The purpose of this project is to provide a sodium-cooled fast flux test reactor designed specifically for irradiation testing of fuels and materials and for long-term testing and evaluation of plant components and systems for the Liquid Metal Reactor (LMR) Program. The FFTF includes the reactor, heat removal equipment and structures, containment, core component handling and examination, instrumentation and control, and utilities and other essential services. The complex array of buildings and equipment are arranged around the Reactor Containment Building
The Department of Energy's (DOE) responsibility for the disposition of radioactive materials has giv...
Unirradiated sodium bonded metal fuel and casting scrap material containing highly enriched uranium ...
The superior uranium utilization efficiency of fast spectrum reactors relative to thermal spectrum r...
A general description of the FFTF is presented concerning the construction progress; status of start...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponso...
The Fast Flux Test Facility (FFTF) was a 400-MWt, sodium-cooled, low-pressure, high-temperature, fas...
Static corrosion tests in sodium and in fused-fluoride-salt mixture on type 310 stainless steel T-jo...
The Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) of the Idaho Nati...
This paper discusses operational and criticality safety experience associated with the Idaho Nationa...
In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehen...
The Gas-Cooled Fast Reactor (GFR) is one of six systems selected for viability assessment in the Gen...
Cavity reactor critical experiments with full gaseous core of uranium hexafluoride, and mockup exper...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
The US Liquid Metal Reactor Development Program has been restructured to take advantage of the oppor...
The Department of Energy's (DOE) responsibility for the disposition of radioactive materials has giv...
Unirradiated sodium bonded metal fuel and casting scrap material containing highly enriched uranium ...
The superior uranium utilization efficiency of fast spectrum reactors relative to thermal spectrum r...
A general description of the FFTF is presented concerning the construction progress; status of start...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponso...
The Fast Flux Test Facility (FFTF) was a 400-MWt, sodium-cooled, low-pressure, high-temperature, fas...
Static corrosion tests in sodium and in fused-fluoride-salt mixture on type 310 stainless steel T-jo...
The Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) of the Idaho Nati...
This paper discusses operational and criticality safety experience associated with the Idaho Nationa...
In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehen...
The Gas-Cooled Fast Reactor (GFR) is one of six systems selected for viability assessment in the Gen...
Cavity reactor critical experiments with full gaseous core of uranium hexafluoride, and mockup exper...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
The US Liquid Metal Reactor Development Program has been restructured to take advantage of the oppor...
The Department of Energy's (DOE) responsibility for the disposition of radioactive materials has giv...
Unirradiated sodium bonded metal fuel and casting scrap material containing highly enriched uranium ...
The superior uranium utilization efficiency of fast spectrum reactors relative to thermal spectrum r...