The need to provide more accurate property information on U-Mo fuel alloys to reactor operators, modelers, researchers, fabricators, and regulators increases as success of the RERTR program continues. This presentation will provide an overview of fresh fuel U-Mo characterization activities on monolithic fuel occurring at the Idaho National Laboratory. The overview will particularly be focused on properties available through current and previous research, and also on the type of information still needed. The presentation will deal with mechanical, physical, and microstructural properties in terms of both integrated and separate effects. Appropriate discussion in terms of fabrication characteristics, impurities, thermodynamic response, and th...
RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughou...
The Materials Management and Minimization (M3) Program intends to qualify a new high-density low-enr...
Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National ...
Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. Th...
High-performance research reactors require fuel that operates at high specific power to high fission...
The pursuit of a high uranium density research reactor fuel plate has led to monolithic fuel, which ...
Monolithic fuel plates are being developed for application in research reactors throughout the world...
The objective of this investigation is to develop a shear punch testing (SPT) procedure and standard...
A variety of phases have the potential to develop in the irradiated fuels for the reduced enrichment...
High-performance research reactors require fuel that operates at high specific power to high fission...
; 9 < 4 6 9 7 ; 6 8 7 6 sting Deactor (MTR) has sought to develop improved, economical, long-life fu...
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...
Three depleted uranium alloys are successfully cast for the radiation stability studies of the fuel-...
The Materials Management and Minimization (M3) Program intends to qualify a new high‑density low‑enr...
RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughou...
The Materials Management and Minimization (M3) Program intends to qualify a new high-density low-enr...
Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National ...
Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. Th...
High-performance research reactors require fuel that operates at high specific power to high fission...
The pursuit of a high uranium density research reactor fuel plate has led to monolithic fuel, which ...
Monolithic fuel plates are being developed for application in research reactors throughout the world...
The objective of this investigation is to develop a shear punch testing (SPT) procedure and standard...
A variety of phases have the potential to develop in the irradiated fuels for the reduced enrichment...
High-performance research reactors require fuel that operates at high specific power to high fission...
; 9 < 4 6 9 7 ; 6 8 7 6 sting Deactor (MTR) has sought to develop improved, economical, long-life fu...
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...
Three depleted uranium alloys are successfully cast for the radiation stability studies of the fuel-...
The Materials Management and Minimization (M3) Program intends to qualify a new high‑density low‑enr...
RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughou...
The Materials Management and Minimization (M3) Program intends to qualify a new high-density low-enr...
Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National ...