Neutron-induced Microstructural Alteration of GlidCop{trademark} Alloys at 415°C and High Neutron Exposure PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages : 9
Book Description
GlidCop{trademark} internally oxidized copper alloys remain the leading candidates for high heat flux applications in fusion reactor. This paper presents the microstructural changes incurred in three GlidCop{trademark} alloys exposed to long term, high temperature neutron irradiation. Irradiation at high temperature produced a microstructure containing a much lower dislocation density than the unirradiated specimens. Although 10--50 nm size triangular oxide particles were observed in areas with a very low number density of particles, spherical oxide particles on the order of 5--7 nm in diameter, thought to be CuAl2O4, were the predominant morphology. The changes in grain size distribution, dislocation density, and precipitate type and distribution saturate in the range of 34 to 50 dpa, as reflected in the saturation of mechanical properties.
Author: Publisher: ISBN: Category : Languages : en Pages : 9
Book Description
GlidCop{trademark} internally oxidized copper alloys remain the leading candidates for high heat flux applications in fusion reactor. This paper presents the microstructural changes incurred in three GlidCop{trademark} alloys exposed to long term, high temperature neutron irradiation. Irradiation at high temperature produced a microstructure containing a much lower dislocation density than the unirradiated specimens. Although 10--50 nm size triangular oxide particles were observed in areas with a very low number density of particles, spherical oxide particles on the order of 5--7 nm in diameter, thought to be CuAl2O4, were the predominant morphology. The changes in grain size distribution, dislocation density, and precipitate type and distribution saturate in the range of 34 to 50 dpa, as reflected in the saturation of mechanical properties.
Author: David S. Gelles Publisher: ISBN: Category : Austenitic alloys Languages : en Pages : 11
Book Description
Density change measurements have been completed on a wide variety of commercially available structural alloys irradiated to neutron fluence levels as large as 2.8x1023n.cm2 (E>0.1MeV) or ~140 dpa in EBR-II at eight temperatures between 399 and 650°C. While there was essentially no swelling in some ferritic alloys and some austenitic superalloys, other austenitic alloys exhibited a wide range of swelling depending on composition, heat treatment, and irradiation temperature.
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Author: David S. Gelles