken, A.M. Garde, Zirconium in the nuclear industry: ninth international symposium, ASTM STP 1132 1990 ASTM International West Conshohocken, PA
-
(1990)
Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132
-
-
Garzarolli, F.1
Stehle, H.2
Tricot, R.3
Gros, J.P.4
-
36
-
-
0030289361
-
Microstructure of oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 formed in 10.3-MPa steam at 673 K
-
Bradley ER, Sabol GP, editors West Conshohocken, PA: ASTM International
-
Anada H, Takeda K. Microstructure of oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 formed in 10.3-MPa steam at 673 K. In: Bradley ER, Sabol GP, editors. Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295. West Conshohocken, PA: ASTM International; 1996.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
-
-
Anada, H.1
Takeda, K.2
-
37
-
-
8844221532
-
The microstructural characterization of factors which determin the degradation behaviour of Zircaloy-4
-
S.B. Newcomb, J.A. Little, Henry Ling Dorest
-
D.T. Foord, and S.B. Newcomb The microstructural characterization of factors which determin the degradation behaviour of Zircaloy-4 S.B. Newcomb, J.A. Little, Microscopy of oxidation 3 1996 Henry Ling Dorest
-
(1996)
Microscopy of Oxidation 3
-
-
Foord, D.T.1
Newcomb, S.B.2
-
38
-
-
0027573841
-
-
B. Wadman, H.O. Andren, A.L. Nystrom, P. Rudling, and H. Pettersson J Nucl Mater 200 1993 207
-
(1993)
J Nucl Mater
, vol.200
, pp. 207
-
-
Wadman, B.1
Andren, H.O.2
Nystrom, A.L.3
Rudling, P.4
Pettersson, H.5
-
42
-
-
33744933196
-
Comparison of the high burn-up corrosion on M5 and low tin Zircaloy-4
-
P. Rudling, B. Kammenzind, ASTM International West Conshohocken, PA
-
P. Bossis, D. Pecheur, K. Hanifi, J. Thomazet, and M. Blat Comparison of the high burn-up corrosion on M5 and low tin Zircaloy-4 P. Rudling, B. Kammenzind, Zirconium in the nuclear industry: fourteenth international symposium, ASTM STP 1467 2005 ASTM International West Conshohocken, PA
-
(2005)
Zirconium in the Nuclear Industry: Fourteenth International Symposium, ASTM STP 1467
-
-
Bossis, P.1
Pecheur, D.2
Hanifi, K.3
Thomazet, J.4
Blat, M.5
-
43
-
-
0032673284
-
-
Y.H. Jeong, J.H. Baek, S.J. Kim, H.G. Kim, and H. Ruhmann J Nucl Mater 270 1999 322
-
(1999)
J Nucl Mater
, vol.270
, pp. 322
-
-
Jeong, Y.H.1
Baek, J.H.2
Kim, S.J.3
Kim, H.G.4
Ruhmann, H.5
-
44
-
-
33744786260
-
TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor
-
P. Rudling, B. Kammenzind, ASTM International West Conshohocken, PA
-
S. Abolhassani, R. Restani, T. Rebac, F. Groeschel, W. Hoffelner, and G. Bart TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor P. Rudling, B. Kammenzind, Zirconium in the nuclear industry: fourteenth international symposium, ASTM STP 1467 2005 ASTM International West Conshohocken, PA
-
(2005)
Zirconium in the Nuclear Industry: Fourteenth International Symposium, ASTM STP 1467
-
-
Abolhassani, S.1
Restani, R.2
Rebac, T.3
Groeschel, F.4
Hoffelner, W.5
Bart, G.6
-
45
-
-
0000256403
-
Microstructure of oxide layers formed during autoclave testing of zirconium alloys, ASTM STP 1245
-
A.M. Garde, E.R. Bradley, ASTM International West Conshohocken, PA
-
B. Wadman, Z. Lai, H.-O. Nystrom, L.-A. Nyström, P. Rudling, and H. Pettersson Microstructure of oxide layers formed during autoclave testing of zirconium alloys, ASTM STP 1245 A.M. Garde, E.R. Bradley, Zirconium in the nuclear industry: tenth international symposium 1994 ASTM International West Conshohocken, PA
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium
-
-
Wadman, B.1
Lai, Z.2
Nystrom, H.-O.3
Nyström, L.-A.4
Rudling, P.5
Pettersson, H.6
-
47
-
-
0030285531
-
2 microstructure of Zircaloy-4 cladding tube
-
