The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponsored by the Department of Energy (DOE) as part of the National Fast Breeder Reactor (FBR) Safety Assurance Program. The experiments are being conducted under the direction of Argonne National Laboratory (ANL) and Hanford Engineering Development Laboratory (HEDL). The irradiation phase of the W-1 SLSF experiment was conducted between May 27 and July 20, 1979, and terminated with incipient fuel pin cladding failure during the final boiling transient. Experimental hardware and facility performed as designed, allowing completion of all planned tests and test objectives. This paper focuses on high temperature in-fuel thermocouples and discusses the...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
Many advanced nuclear reactor designs require new fuel, cladding and structural materials. Data are ...
In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehen...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
The purpose of this project is to provide a sodium-cooled fast flux test reactor designed specifical...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
AbstractThe thermal, mechanical, and neutronic performance of the metal alloy fast reactor fuel desi...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
The superior uranium utilization efficiency of fast spectrum reactors relative to thermal spectrum r...
Many advanced nuclear reactor designs require new fuel, cladding, and structural materials. Data are...
AbstractTwo independent sodium loops under common name INSOT facilities were constructed in Fast Rea...
The W-2 SLSF (Sodium Loop Safety Facility) experiment was an instrumented in-reactor test performed ...
Many advanced nuclear reactor designs require new fuel, cladding, and structural materials. Data are...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
Many advanced nuclear reactor designs require new fuel, cladding and structural materials. Data are ...
In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehen...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
The purpose of this project is to provide a sodium-cooled fast flux test reactor designed specifical...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
AbstractThe thermal, mechanical, and neutronic performance of the metal alloy fast reactor fuel desi...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
The superior uranium utilization efficiency of fast spectrum reactors relative to thermal spectrum r...
Many advanced nuclear reactor designs require new fuel, cladding, and structural materials. Data are...
AbstractTwo independent sodium loops under common name INSOT facilities were constructed in Fast Rea...
The W-2 SLSF (Sodium Loop Safety Facility) experiment was an instrumented in-reactor test performed ...
Many advanced nuclear reactor designs require new fuel, cladding, and structural materials. Data are...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
Many advanced nuclear reactor designs require new fuel, cladding and structural materials. Data are ...