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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry: Twelfth International Symposium
By
GP Sabol
GP Sabol
1
Westinghouse Electric Company
(retired)
Pittsburgh, PA Symposium Chair and STP Editor
.
Search for other works by this author on:
GD Moan
GD Moan
2
AECL
,
Mississauga, Ont.,
Canada
Editorial Chair and STP Editor
.
Search for other works by this author on:
ISBN-10:
0-8031-2499-6
ISBN:
978-0-8031-2499-8
No. of Pages:
968
Publisher:
ASTM International
Publication date:
2000

An historical review is given on the effects of neutron irradiation on the microstructure and properties of Zircaloy. Topics included are basic neutron damage structure, precipitate instabilities, irradiation growth, deformation and mechanical properties, and corrosion. A personal perspective is given by the author, and an extensive list of references covers the area.

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C.
and
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E. J.
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Voids in Irradiated Stainless Steel
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On the Question of Void Formation in Neutron Irradiated Zirconium
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,
C. D.
and
Ellis
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C. E.
, “
Influence of Niobium in Irradiation Strengthening of Dilute Zr-Nb Alloys
,”
Philosophical Magazine
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18
,
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Williams
,
C. D.
and
Gilbert
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Fast Neutron Damage in Zirconium-Based Structural Alloys
,”
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Microstructure of Irradiated and Tested Zircaloy-2
,”
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35
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and
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Irradiation Damage in Zircaloy-2 Produced by High-Dose Ion Bombardment
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50
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Lee
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Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys
,”
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American Society for Testing and Materials
,
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12.
Bell
,
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,
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13.
Adamson
,
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Irradiation Growth of Zircaloy
,”
Zirconium in the Nuclear Industry
, ASTM STP 633,
American Society for Testing and Materials
,
1977
, p. 326.
14.
Northwood
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and
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Some Comments on Damage Alignment in Neutron-Irradiated Zirconium Alloys
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,”
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, pp. 379–394.
17.
Gilbert
,
R. W.
,
Farrell
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, and
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C. E.
, “
Damage Structure in Zirconium Alloys Irradiated at 573K to 928K
,”
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, Vol.
84
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18.
Griffiths
,
M.
,
Mecke
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J. F.
, and
Winegar
,
J. E.
, “
Evolution of Microstructure in Zirconium Alloys During Irradiation
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
American Society for Testing and Materials
,
1996
, pp. 580–602.
19.
Adamson
,
R. B.
and
Bell
,
W. L.
, “
Effects of Neutron Irradiation and Oxygen Content on the Microstructure and Mechanical Properties of Zircaloy
,”
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Xian, China
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,
EMAS
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21.
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, and
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Effects of Boiling Water Reactor Irradiation on Tensile Properties of Zircaloy
,”
Proceedings
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Karlsruhe, Germany
,
12
1974
, pp. 189–192.
22.
Holt
,
R. A.
and
Gilbert
,
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, “
(c)-Component Dislocation in Neutron Irradiated Zircaloy-2
,”
Journal of Nuclear Materials
, Vol.
116
,
1983
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23.
Holt
,
R. A.
and
Gilbert
,
R. W.
, “
(c) Component Dislocations in Annealed Zircaloy Irradiated at About 570K
,”
Journal of Nuclear Materials
, Vol.
137
,
1986
, pp. 185–189.
24.
Griffiths
,
M.
and
Gilbert
,
R. W.
, “
The Formation of (c)-Component Defects in Zirconium Alloys during Neutron Irradiation
,”
Journal of Nuclear Materials
, Vol.
150
,
1987
, p. 169.
25.
Adamson
,
R. B.
,
Tucker
,
R. P.
, and
Fidleris
,
V.
, “
High Temperature Irradiation Growth in Zircaloy
,”
Zirconium in the Nuclear Industry
, ASTM STP 754,
American Society for Testing and Materials
,
1981
, pp. 208–234.
26.
Rogerson
,
A.
and
Murgatroyd
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R. A.
, “
‘Breakaway’ Growth in Annealed Zircaloy-2 at 353 K and 553 K
,”
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,
1983
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27.
Griffiths
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A Review of Microstructure Evolution in Zirconium Alloys
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28.
Cheng
,
B.
,
Adamson
,
R. B.
,
Bell
,
W. L.
, and
Proebstle
,
R. A.
, “
Corrosion Performance of Some Zirconium Alloys Irradiated in SGHWR
,”
Proceedings
, International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors,
Myrtle Beach, SC
,
1983
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29.
