Abstract

The microstructures of four kinds of Zircaloy-2-type materials with neutron exposure up to about 15 × 1025 n/m2 (E>1MeV) were examined to investigate the microstructural evolution and to correlate it with the in-reactor corrosion behavior at very high fluences. The materials examined in this study included two advanced Zr-based alloys with good corrosion resistance, namely High Fe Zry and High FeNi Zry, and two other kinds of Zry-2 materials with slightly different elemental compositions and fabrication processes producing differing second phase particle sizes. All alloys showed good corrosion behavior and low hydrogen pickup when irradiated up to four cycles in dummy neutron source holders located outside of channel boxes. After six irradiation cycles, all four of the alloys had an increase in the rate of uniform corrosion and hydrogen pickup. The results of the microstructure examinations after six-cycle irradiation indicated two interesting points: (1) increased insight into the dissolution process for Zr-Fe-Cr particles, and (2) a correlation between the number density of Zr-Fe-Cr particles surviving through irradiation and the corrosion behavior at high fluences. From these results, it is suggested that increasing the initial particle size and/or controlling the alloy chemistry would be beneficial to improve the uniform corrosion performance and to lower hydrogen pickup, especially at very high fluences.

References

1.
Etoh
,
Y.
,
Shimada
,
S.
,
Yoshida
,
T.
,
Ikeda
,
T.
,
Adamson
,
R. B.
,
Chen
,
J.-S. F.
, et al
, “
Development of New Zirconium Alloys for a BWR
,”
Zirconium in the Nuclear Industry: Eleventh International Symposium
, ASTM STP 1295,
E. R.
Bradley
and
G. P.
Sablo
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1996
, pp.
825
-
849
.
2.
Etoh
,
Y.
,
Shimada
,
S.
,
Adamson
,
R. B.
,
Yasuda
,
T.
,
Kogai
,
T.
, and
Ishii
,
Y.
, “
Irradiation Behavior of Zr Alloys for Ultra High Burnup Fuel
,”
Proceedings, International Topical Mtg. On Light Water Reactor Fuel Performance
,
Portland, OR
,
American Nuclear Society
,
La Grange Park, IL
,
1997
, pp.
211
-
218
.
3.
Ishimoto
,
S.
,
Kubo
,
T.
,
Adamson
,
R. B.
,
Etoh
,
Y.
,
Ito
,
K.
, and
Suzawa
,
Y.
, “
Development of New Zirconium Alloys for Ultra-High Burnup Fuel
,”
Proceedings, International Topical Mtg. on Light Water Reactor Fuel Performance
,
Park City, UT
,
American Nuclear Society
,
La Grange Park, IL
,
2000
, pp.
31
-
42
.
4.
Ishimoto
,
S.
,
Kubo
,
T.
, and
Kubota
,
O.
, “
Development of New Zirconium Alloys for Higher Burnup Fuel
,”
Proceedings, ENS TopFuel 2003 Conference
,
Würzburg, Germany
, March 16–19, 2003.
5.
Nanikawa
,
S.
,
Etoh
,
Y.
,
Shimada
,
S.
,
Kubo
,
T.
,
Ito
,
K.
, and
Harada
,
M.
, “
Correlation Between Characteristics of Oxide Films Formed on Zr Alloys in BWRs and Corrosion Performance
,”
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.
815
-
835
.
6.
Ito
,
K.
,
Shimada
,
S.
,
Levin
,
H. A.
,
Adamson
,
R. B.
,
Oguma
,
M.
,
Chen
,
B.
, et al
, “
Effects of Water Chemistry Impurities on Corrosion of Zr-Alloys Under BWR Condition
,”
Proceedings, International Topical Meeting on Light Water Reactor Fuel Performance
,
West Palm Beach, FL
, April 17–21, 1994, pp.
273
-
285
.
7.
Aomi
,
M.
,
Kogai
,
T.
,
Shimada
,
S.
,
Ichikawa
,
N.
,
Ibe
,
E.
,
Ishii
,
Y.
, et al
, “
Evaluation of Zircaloy Corrosion under Various Water Chemistries in a BWR Simulation Loop
,”
Proceedings, International Conference on Water Chemistry in Nuclear Reactor System 7
,
Bournemouth, UK
, October 13–17, Vol.
1
,
1996
, pp.
284
-
286
.
8.
Shimada
,
S.
,
Lin
,
C. C.
,
Cheng
,
B.
,
Ieda
,
T.
,
Oguma
,
M.
,
Takei
,
K.
, et al
, “
Parametric Tests of the Effects of Water Chemistry Impurities on Corrosion of Zr-Alloys under Simulated BWR Condition
,”
Influence of Water Chemistry on Fuel Cladding Behavior
, IAEA-TECDOC-927,
IAEA, Vienna
,
1997
, pp.
73
-
89
.
9.
Garzarolli
,
F.
,
Schumann
,
R.
, and
Steinberg
,
E.
, “
Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements
,”
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.
709
-
723
.
10.
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,
E. R.
Bradley
and
G. P.
Sabol
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1996
, pp.
726
-
757
.
11.
Abolhassani
,
S.
,
Gavillet
,
D.
,
Groeschel
,
F.
,
Jourdain
,
P.
, and
Zwicky
,
H. U.
, “
Recent Observation on The Evolution of The Secondary Phase Particles in Zircaloy-2 under Irradiation in A BWR up to High Burn-Up
,”
Proceedings, International Topical Mtg. On Light Water Reactor Fuel Performance
,
Park City, UT
,
