A series of quasi-steady state tests were made to study dynamic boiling and to determine a boiling region which would not lead to immediate dryout and pin failure in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility (previously the Fuel Failure Mockup), an engineering-scale sodium loop for testing simulated LMFBR fuel assemblies at normal and off-normal operating conditions. These tests were made on an assembly consisting of 19 electrically heated pins of the same configuration as FFTF fuel. Approximately 50 flow transients were so conducted to boiling or near boiling over a range of flows and powers. Dryout occurred at three test conditions
Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-o...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...
The recent modification of the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility at ORNL will...
Two-dimensional boiling effects may significantly influence the course of LOPI and LSHRS hypothetica...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
The most serious of the postulated accidents considered in the design of the Liquid Metal Cooled F...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
Calculational analysis of the unprotected loss of flow (ULOF) accident in a Generation-IV SFR, featu...
TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothe...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
Flow excursion induced dryout at low heat flux natural convection boiling, typical of liquid metal f...
Experimental and analytical investigations performed in the United States, Germany, Great Britain, a...
International audienceIn the framework of the research and development on GEN IV sodium fast reactor...
Two important correlations have been obtained to calculate the maximum coolant temperature and the N...
Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-o...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...
The recent modification of the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility at ORNL will...
Two-dimensional boiling effects may significantly influence the course of LOPI and LSHRS hypothetica...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
The most serious of the postulated accidents considered in the design of the Liquid Metal Cooled F...
The W-1 Sodium Loop Safety Facility (SLSF) experiment was designed to study the heat release charact...
Calculational analysis of the unprotected loss of flow (ULOF) accident in a Generation-IV SFR, featu...
TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothe...
The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combin...
Flow excursion induced dryout at low heat flux natural convection boiling, typical of liquid metal f...
Experimental and analytical investigations performed in the United States, Germany, Great Britain, a...
International audienceIn the framework of the research and development on GEN IV sodium fast reactor...
Two important correlations have been obtained to calculate the maximum coolant temperature and the N...
Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-o...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...