C.M. Eucken, A.M. Garde, ASTM International West Conshohocken, PA
-
2 microstructure of Zircaloy-4 cladding tube C.M. Eucken, A.M. Garde, Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295 1996 ASTM International West Conshohocken, PA
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
-
-
Anada, H.1
Herb, B.J.2
Nomoto, K.3
Hagi, S.4
Graham, R.A.5
Kuroda, T.6
-
50
-
-
73149088379
-
-
H.X. Zhang, D. Fruchart, E.K. Hlil, L. Ortega, Z.K. Li, and J.J. Zhang J Nucl Mater 396 2010 65
-
(2010)
J Nucl Mater
, vol.396
, pp. 65
-
-
Zhang, H.X.1
Fruchart, D.2
Hlil, E.K.3
Ortega, L.4
Li, Z.K.5
Zhang, J.J.6
-
51
-
-
0026381514
-
Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O18
-
C.M. Eucken, A.M. Garde, ASTM International West Conshohocken, PA
-
J. Godlewski, P. Gros, M. Lambertin, J.F. Wadier, and H. Weidinger Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O18 C.M. Eucken, A.M. Garde, Zirconium in the nuclear industry: ninth international symposium, ASTM STP 1132 1991 ASTM International West Conshohocken, PA
-
(1991)
Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132
-
-
Godlewski, J.1
Gros, P.2
Lambertin, M.3
Wadier, J.F.4
Weidinger, H.5
-
53
-
-
0000915132
-
How the tetragonal zirconia is stabilized in the oxide scale that if formed on a zirconium alloy corroded at 400°C in steam
-
A.M. Garde, E.R. Bradley, ASTM International West Conshohocken, PA
-
J. Godlewski How the tetragonal zirconia is stabilized in the oxide scale that if formed on a zirconium alloy corroded at 400°C in steam A.M. Garde, E.R. Bradley, Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245 1994 ASTM International West Conshohocken, PA
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
-
-
Godlewski, J.1
-
54
-
-
33749141878
-
Multi-scale characterization of the metal-oxide interface of zirconium alloys
-
G.P. Sabol, G.D. Moan, ASTM International West Conshohocken, PA
-
P. Bossis, G. Lelièvre, P. Barberis, X. Iltis, F. Lefebvre, and L. Thomas Multi-scale characterization of the metal-oxide interface of zirconium alloys G.P. Sabol, G.D. Moan, Zirconium in the nuclear industry: twelfth international symposium, ASTM STP 1354 2000 ASTM International West Conshohocken, PA
-
(2000)
Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354
-
-
Bossis, P.1
Lelièvre, G.2
Barberis, P.3
Iltis, X.4
Lefebvre, F.5
Thomas, L.6
-
55
-
-
0013134787
-
Precipitate behavior in Zircaloy-2 oxide-films and its relevance to corrosion-resistance
-
C.M. Eucken, A.M. Garde, ASTM International West Conshohocken, PA
-
T. Kubo, and M. Uno Precipitate behavior in Zircaloy-2 oxide-films and its relevance to corrosion-resistance C.M. Eucken, A.M. Garde, Zirconium in the nuclear industry: ninth international symposium, ASTM STP 1132 1990 ASTM International West Conshohocken, PA
-
(1990)
Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132
-
-
Kubo, T.1
Uno, M.2
-
56
-
-
76549136893
-
-
N. Ni, S. Lozano-Perez, M.L. Jenkins, C. English, G.D.W. Smith, and J.M. Sykes Scripta Mater 62 2010 564
-
(2010)
Scripta Mater
, vol.62
, pp. 564
-
-
Ni, N.1
Lozano-Perez, S.2
Jenkins, M.L.3
English, C.4
Smith, G.D.W.5
Sykes, J.M.6
-
62
-
-
0343254812
-
Oxide characteristics and corrosion and hydrogen uptake in Zr-2.5 Nb CANDU pressure tubes
-
Bradley ER, Sabol GP, editors West Conshohocken, PA: ASTM International
-
Warr BD, Heide PAWVD, Maruire MA. Oxide characteristics and corrosion and hydrogen uptake in Zr-2.5 Nb CANDU pressure tubes. In: Bradley ER, Sabol GP, editors. Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295. West Conshohocken, PA: ASTM International; 1996.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
-
-
Warr, B.D.1
Pawvd, H.2
Maruire, M.A.3
-
63
-
-
0030289408
-
