Simulant-material experimental investigation of flow dynamics in the CRBR Upper-Core Structure
The results of a simulant-material experimental investigation of flow dynamics in the Clinch River Breeder Reactor (CRBR) Upper Core Structure are described. The methodology used to design the experimental apparatus and select test conditions is detailed. Numerous comparisons between experimental data and SIMMER-II Code calculations are presented with both advantages and limitations of the SIMMER modeling features identified.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6626900
- Report Number(s):
- NUREG/CR-2866; LA-9478-MS; ON: DE83004123
- Resource Relation:
- Other Information: Mf only; illegibility does not permit PC reproduction
- Country of Publication:
- United States
- Language:
- English
Similar Records
Brief analysis of the transient fluid flow at the entrance of the upper core structure during a hypothetical core expansion
Nonlinear analysis of the CRBR core restraint system
Assessment of CRBR core disruptive accident energetics
Technical Report
·
Wed Apr 01 00:00:00 EST 1981
·
OSTI ID:6626900
Nonlinear analysis of the CRBR core restraint system
Conference
·
Thu Jan 01 00:00:00 EST 1976
·
OSTI ID:6626900
Assessment of CRBR core disruptive accident energetics
Technical Report
·
Thu Mar 01 00:00:00 EST 1984
·
OSTI ID:6626900
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
REACTOR CORE DISRUPTION
REACTOR CORES
COMPUTER CALCULATIONS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
PRESSURE GRADIENTS
REACTOR SAFETY
TEST FACILITIES
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SODIUM COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
REACTOR CORE DISRUPTION
REACTOR CORES
COMPUTER CALCULATIONS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
PRESSURE GRADIENTS
REACTOR SAFETY
TEST FACILITIES
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SODIUM COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding