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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 630-638
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33484
Articles are hosted by Taylor and Francis Online.
The effect of neutron irradiation on hightemperature tensile and creep properties of austenitic heat-resistant alloys was studied. The effect, which appeared in the loss of ductility at elevated temperatures, was caused by helium produced by a nuclear transmutation reaction of thermal neutrons with boron and nickel in the alloy. The fracture mode was characterized by intergranular cracking. The tensile properties were determined at 700 to 1000°C after irradiation up to a maximum thermal neutron fluence of 1.2 x 1025 n/m2. Creep tests were made at 900°C after irradiation to 6.6 x 1024 and 7.5 x 1024 n/m2. The tensile ductility was reduced with increasing deformation temperature, due primarily to the loss of necking elongation. In the postirradiation creep tests, significant reduction in rupture life also occurred. In both tensile and creep properties, the iron-base alloys were superior to the nickel-rich alloys, and, in particular, a heat of Incoloy alloy 800 showed exceptionally high resistance to irradiation.