Gilbert
,
R. W
,
Griffiths
,
M.
, and
Carpenter
,
G. J. C.
, “
Amorphous Intermetallics in Neutron Irradiated Zircaloys after High Fluences
,”
Journal of Nuclear Materials
, Vol.
135
,
1985
, p. 265.
30.
Cheng
,
B.
and
Adamson
,
R. B.
, “
Mechanistic Studies of Zircaloy Nodular Corrosion
,”
Zirconium in the Nuclear Industry: Seventh International Symposium
, ASTM STP 939,
American Society for Testing and Materials
,
1987
, p. 387.
31.
Yang
,
W. J. S.
,
Tucker
,
R. P.
,
Cheng
,
B.
, and
Adamson
,
R. B.
, “
Precipitates in Zircaloy Identification and Effect of Irradiation
,”
Proceedings
, Workshop on Second Phase Particles and Matrix Properties of the Zircaloys,
Erlangen, FR Germany
,
07
1985
, pp. 85–100.
32.
Griffiths
,
M.
,
Gilbert
,
R. W.
, and
Cheadle
,
B. A.
, “
Formation, Growth and Decomposition of Precipitates in Zircaloy-2 and 4
,”
Proceedings
, Workshop on Second Phase Particles and Matrix Properties of the Zircaloys,
Erlangen, FR Germany
,
07
1985
, pp. 67–83.
33.
Yang
,
W. J. S.
,
Tucker
,
R. P.
,
Cheng
,
B.
, and
Adamson
,
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, “
Precipitates in Zircaloy: Identification and the Effects of Irradiation and Thermal Treatment
,”
Journal of Nuclear Materials
, Vol.
138
,
1986
, p. 185.
34.
Griffiths
,
M.
,
Gilbert
,
R. W.
, and
Carpenter
,
G. J. C.
, “
Phase Stability, Decomposition and Redistribution of Intermetallic Precipitates in Zircaloy-2 and -4 During Neutron Irradiation
,”
Journal of Nuclear Materials
, Vol.
150
,
1987
, p. 53.
35.
Etoh
,
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,
Kikuchi
,
K.
,
Yasuda
,
T.
,
Koizumi
,
S.
, and
Oishi
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, “
Neutron Irradiation Effects on the Nodular Corrosion of Zircaloy-2
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36.
Etoh
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Irradiation-Induced Dissolution of Precipitates in Zircaloy-2
,”
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37.
Etoh
,
Y
and
Shimada
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Neutron Irradiation Effects on Intermetallic Precipitates in Zircaloy as a Function of Fluence
,”
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38.
Huang
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P. Y.
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Mahmood
,
S. T.
, and
Adamson
,
R. B.
, “
Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
American Society for Testing and Materials
,
1996
, pp. 726–757.
39.
Griffiths
,
M.
,
Mecke
,
J. F.
, and
Winegar
,
J. E.
, “
Evolution of Microstructure in Zirconium Alloys During Irradiation
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
American Society for Testing and Materials
,
1996
, pp. 580–602.
40.
Franklin
,
D. G.
and
Adamson
,
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Implications of Zircaloy Creep and Growth to Light Water Reactor Performance
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42.
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Zirconium in the Nuclear Industry: Sixth International Symposium
, ASTM STP 824,
American Society for Testing and Materials
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1984
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43.
Nichols
,
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, “
Mechanistic Modeling of Zircaloy Deformation and Fracture in Fuel Element Analysis
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Zirconium in the Nuclear Industry: Seventh International Symposium
, ASTM STP 939,
American Society for Testing and Materials
,
1987
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44.
Hesketh
,
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,
Harbottle
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Tucker
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,”
Zirconium in the Nuclear Industry: Sixth International Symposium
, ASTM STP 824,
American Society for Testing and Materials
,
1984
, pp. 427–451.
46.
Rogerson
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Irradiation Growth in Zirconium and Its Alloys
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47.
Fidleris
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, “
An Overview of Microstructural and Experimental Factors that Affect Irradiation Growth Behavior of Zirconium Alloys
,”
Zirconium in the Nuclear Industry: Seventh International Symposium
, ASTM STP 939,
American Society for Testing and Materials
,
1987
, pp. 49–85.
48.
Holt
,
R. A.
 et al
, “
Non-linear Irradiation Growth of Cold-Worked Zircaloy-2
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
American Society for Testing and Materials
,
1996
, pp. 623–637.
49.
Garzarolli
,
F.
,
Dewes
,
P.
