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ASTM Selected Technical Papers
Effects of Radiation on Materials: 15th International Symposium
By
RE Stoller
RE Stoller
1
Oak Ridge National Laboratory
,
Oak Ridge, Tennessee
;
chairman and editor
Search for other works by this author on:
AS Kumar
AS Kumar
2
University of Missouri-Rolla
,
Rolla, Missouri
;
cochairman and editor
Search for other works by this author on:
DS Gelles
DS Gelles
3
Battelle Pacific Northwest Laboratory
,
Richland, Washington
;
cochairman and editor
Search for other works by this author on:
ISBN-10:
0-8031-1477-X
ISBN:
978-0-8031-1477-7
No. of Pages:
1339
Publisher:
ASTM International
Publication date:
1992

Six binary Fe-Cr alloys with chromium levels ranging from 3 to 18% were tensile tested at room temperature following irradiation at 365, 403, and 574°C to doses of 7.4, 37.7, and 34.3 dpa, respectively. Irradiation at 365 and 403°C produced significant strengthening at all chromium levels, with concurrent reductions in ductility. Strength levels were insensitive to composition, irradiation temperature, or neutron exposure. Irradiation at 574°C produced strength increases at only the two highest chromium levels. The results are attributed to dislocation loop and void development at 365 and 403°C, and phase instability at 574°C. No evidence for channel fracture was found.

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R. L.
,
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,
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,
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, and
Holmes
,
J. J.
, “
Swelling and Tensile Property Evaluations of High-Fluence EBR-II Thimbles
,”
Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys
, ASTM STP 529,
American Society for Testing and Materials
,
Philadelphia
,
1973
, pp. 149–164.
2.
Hamilton
,
M. L.
,
Huang
,
F. H.
,
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,
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, and
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,
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, “
Mechanical Properties and Fracture Behavior of 20% Cold Worked 316 Stainless Steel Irradiated to Very High Neutron Exposures
,”
Influence of Radiation on Material Properties: 13th International Symposium (Part II)
, ASTM STP 956,
Garner
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,
Henager
,
C. H.
 Jr.
, and
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,
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,
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, pp. 245–270.
3.
Gelles
,
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, “
Neutron Irradiation Damage in Ferritic Fe-Cr Alloys
,”
Effects of Radiation on Materials: 14th International Symposium
, ASTM STP 1046, Vol.
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.,
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,
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, and
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, Eds.,
American Society for Testing and Materials
,
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,
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, pp. 73–97.
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,
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,
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and
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,
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, “
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,” Alloy Development for Irradiation Performance Progress Report for Period Ending September 1983, DOE/ER-0045/11,
Department of Energy
, Washington, DC,
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,
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,
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, Vols.
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,
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,
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,
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,
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, and
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,
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, “
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,”
The Use of Small-Scale Specimens for Testing Irradiated Material
, ASTM STP 888,
Corwin
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and
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, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
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, pp. 201–219.
8.
Maxon
,
M. F.
,
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,
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, and
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,
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, “
The Tensile Properties of Fe-Cr Binary Alloys Using Miniature Specimens
,” Fusion Reactor Materials Semiannual Progress Report for Period Ending 30 September 1987, DOE/ER-0313/3,
Department of Energy
, Washington, DC,
1988
, p. 60.
9.
Klueh
,
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and
Maziasz
,
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, “
Helium Effects on Neutron-Irradiated Cr-Mo Ferritic Steels: A Review of Recent Results
,”
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, ASTM STP 1046, Vol.
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,
Packan
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,
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, and
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, Eds.,
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,
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,
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, pp. 246–262.
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,
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,
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,
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, p. 291.
11.
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,
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and
Thomas
,
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, “
Effects of Neutron Irradiation on Microstructure in Experimental and Commercial Ferritic Alloys
,”
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,
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and
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, Eds.,
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,
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,
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, pp. 559–568.
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and
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,
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, vol.
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, pp. 331–333.
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, and
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,
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,
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,
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, and
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,
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,
05
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, pp. 93–115.
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