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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
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AS Kumar,
AS Kumar
2
University of Missouri-Rolla
, Rolla, Missouri
; cochairman and editor
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DS Gelles
DS Gelles
3
Battelle Pacific Northwest Laboratory
, Richland, Washington
; cochairman and editor
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ISBN-10:
0-8031-1477-X
ISBN:
978-0-8031-1477-7
No. of Pages:
1339
Publisher:
ASTM International
Publication date:
1992
eBook Chapter
Postirradiation Strength and Deformation of Ferritic Fe-Cr Binary Alloys
By
ML Hamilton
,
ML Hamilton
1
Senior scientist and staff scientist
, respectively, Pacific Northwest Laboratory
, P.O. Box 999, Mail Stop P8-15, Richland, WA 99352
.
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DS Gelles
DS Gelles
1
Senior scientist and staff scientist
, respectively, Pacific Northwest Laboratory
, P.O. Box 999, Mail Stop P8-15, Richland, WA 99352
.
Search for other works by this author on:
Page Count:
9
-
Published:1992
Citation
Hamilton, M, & Gelles, D. "Postirradiation Strength and Deformation of Ferritic Fe-Cr Binary Alloys." Effects of Radiation on Materials: 15th International Symposium. Ed. Stoller, R, Kumar, A, & Gelles, D. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959 : ASTM International, 1992.
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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.
References
1.
Fish
, R. L.
, Straalsund
, J. L.
, Hunter
, C. W.
, 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.
, Yang
, W. J. S.
, and Garner
, F. A.
, “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
F. A.
, Henager
, C. H.
Jr., and Igata
N.
, Eds., American Society for Testing and Materials
, Philadelphia
, 1987
, pp. 245–270.3.
Gelles
, D. S.
, “Neutron Irradiation Damage in Ferritic Fe-Cr Alloys
,” Effects of Radiation on Materials: 14th International Symposium
, ASTM STP 1046, Vol. I
., Packan
N. H.
, Stoller
R. E.
, and Kumar
A. S.
, Eds., American Society for Testing and Materials
, Philadelphia
, 1989
, pp. 73–97.4.
Little
, E. A.
and Stow
, D. A.
, Metallurgical Science
, 1980
, p. 89.5.
Gelles
, D. S.
and Meinecke
, R. L.
, “Swelling in Simple Ferritic Alloys Irradiated to High Fluence
,” Alloy Development for Irradiation Performance Progress Report for Period Ending September 1983, DOE/ER-0045/11, Department of Energy
, Washington, DC, 1984
, p. 103.6.
Gelles
, D. S.
, Journal of Nuclear Materials
, Vols. 108–109
, 1982
, pp. 515–526.7.
Panayotou
, N. F.
, Atkin
, S. D.
, and Puigh
, R. J.
, “Design and Use of Nonstandard Tensile Specimens for Irradiated Materials Testing
,” The Use of Small-Scale Specimens for Testing Irradiated Material
, ASTM STP 888, Corwin
W. R.
and Lucas
G. E.
, Eds., American Society for Testing and Materials
, Philadelphia
, 1986
, pp. 201–219.8.
Maxon
, M. F.
, Heinisch
, H. L.
, and Gelles
, D. S.
, “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
, R. L.
and Maziasz
, P. J.
, “Helium Effects on Neutron-Irradiated Cr-Mo Ferritic Steels: A Review of Recent Results
,” Effects of Radiation on Materials: 14th International Symposium
, ASTM STP 1046, Vol. I
, Packan
N. H.
, Stoller
R. E.
, and Kumar
A. S.
, Eds., American Society for Testing and Materials
, Philadelphia
, 1989
, pp. 246–262.10.
Metals Handbook
, 8th ed., Vol. 8
, American Society for Metals
, Metals Park, OH
, 1973
, p. 291.11.
Gelles
, D. S.
and Thomas
, L. E.
, “Effects of Neutron Irradiation on Microstructure in Experimental and Commercial Ferritic Alloys
,” Proceedings, Topical Conference on Ferritic Alloys for Use in Nuclear Energy Technologies
, Davis
J. W.
and Michel
D. J.
, Eds., The Metallurgical Society of AIME
, Warrendale, PA
, 1984
, pp. 559–568.12.
Kelley
, M. J.
and Stoloff
, N. S.
, Met. Trans. A
, vol. 7A
, 1976
, pp. 331–333.13.
Home
, G. T.
, Roy
, R. B.
, and Paxton
, H. W.
, Journal of the Iron and Steel Institute
, 02
1963
,pp. 161–167.14.
Rees
, W. P.
, Hopkins
, B. E.
, and Tipler
, H. R.
, Journal of the Iron and Steel Institute
, 05
1954
, pp. 93–115.
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