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ASTM Selected Technical Papers
Effects of Radiation on Materials: Sixteenth International Symposium
By
AE Kumar
AE Kumar
1
University of Missouri-Rolla
,
Rolla, MO
;
symposium chairman and editor
.
Search for other works by this author on:
DS Gelles
DS Gelles
2
Battelle Pacific Northwest Laboratory
,
Richland, WA
;
symposium cochairman and editor
.
Search for other works by this author on:
RK Nanstad
RK Nanstad
3
Oak Ridge National Laboratory
,
Oak Ridge, TN
;
symposium cochairman and editor
.
Search for other works by this author on:
TA Little
TA Little
4
Harwell Laboratory
,
Oxfordshire,
UK
;
symposium cochairman and editor
.
Search for other works by this author on:
ISBN-10:
0-8031-1488-5
ISBN:
978-0-8031-1488-3
No. of Pages:
1344
Publisher:
ASTM International
Publication date:
1994

It has been demonstrated that fast neutron irradiation produces significant hardening in simple Fe-(3-18)Cr binary alloys irradiated to about 35 dpa in the temperature range 365 to 420°C, whereas irradiation at 574°C produces hardening only for 15% or more chromium. The irradiation-induced changes in tensile properties are discussed in terms of changes in the power law work hardening exponent. The work hardening exponent of the lower chromium alloys decreased significantly after low temperature irradiation (< 420°C) but increased after irradiation at 574°C. The higher chromium alloys failed either in cleavage or in a mixed ductile/brittle fashion. Deformation microstructures are presented to support the tensile behavior.

1.
Hamilton
,
M. L.
and
Gelles
,
D. S.
, “
Postirradiation Strength and Deformation of Ferritic Fe-Cr Binary Alloys
,”
Effects of Radiation on Materials: 15th International Symposium
, ASTM STP 1125,
Stoller
R. E.
,
Kumar
A. S.
and
Gelles
D. S.
, Eds.,
ASTM
,
Philadelphia
,
1992
, pp. 1234–1242.
2.
Gelles
,
D. S.
, “
Neutron Irradiation Damage in Ferritic Fe-Cr Alloys
,” Effects of Radiation on Materials: 14th International Symposium, Volume
1
, ASTM STP 1046,
Packan
N. H.
,
Stoller
R. E.
and
Kumar
A. S.
, Eds.,
ASTM
,
Philadelphia
,
1989
, pp. 73–97.
3.
Horton
,
L. L.
,
Bentley
,
J.
and
Farrell
,
K.
, “
A TEM Study of Neutron Irradiated Iron
,”
Journal of Nuclear Materials
, Vol.
108 & 109
,
1982
, pp 222–233.
4.
Gelles
,
D. S.
and
Thomas
,
L.E.
, “
Effects of Neutron Irradiation on Microstructure in Experimental and Commercial Alloys
,” in Proceeding of Topical Conference on Ferritic Alloys for use in Nuclear Energy Technologies,
Davis
J. W.
and
Michel
D. J.
, Eds.,
Metallurgical Society of AIME
,
Warrendale, PA
1984
, pp 559–568.
5.
Bullough
,
R.
,
Wood
,
M. H.
, and
Little
,
E. A.
, “
A Microstructural Explanation for the Low Swelling of Ferritic Steels
,” Effects of Radiation on Materials: Tenth Conference, ASTM STP 725,
Kramer
D.
,
Brager
H. R.
and
Perrin
J. S.
, Eds.,
ASTM
,
Philadelphia
1981
, pp 593–609.
6.
Eyre
,
B. L.
, “
Direct Observation of Neutron Irradiated Damage in a-Iron
,”
Philosophical Magazine
 1478-6435, Vol.
7
,
1962
, pp 2107–2113.
7.
Eyre
,
B. L.
and
Bartlett
,
A. F.
, “
An Electron Microscopic Study of Neutron Damage in Alpha-Iron
,”
Philosophical Magazine
 1478-6435, Vol.
12
,
1965
, pp 261–272.
8.
Smidt
,
F. A.
, Jr.
and
Mastel
,
B.
, “
Some Observations of Dislocation Channelling in Irradiated Iron
,”
Philosophical Magazine
 1478-6435, Vol.
20
,
1969
, pp 651–656.
9.
Robertson
,
I. M.
,
Jenkins
,
M. L.
and
English
,
C. A.
,
Journal of Nuclear Materials
, Vol.
108 & 109
,
1982
, pp 209–221.
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