The importance of oxide morphology for the oxidation rate of zirconium alloys
-
E.R. Bradley, G.P. Sabol, ASTM International West Conshohocken, PA
-
G. Wikmark, P. Rudling, B. Lehtinen, B. Hutchinson, A. Oscarsson, and E. Ahlberg The importance of oxide morphology for the oxidation rate of zirconium alloys E.R. Bradley, G.P. Sabol, Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295 1996 ASTM International West Conshohocken, PA
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
-
-
Wikmark, G.1
Rudling, P.2
Lehtinen, B.3
Hutchinson, B.4
Oscarsson, A.5
Ahlberg, E.6
-
64
-
-
0345521752
-
Investigation of in-pile grown corrosion films on zirconium-based alloys
-
E.R. Bradley, G.P. Sabol, ASTM International West Conshohocken, PA
-
O. Gebhardt, A. Hermann, G. Bart, H. Blank, F. Garzarolli, and I.L.F. Ray Investigation of in-pile grown corrosion films on zirconium-based alloys E.R. Bradley, G.P. Sabol, Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295 1996 ASTM International West Conshohocken, PA
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
-
-
Gebhardt, O.1
Hermann, A.2
Bart, G.3
Blank, H.4
Garzarolli, F.5
Ray, I.L.F.6
-
68
-
-
0026366364
-
Oxide characteristics and their relationship to hydrogen uptake in zirconium alloys
-
C.M. Eucken, A.M. Garde, ASTM International West Conshohocken, PA
-
B.D. Warr, M.B. Elmoselhi, S.B. Newcomb, N.S. McIntyre, A.M. Brennenstuhl, and P.C. Lichtenberger Oxide characteristics and their relationship to hydrogen uptake in zirconium alloys C.M. Eucken, A.M. Garde, Zirconium in the nuclear industry: ninth international symposium, ASTM STP 1132 1991 ASTM International West Conshohocken, PA
-
(1991)
Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132
-
-
Warr, B.D.1
Elmoselhi, M.B.2
Newcomb, S.B.3
McIntyre, N.S.4
Brennenstuhl, A.M.5
Lichtenberger, P.C.6
-
70
-
-
10644286254
-
Instabilities in the oxidation behaviour of Zircaloy-4
-
S.B. Newcomb, M.J. Bennett, The Institute of Materials London
-
D.T. Foord, and S.B. Newcomb Instabilities in the oxidation behaviour of Zircaloy-4 S.B. Newcomb, M.J. Bennett, Microscopy of oxidation-2 1993 The Institute of Materials London
-
(1993)
Microscopy of oxidation-2
-
-
Foord, D.T.1
Newcomb, S.B.2
-
79
-
-
0009915273
-
Corrosion behaviour of Zircaloy-4 sheets produced under various hot-rolling and annealing conditions
-
A.M. Garde, E.R. Bradley, American Society for Testing and Materials West Conshohocken, PA
-
H. Anada, K. Nomoto, and Y. Shida Corrosion behaviour of Zircaloy-4 sheets produced under various hot-rolling and annealing conditions A.M. Garde, E.R. Bradley, Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245 1994 American Society for Testing and Materials West Conshohocken, PA
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
-
-
Anada, H.1
Nomoto, K.2
Shida, Y.3
-
88
-
-
0037403649
-
-
M. Tupin, M. Pijolat, F. Valdivieso, M. Soustelle, A. Frichet, and P. Barberis J Nucl Mater 317 2003 130
-
(2003)
J Nucl Mater
, vol.317
, pp. 130
-
-
Tupin, M.1
Pijolat, M.2
Valdivieso, F.3
Soustelle, M.4
Frichet, A.5
Barberis, P.6
-
90
-
-
84861946484
-
Towards a mechanistic understanding of corrosion mechanisms in zirconium alloys
-
Chongqing, China. American Society for Testing and Materials
-
Preuss M, Frankel P, Lozano-Perez S, Hudson D, Polatidis E, Ni N, et al. Towards a mechanistic understanding of corrosion mechanisms in zirconium alloys. In: 16th International symposium on zirconium in the nuclear industry, Chongqing, China. American Society for Testing and Materials; 2010.
-
(2010)
16th International Symposium on Zirconium in the Nuclear Industry
-
-
Preuss, M.1
Frankel, P.2
Lozano-Perez, S.3
Hudson, D.4
Polatidis, E.5
Ni, N.6
|