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Title: Tensile properties of neutron-irradiated 6061 aluminum alloy in annealed and precipitation-hardened conditions

Abstract

Tensile specimens of 6061 aluminum alloy (nominally 1 wt percent Mg, 0.6 Si) were heat treated to give fully annealed (''0'') temper) and precipitation-hardened (''T6'' temper) conditions and were irradiated in water at 328/sup 0/K (0.35 T/sub m/) to fast (greater than 0.1 MeV) fluences up to 1.8 x 10/sup 27/ n/m/sup 2/ and thermal (less than 0.025 eV) fluences up to 3.0 x 10/sup 27/ n/m/sup 2/. The corresponding maximum displacement level was 260 dpa, and over 7 wt percent Si was created from transmutation reactions. The major microstructural defects were voids, dislocations and a precipitate of silicon. Swelling from voids was less than 1 percent. In the ''T6'' material tested at 323/sup 0/K (0.35 T/sub m/) and 373/sup 0/K (0.4 T/sub m/) irradiation raised the 0.2 percent flow stress and the UTS by 45 to 60 percent from the unirradiated values of about 280 and 330 MPa, respectively; ductility was reduced from 15 to about 9 percent. At 423/sup 0/K (0.45 T/sub m/) there was a similar degree of hardening, but ductility fell to about 5 percent. The alloy in the ''0'' condition was softer, by 125 to 150 MPa, than the irradiated ''T6'' alloy, and its elongationmore » remained above 10 percent. In all cases the loss in ductility occurred principally through reduction in uniform strain. Fractures were ductile.« less

Authors:
;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
Sponsoring Org.:
USDOE
OSTI Identifier:
6886356
Report Number(s):
CONF-780722-9
TRN: 78-018803
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Conference
Resource Relation:
Conference: 9. symposium on effects of radiation in structural materials, Richland, WA, USA, 10 Jul 1978
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; ALUMINIUM ALLOYS; PHYSICAL RADIATION EFFECTS; FAST NEUTRONS; FRACTURES; HEAT TREATMENTS; MICROSTRUCTURE; SWELLING; TENSILE PROPERTIES; ALLOYS; BARYONS; CRYSTAL STRUCTURE; ELEMENTARY PARTICLES; FAILURES; FERMIONS; HADRONS; MECHANICAL PROPERTIES; NEUTRONS; NUCLEONS; RADIATION EFFECTS; 360106* - Metals & Alloys- Radiation Effects

Citation Formats

Farrell, K., and King, R. T. Tensile properties of neutron-irradiated 6061 aluminum alloy in annealed and precipitation-hardened conditions. United States: N. p., 1978. Web.
Farrell, K., & King, R. T. Tensile properties of neutron-irradiated 6061 aluminum alloy in annealed and precipitation-hardened conditions. United States.
Farrell, K., and King, R. T. 1978. "Tensile properties of neutron-irradiated 6061 aluminum alloy in annealed and precipitation-hardened conditions". United States. https://www.osti.gov/servlets/purl/6886356.
@article{osti_6886356,
title = {Tensile properties of neutron-irradiated 6061 aluminum alloy in annealed and precipitation-hardened conditions},
author = {Farrell, K. and King, R. T.},
abstractNote = {Tensile specimens of 6061 aluminum alloy (nominally 1 wt percent Mg, 0.6 Si) were heat treated to give fully annealed (''0'') temper) and precipitation-hardened (''T6'' temper) conditions and were irradiated in water at 328/sup 0/K (0.35 T/sub m/) to fast (greater than 0.1 MeV) fluences up to 1.8 x 10/sup 27/ n/m/sup 2/ and thermal (less than 0.025 eV) fluences up to 3.0 x 10/sup 27/ n/m/sup 2/. The corresponding maximum displacement level was 260 dpa, and over 7 wt percent Si was created from transmutation reactions. The major microstructural defects were voids, dislocations and a precipitate of silicon. Swelling from voids was less than 1 percent. In the ''T6'' material tested at 323/sup 0/K (0.35 T/sub m/) and 373/sup 0/K (0.4 T/sub m/) irradiation raised the 0.2 percent flow stress and the UTS by 45 to 60 percent from the unirradiated values of about 280 and 330 MPa, respectively; ductility was reduced from 15 to about 9 percent. At 423/sup 0/K (0.45 T/sub m/) there was a similar degree of hardening, but ductility fell to about 5 percent. The alloy in the ''0'' condition was softer, by 125 to 150 MPa, than the irradiated ''T6'' alloy, and its elongation remained above 10 percent. In all cases the loss in ductility occurred principally through reduction in uniform strain. Fractures were ductile.},
doi = {},
url = {https://www.osti.gov/biblio/6886356}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 1978},
month = {Sun Jan 01 00:00:00 EST 1978}
}

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