Boron carbide pellets were irradiated in a spectrum-hardened ETR flux at temperatures of 1220 to 1620 deg F up to maximum specimen-averaged exposures of 38 x 10/sup 20/ captures/cm/sup 3/. Material variables included pellet density (75 to 99% T. D.) and stoichiometry (B: C = 3.8 to 4.1). Gas release and irradiation temperature were continuously monitored during the irradiation. Results are reported for boron carbide structural degradation, helium release, and interaction with Type 316 stainless steel. (auth
International audienceThis paper presents an in situ Transmission Electron Microscopy (TEM) study of...
International audienceThis paper presents a new methodology used to study transmutation damage in bo...
Zirconium carbide is a candidate to either replace or supplement silicon carbide as a coating materi...
Elemental boron, boron carbide, and zirconium diboride were irradiated at reactor ambient temperatur...
Boron carbide pellets were fabricated with variations in material parameters. These pellets were irr...
"Bettis Atomic Power Laboratory, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by ...
International audienceIn the framework of nuclear reactor core meltdown accident studies, the degrad...
Work performed at the Knolls Atomic Power Laboratory, Schenectady, New York.Other issues of this rep...
Uranium dioxide pellets sealed in Type 316 stainless steel containers with a helium gas were irradia...
Reduced activation ferritic/martensitic steel, F-82H (Fe-8Cr-2W-V-Ta), was irradiated in the High Fl...
Boron carbide-graphite nuclear control-rod materials containing up to 45 wt% B were prepared by hot-...
International audienceAlready used as neutron absorber in the current French nuclear reactors, boron...
"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...
"Contract No. W-7405-eng-92.""UC-25 Metallurgy and Ceramics (TID-4500, 14th Ed.).""April 21, 1959.""...
International audienceThis paper presents an in situ Transmission Electron Microscopy (TEM) study of...
International audienceThis paper presents a new methodology used to study transmutation damage in bo...
Zirconium carbide is a candidate to either replace or supplement silicon carbide as a coating materi...
Elemental boron, boron carbide, and zirconium diboride were irradiated at reactor ambient temperatur...
Boron carbide pellets were fabricated with variations in material parameters. These pellets were irr...
"Bettis Atomic Power Laboratory, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by ...
International audienceIn the framework of nuclear reactor core meltdown accident studies, the degrad...
Work performed at the Knolls Atomic Power Laboratory, Schenectady, New York.Other issues of this rep...
Uranium dioxide pellets sealed in Type 316 stainless steel containers with a helium gas were irradia...
Reduced activation ferritic/martensitic steel, F-82H (Fe-8Cr-2W-V-Ta), was irradiated in the High Fl...
Boron carbide-graphite nuclear control-rod materials containing up to 45 wt% B were prepared by hot-...
International audienceAlready used as neutron absorber in the current French nuclear reactors, boron...
"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...
"Contract No. W-7405-eng-92.""UC-25 Metallurgy and Ceramics (TID-4500, 14th Ed.).""April 21, 1959.""...
International audienceThis paper presents an in situ Transmission Electron Microscopy (TEM) study of...
International audienceThis paper presents a new methodology used to study transmutation damage in bo...
Zirconium carbide is a candidate to either replace or supplement silicon carbide as a coating materi...