American Nuclear Society
,
La Grange Park, IL
,
2000
, pp.
2
-
16
.
12.
Tägtstrom
,
P.
,
Limbäck
,
M.
,
Dohlbäck
,
M.
, and
Andersson
,
T.
, “
Effects of Hydrogen Pickup and Second-Phase Particle Dissolution on the In-Reactor Corrosion Performance of BWR Claddings
,”
Zirconium in the Nuclear Industry: Thirteenth International Symposium
, ASTM STP 1423,
G. P.
Sabol
and
P.
Rudling
, Eds.,
ASTM International
,
West Conshohocken, PA
,
2002
, pp.
96
-
118
.
13.
Griffiths
,
M.
, “
Amorphous Intermetallics in Neutron Irradiated Zry after High Fluences
,”
Journal of Nuclear Materials
 0022-3115, Vol.
135
,
1985
, pp.
265
-
268
.
14.
Motta
,
A. T.
,
Olander
,
D. R.
, and
Machiels
,
A. J.
, “
Electron Irradiation-Induced Amorphization of Precipitates in Zircaloy-2
,”
Effects of Radiation on Materials: Fourteenth International Symposium
, ASTM STP 1046,
N. H.
Packan
,
R. E.
Stoller
, and
A. S.
Kumar
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1989
, pp.
457
-
469
.
15.
Kai
,
J. J.
,
Tsai
,
C. H.
, and
Hsieh
,
W. F.
, “
Effects of Proton Irradiation on the Microstructural Evolution of Zircaloy-2 Tubing
,”
Effects of Radiation on Materials: Fifteenth International Symposium
, ASTM STP 1125,
R. E.
Stoller
,
A. S.
Kumar
, and
D. S.
Gelles
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1992
, pp.
355
-
372
.
16.
Etoh
,
Y.
and
Shimada
,
S.
, “
Irradiation Induced Dissolution of Precipitates in Zry-2
,”
Journal of Nuclear Science and Technology
 0022-3131, Vol.
29
, No.
4
,
1992
, pp.
358
-
366
.
17.
Griffiths
M.
,
Chow
,
C.
,
Coleman
,
C. E.
,
Holt
,
R. A.
,
Sagat
,
S.
, and
Urbanic
,
V. F.
, “
Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors During Service
,”
Effects of Radiation on Materials: Sixteenth International Symposium
, ASTM STP 1175,
A. S.
Kumar
,
D. S.
Gelles
,
R. K.
Nanstad
, and
E. A.
Little
, Eds.,
ASTM International
,
West Conshohocken, PA
,
1993
, pp.
1077
-
1110
.
18.
Mahmood
,
S. T.
,
Farkas
,
D. M.
,
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,
G. P.
Sabol
and
G. D.
Moan
, Eds.,
ASTM International
,
West Conshohocken, PA
,
2000
, pp.
139
-
169
.
19.
Etoh
,
Y.
,
Nonaka
,
Y.
,
Kubo
,
T.
,
Nomata
,
T.
,
Hayashi
,
H.
, and
Kitamura
,
M.
, “
The Effect of Microstructure on the Corrosion Behavior of Zircaloy-2 in BWRs
,”
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.
658
-
677
.
20.
Lemaingn
,
C.
, “
Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys
,”
Zirconium in the Nuclear Industry: Thirteenth International Symposium
, ASTM STP 1423,
G. P.
Sabol
and
P.
Rudling
, Eds.,
ASTM STP 1423
,
G. P.
Sabol
and
P.
Rudling
, Eds.,
ASTM International
,
West Conshohocken, PA
,
2002
, pp.
20
-
29
.
21.
Motta
,
A. T.
, “
Amorphization of Intermetallic Compounds under Irradiation — A Review
,”
Journal of Nuclear Materials
 0022-3115 https://doi.org/10.1016/S0022-3115(96)00740-4, Vol.
244
,
1997
, pp.
227
-
250
.
22.
Griffiths
,
M.
,
Holt
,
R. A.
, and
Rogerson
,
A.
, “
Microstructural Aspects of Accelerated Deformation of Zircaloy Nuclear Reactor Components During Service
,”
Journal of Nuclear Materials
 0022-3115, Vol.
225
,
1995
,
245
-
258
.
23.
Van Swam
,
L. F. P.
and
Shann
,
S. H.
, “
The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactor
,”
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.
758
-
781
.
24.
Rudling
,
P.
,
Wikmark
,
G.
,
Lehtinen
,
B.
, and
Pettersson
,
H.
, “
Impact of Second Phase Particles on BWR Zr-2 Corrosion and Hydriding Performance
,”
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.
678
-
706
.
25.
Weidinger
,
H. G.
,
Ruhmann
,
H.
,
Cheliotis
,
G.
,
Maguire
,
M.
, and
Yau
,
T.-L.
, “
Corrosion-Electrochemical Properties of Zirconium Intermetallics
,”
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.
499
-
535
.
26.
Isobe
,
T.
,
Murai
,
T.
, and
Mae
,
Y.
, “
Anodic Protection Provided by Precipitates in Aqueous Corrosion of Zircaloy
,”
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.
203
-
217
.
27.
Murai
,
T.
,
Isobe
,
T.
,
Takizawa
,
Y.
, and
Mae
,
Y.
, “
Fundamental Study on the Corrosion Mechanism of Zr-0.2Fe, Zr-0.2Cr, and Zr-0.1Fe-0.1Cr Alloys
,”
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.
623
-
640
.
28.
Barberis
,
P.
,
Ahlberg
,
E.
,
Simic
,
N.
,
Charquet
,
D.
,
Lemaignan
,
C.
,
Wikmark
,
G.
, et al
, “
Role of the Second-Phase Particles in Zirconium Binary Alloys
,”
Zirconium in the Nuclear Industry: Thirteenth International Symposium
, ASTM STP 1423,
G. P.
Sabol
and
P.
Rudling
, Eds.,
ASTM International
,
West Conshohocken, PA
,
2002
, pp.
38
-
58
.
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