,
Moussner
,
G.
, and
Basso
,
H. H.
, “
Effects of High Neutron Fluences on Microstructure and Growth of Zircaloy-4
,”
Zirconium in the Nuclear Industry: Eighth International Symposium
, ASTM STP 1032,
American Society for Testing and Materials
,
1989
, pp. 641–657.
50.
deCarlan
,
Y.
,
Regnand
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C.
,
Griffiths
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M.
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Gilbon
,
D.
, and
Lemaignan
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C.
, “
Influence of Iron in the Nucleation of (c) Component Dislocation Loops
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
American Society for Testing and Materials
,
1996
, pp. 638–653.
51.
Kruger
,
R. M.
and
Adamson
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Precipitate Behavior in Zirconium-based Alloys in BWRs
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52.
Holt
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Mechanisms of Irradiation Growth of Alpha-Zirconium Alloys
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53.
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Cyclic Deformation of Neutron Irradiated Copper
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Wechsler
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Dislocation Channeling in Irradiated and Quenched Metals
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57.
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and
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 B.
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,”
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, ASTM STP 633,
American Society for Testing and Materials
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1977
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58.
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Failure Strain for Irradiated Zircaloy Based on Subsized Specimen Testing and Analysis
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, ASTM STP 888,
American Society for Testing and Materials
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60.
Bell
,
W. L.
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Adamson
,
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, “
Use of 2 ½ D Electron Microscopy to Study Dislocation Channeling Effects in Irradiated Zircaloy
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61.
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Effect of Irradiation at 588K on Mechanical Properties and Deformation Behavior of Zirconium Alloy Strip
,”
Zirconium in the Nuclear Industry
, ASTM STP 939,
American Society for Testing and Materials
,
1987
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62.
Yasuda
,
T.
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Nakatsuka
,
M.
, and
Yamashita
,
K.
, “
Deformation and Fracture Properties of Neutron Irradiated Recrystallized Zircaloy-2 Cladding under Uniaxial Tension
,”
Zirconium in the Nuclear Industry
, ASTM STP 939,
American Society for Testing and Materials
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1987
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63.
Garde
,
A. M.
, “
Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence
,”
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, ASTM STP 1023,
American Society for Testing and Materials
,
1989
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64.
Garde
,
A. M.
,
Smith
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G. P.
, and
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Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
American Society for Testing and Materials
,
1996
, pp. 407–430.
65.
Kruger
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Precipitate Stability in Zircaloy-2
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Torimaru
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,”
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67.
Huang
,
P. Y.
,
Mahmood
,
S. T.
, and
Adamson
,
R. B.
, “
Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
American Society for Testing and Materials
,
1996
, pp. 726–757.
68.
Mahmood
,
S. T.
,
Edsinger
,
K. W.
,
Farkas
,
D. M.
, and
Adamson
,
R. B.
, “
Effects of SPP Dissolution on Mechanical Properties of Zircaloy-2
,”
Proceedings
, 1997 International Topical Meeting on LWR Fuel Performance,
Portland, OR
,
American Nuclear Society, Inc.
,
LaGrange Park, IL
,
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, pp. 440–451.
69.
Mahmood
,
S. T.
,
Farkas
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D. M.
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Adamson
,
R. B.
, and
Etoh
,
Y.
, “
Post-Irradiation Characterization of Ultra High Fluence Zircaloy-2 Plate
,”
Zirconium in the Nuclear Industry: Twelfth International Symposium
, ASTM STP 1354,
Toronto
,
1998
(this publication).
70.
Azzarto
,
F. J.
,
Baldwin
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E. E.
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Wiesinger
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F. W.
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Lewis
,
D. M.
, “
Unirradiated, In-Pile and Post-Irradiation Low Strain Rate Tensile Properties of Zircaloy-4
,”
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, Vol.
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71.
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,
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Uniaxial In-Reactor Creep of Zirconium Alloys
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72.
Kreyns
,
P. H.
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Burkhart
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Radiation Enhanced Relaxation in Zircaloy-4 and Zr/2.5Nb/0.5 As Alloys
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Zirconium in the Nuclear Industry: Twelfth International Symposium
, ASTM STP 1354,
American Society for Testing and Materials
,
1999
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76.
Causy
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Irradiation-Enhanced Creep of Zr-2.5 Nb Tubes at High Neutron Fluences
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Zirconium in the Nuclear Industry: Twelfth International Symposium
, ASTM STP 1354,
American Society for Testing and Materials
,
1999
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77.
Marlowe
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