The objective is to provide a test facility for in-sodium simulations of conditions following a major loss-of-coolant accident. These tests are intended to provide information on the carry-over of fuel material from a boiling sodium pool
The instellation is designed primarily for operational testing of Na- heated steam generators and in...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
Reactor vessel auxiliary cooling system (RVACS) has been developed to make diverse safety system for...
The objectives of this project are to: develop a computer program for calculating two-dimensional, t...
In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehen...
TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothe...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Two 37-pin scale models of Clinch River Breeder Reactor Plant fuel subassemblies were designed, fabr...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
Generator IV and other nuclear fast reactors have historically used liquid sodium as a coolant. The ...
The objectives of the research program are to develop a computer program for calculating two-dimensi...
The loss-of-reactor-level (LORL) where the coolant circulation path is lost is one of the important ...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
The instellation is designed primarily for operational testing of Na- heated steam generators and in...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
Reactor vessel auxiliary cooling system (RVACS) has been developed to make diverse safety system for...
The objectives of this project are to: develop a computer program for calculating two-dimensional, t...
In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehen...
TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothe...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Two 37-pin scale models of Clinch River Breeder Reactor Plant fuel subassemblies were designed, fabr...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
Generator IV and other nuclear fast reactors have historically used liquid sodium as a coolant. The ...
The objectives of the research program are to develop a computer program for calculating two-dimensi...
The loss-of-reactor-level (LORL) where the coolant circulation path is lost is one of the important ...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
The instellation is designed primarily for operational testing of Na- heated steam generators and in...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
Reactor vessel auxiliary cooling system (RVACS) has been developed to make diverse safety system for...
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