In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehensive posttest examinations (PTE) to characterize the postirradiation condition of the cladding, fuel, and other test-subassembly components. PTE information and on-line instrumentation data, are analyzed to identify the sequence of events and the severity of the accident for each experiment. Following in-reactor experimentation, the SLSF loop and test assembly are transported to the Hot Fuel Examination Facility (HFEF) for initial disassembly. Goals of the HFEF-phase of the PTE are to retrieve the fuel bundle by dismantling the loop and withdrawing the test assembly, to assess the macro-condition of the fuel bundle by nondestructive examinati...
The objective is to provide a test facility for in-sodium simulations of conditions following a majo...
As the end of World War II approached, scientists who developed the processes to generate nuclear ma...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponso...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
AbstractTwo independent sodium loops under common name INSOT facilities were constructed in Fast Rea...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothe...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
AbstractThe design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the...
AbstractThe thermal, mechanical, and neutronic performance of the metal alloy fast reactor fuel desi...
Two three-pin cluster tests simulating the Unprotected Loss-of-Flow (ULOF) accident of Sodiumcooled ...
The objective is to provide a test facility for in-sodium simulations of conditions following a majo...
As the end of World War II approached, scientists who developed the processes to generate nuclear ma...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponso...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
AbstractTwo independent sodium loops under common name INSOT facilities were constructed in Fast Rea...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothe...
Measurements of the reaction of methane with sodium have been extended to 1400°F, where 100 ppm in h...
AbstractThe design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the...
AbstractThe thermal, mechanical, and neutronic performance of the metal alloy fast reactor fuel desi...
Two three-pin cluster tests simulating the Unprotected Loss-of-Flow (ULOF) accident of Sodiumcooled ...
The objective is to provide a test facility for in-sodium simulations of conditions following a majo...
As the end of World War II approached, scientists who developed the processes to generate nuclear ma...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...