Experimental and analytical investigations performed in the United States, Germany, Great Britain, and Japan on the effects of partial flow blockages in liquid-metal fast breeder reactor fuel assemblies are reviewed and the results presented. Generalized models are developed from experimental data obtained for blockages of various sizes, shapes, and porosity, with and without pins, utilizing water and sodium as the coolant. Generally, the recirculating flow in the wake behind a blockage is a relatively effective heat transfer mechanism. Experiments where sodium boiling was made to occur behind the blockages indicate that boiling is stable for the configurations tested; these results are predicted by analytical models. Blockages at the inlet...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Heat transfer coefficients were experimentally determined for 31-rod sodium-cooled bundle with a 6-s...
"September, 1973."Includes bibliographical references (pages [40]-[44])U.S. Atomic Energy Commission...
To assess the effect of partial flow blockages on the local temperature distributions in LMFBR fuel ...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a f...
Two important correlations have been obtained to calculate the maximum coolant temperature and the N...
When a nuclear reactor with rectangular fuel assemblies runs for a long time, impurities and debris ...
Flow blockage of the fuel assembly in the lead-based fast reactor (LFR) may produce critical local s...
Several innovative solutions for a liquid metal fast reactor design are being investigated. Among th...
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a f...
Liquid metal fast reactors often use a tightly packed triangular lattice of fuel pins that are helic...
The most serious of the postulated accidents considered in the design of the Liquid Metal Cooled F...
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a f...
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...
Heat transfer coefficients were experimentally determined for 31-rod sodium-cooled bundle with a 6-s...
"September, 1973."Includes bibliographical references (pages [40]-[44])U.S. Atomic Energy Commission...
To assess the effect of partial flow blockages on the local temperature distributions in LMFBR fuel ...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a f...
Two important correlations have been obtained to calculate the maximum coolant temperature and the N...
When a nuclear reactor with rectangular fuel assemblies runs for a long time, impurities and debris ...
Flow blockage of the fuel assembly in the lead-based fast reactor (LFR) may produce critical local s...
Several innovative solutions for a liquid metal fast reactor design are being investigated. Among th...
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a f...
Liquid metal fast reactors often use a tightly packed triangular lattice of fuel pins that are helic...
The most serious of the postulated accidents considered in the design of the Liquid Metal Cooled F...
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a f...
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...
Heat transfer coefficients were experimentally determined for 31-rod sodium-cooled bundle with a 6-s...
"September, 1973."Includes bibliographical references (pages [40]-[44])U.S. Atomic Energy Commission...