Abstract

A stress relaxation on bent-beam specimen irradiation campaign was performed in the French material testing reactor OSIRIS in order to screen different materials according to their in-flux behavior and to derive constitutive laws that are used to describe the in-reactor behavior of assembly components under axial stress. This paper presents the methodology used, with particular emphasis on the validation of the different hypotheses. The methodology is illustrated with the results obtained on an industrial Zircaloy-4 (Zy-4) alloy used in guide thimbles. As an illustration of the capability of the method, the parameters of simple creep behavior laws are adjusted to the relaxation results. The creep-law predictions are compared to results obtained previously in a creep experiment.

References

1.
Auclair
,
M.
,
Gosmain
,
L.
,
Guimbal
,
P.
,
Moulin
,
D.
,
Roux
,
P.
,
Sauder
,
C.
, and
Villard
,
J. F.
, “
CEDRIC Experiment: On Line Elongation Measurement of a High Temperature Specimen Under Driven Stress in the Osiris Reactor
,”
IGORR 2009
, Beijing, China, Oct. 28–30,
2009
, http://www.igorr.com/home/liblocal/docs/IGORR2009%20-%20CEDRIC.pdf.
2.
Fraser
,
D. E.
,
Ross-Ross
,
P. A.
, and
Causey
,
A. R.
, “
The Relation Between Stress-Relaxation and Creep for Some Zirconium Alloys During Neutron Irradiation
,”
J. Nucl. Mater.
 0022-3115, Vol.
46
, No.
3
,
1973
, pp.
281
292
. https://doi.org/10.1016/0022-3115(73)90043-3
3.
Morize
,
P.
,
Baicry
,
J.
, and
Mardon
,
J. P.
Effect of Irradiation at 588 K on Mechanical Properties and Deformation Behavior of Zirconium Alloy Strip
,”
Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
, Strasbourg, France,
1987
,
R. B.
Adamson
and
L. F. P.
Van Swam
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
101
119
.
4.
Causey
,
A. R.
,
Butcher
,
F. J.
, and
Donohue
,
S. A.
, “
Measurement of Irradiation Creep of Zirconium Alloys Using Stress Relaxation
,”
J. Nucl. Mater.
 0022-3115 Vol.
159
,
1988
, pp.
101
113
. https://doi.org/10.1016/0022-3115(88)90088-8
5.
Foster
,
J. P.
,
Gilbert
,
E. R.
,
Bundec
,
K.
, and
Porter
,
D. L.
, “
Relationship Between In-Reactor Stress Relaxation and Irradiation Creep
,”
J. Nucl. Mater.
 0022-3115, Vol.
252
, No.
1–2
,
1998
, pp.
89
97
. https://doi.org/10.1016/S0022-3115(97)00294-8
6.
Causey
,
A. R.
,
Carpenter
,
G. J. C.
, and
MacEwen
,
S. R.
, “
In-Reactor Stress Relaxation of Selected Metals and Alloys at Low Temperatures
,”
J. Nucl. Mater.
 0022-3115, Vol.
90
, No.
1–3
,
1980
, pp.
216
223
. https://doi.org/10.1016/0022-3115(80)90258-5
7.
Ferrer
,
F.
,
Barbu
,
A.
,
Bretheau
,
T.
,
Crepin
,
J.
,
Willaime
,
F.
, and
Charquet
,
D.
, “
The Effect of Small Concentrations of Sulfur on the Plasticity of Zirconium Alloys at Intermediate Temperatures
,”
Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423
, Annecy, France,
2002
,
G. D.
Moan
and
P.
Rudling
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
863
885
.
8.
Robinet
,
P.
,
1995
, “
Etude Expérimentale et Modélisation du Comportement Viscoplastique Anisotrope du Zircaloy-4 dans Deux États Métallurgiques [Experimental study and modelization of the anisotropic viscoplastic behaviour of zircaloy 4 in two metallurgical states]
,” Ph.D. thesis,
U.F.R. des Sciences et Technique de l’Université de Franche-Comté
.
9.
McInteer
,
W. A.
,
Baty
,
D. L.
, and
Stein
,
K. O.
, “
The Influence of Tin Content on the Thermal Creep of Zircaloy-4
