Monolithic fuel plates are being developed for application in research reactors throughout the world. These fuel plates are comprised of a U-Mo alloy foil encased in aluminum alloy cladding. Three different fabrication techniques have been looked at for producing monolithic fuel plates: hot isostatic pressing (HIP), transient liquid phase bonding (TLPB), and friction stir welding (FSW). Of these three techniques, HIP and FSW are currently being emphasized. As part of the development of these fabrication techniques, fuel plates are characterized and tested to determine properties like hardness and the bond strength at the interface between the fuel and cladding. Testing of HIPed samples indicates that the foil/cladding interaction behavior d...
The need to provide more accurate property information on U-Mo fuel alloys to reactor operators, mod...
The objective of this investigation is to develop a shear punch testing (SPT) procedure and standard...
This paper discusses how candidate fuel plates for RERTR Fuel Development experiments are examined a...
Results on the relative bond strength of the fuel-clad interface in monolithic fuel plates have been...
Understanding fuel foil mechanical properties, and fuel / cladding bond quality and strength in mono...
Interaction between U-Mo fuel and Al has proven to dramatically impact the overall irradiation perfo...
The pursuit of a high uranium density research reactor fuel plate has led to monolithic fuel, which ...
Evaluation of the PIE results of the monolithic plates that were irradiated as part of the RERTR-6 e...
Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National ...
Within the Reduced Enrichment for Research and Test Reactors (RERTR) program directed by the US Depa...
Engineering of nuclear fuels using monolithic plates of uranium-molybdenum and Al-6061 clad-ding is ...
Monolithic nuclear fuel is currently being developed for use in research reactors, and friction bond...
Full-size U-10Mo foils are being developed for use in high density LEU monolithic fuel plates. The a...
Full-size/prototypic U10Mo monolithic fuel-foils and aluminum clad fuel plates are being developed a...
Full-size U10Mo foils are being developed for use in high density LEU monolithic fuel plates. The ap...
The need to provide more accurate property information on U-Mo fuel alloys to reactor operators, mod...
The objective of this investigation is to develop a shear punch testing (SPT) procedure and standard...
This paper discusses how candidate fuel plates for RERTR Fuel Development experiments are examined a...
Results on the relative bond strength of the fuel-clad interface in monolithic fuel plates have been...
Understanding fuel foil mechanical properties, and fuel / cladding bond quality and strength in mono...
Interaction between U-Mo fuel and Al has proven to dramatically impact the overall irradiation perfo...
The pursuit of a high uranium density research reactor fuel plate has led to monolithic fuel, which ...
Evaluation of the PIE results of the monolithic plates that were irradiated as part of the RERTR-6 e...
Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National ...
Within the Reduced Enrichment for Research and Test Reactors (RERTR) program directed by the US Depa...
Engineering of nuclear fuels using monolithic plates of uranium-molybdenum and Al-6061 clad-ding is ...
Monolithic nuclear fuel is currently being developed for use in research reactors, and friction bond...
Full-size U-10Mo foils are being developed for use in high density LEU monolithic fuel plates. The a...
Full-size/prototypic U10Mo monolithic fuel-foils and aluminum clad fuel plates are being developed a...
Full-size U10Mo foils are being developed for use in high density LEU monolithic fuel plates. The ap...
The need to provide more accurate property information on U-Mo fuel alloys to reactor operators, mod...
The objective of this investigation is to develop a shear punch testing (SPT) procedure and standard...
This paper discusses how candidate fuel plates for RERTR Fuel Development experiments are examined a...