,”
Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
, San Diego, CA,
1989
,
ASTM International
,
West Conshohocken, PA
, pp.
621
640
.
10.
Kearns
,
J.
, “
Terminal Solubility and Partitioning of Hydrogen in the Alpha Phase of Zirconium Zircaloy-2 and Zircaloy-4
,”
J. Nucl. Mater.
 0022-3115, Vol.
22
, No.
3
,
1967
, pp.
292
303
. https://doi.org/10.1016/0022-3115(67)90047-5
11.
Rupa
,
N.
,
Clavel
,
M.
,
Bouffioux
,
P.
,
Domain
,
C.
, and
Legris
,
A.
, “
About the Mechanisms Governing the Hydrogen Effect on Viscoplasticity of Unirradiated Fully Annealed Zircaloy-4 Sheet
,”
Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423
, Annecy, France,
2002
,
G. D.
Moan
and
P.
Rudling
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
811
834
.
12.
Le Saux
,
M.
,
Besson
,
J.
,
Carassou
,
S.
,
Poussard
,
C.
, and
Averty
,
X.
, “
Behavior and Failure of Uniformly Hydrided Zircaloy-4 Fuel Claddings Between 25°C and 480°C Under Various Stress States, Including RIA Loading Conditions
,”
Eng. Failure Anal.
 1350-6307, Vol.
17
,
2010
, pp.
683
700
. https://doi.org/10.1016/j.engfailanal.2009.07.001
13.
Yvon
,
P.
,
Diz
,
J.
, and
Ligneau
,
N.
, “
Irradiation Creep and Growth of Guide Thimble Alloys
,”
Proceedings of the International Symposium Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors Fontevraud IV
, Fontevraud, France, Sept. 14–18,
1998
,
Société Française de l’Energie Nucléaire
,
Paris
,
1998
, Vol.
2
, pp.
1241
1252
.
14.
Bossis
,
P.
,
Verhaeghe
,
B.
,
Doriot
,
S.
,
Gilbon
,
D.
,
Chabretou
,
V.
,
Dalmais
,
A.
,
Mardon
,
J. P.
,
Blat
,
M.
, and
Miquet
,
A.
, “
In PWR Comprehensive Study of High Burn-up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4
,” Sunriver, OR,
2009
,
Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
,
B.
Kammenzind
and
M.
Limback
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
430
456
.
15.
Fidleris
,
V.
, “
The Irradiation Creep and Growth Phenomena
,”
J. Nucl. Mater.
 0022-3115, Vol.
159
,
1988
, pp.
22
42
. https://doi.org/10.1016/0022-3115(88)90083-9
16.
King
,
S. J.
,
Kesterson
,
R. L.
,
Yueh
,
K. H.
,
Comstock
,
R. J.
,
Herwig
,
W. M.
, and
Feguson
,
S. D.
, “
Impact of Hydrogen on Dimensional Stability of ZIRLO Fuel Assemblies
,”
Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423
,
G. D.
Moan
and
P.
Rudling
, Annecy, France,
2002
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
471
489
.
17.
Barberis
,
P.
,
Vermoyal
,
J. J.
,
Chabretou
,
V.
, and
Rebeyrolle
,
V.
, “
CASTA DIVA™: Experiments and Modelling Oxide Induced Deformation in Nuclear Components
,”
15th International Symposium, ASTM STP 1505
, Sunriver, OR,
2009
,
B.
Kammenzind
and
M.
Limback
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
612
630
.
18.
Blat-Yrieix
,
M.
,
Ambard
,
A.
,
Foct
,
F.
,
Miquet
,
A.
, and
Cayet
,
N.
, “
Toward a Better Understanding of Dimensional Changes in Zircaloy-4: What is the Impact Induced by Hydrides and Oxide Layer?
,”
Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505
, Sunriver, OR,
2009
,
B.
Kammenzind
and
M.
Limback
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
594
607
.
19.
Adamson
,
R. B.
, “
Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy
,” Toronto, Canada,
2000
,
Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354
,
G. P.
Sabol
and
G. D.
Moan
, Eds.,
ASTM International
,
West Conshohocken, PA
, pp.
15
31
.
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