Assessment of TRAC-PF1/MOD3 Mark-22 assembly model using SRL A'' tank single-assembly flow experiments
Conference
·
OSTI ID:6004430
This paper summarizes the results of an assessment of our TRAC-PF1/MOD3 Mark-22 prototype fuel assembly model against single-assembly data obtained from the A'' Tank single-assembly tests that were performed at the Savannah River Laboratory. We felt the data characterize prototypic assembly behavior over a range of air-water flow conditions of interest for loss-of-coolant accident (LOCA) calculations. This study was part of a benchmarking effort performed to evaluate and validate a multiple-assembly, full-plant model that is being developed by Los Alamos National Laboratory to study various aspects of the Savannah River plant operating conditions, including LOCA transients, using TRAC-PF1/MOD3 Version 1.10. The results of this benchmarking effort demonstrate that TRAC-PF1/MOD3 is capable pf calculating plenum conditions and assembly flows during conditions thought to be typical of the Emergency Cooling System (ECS) phase of a LOCA. 10 refs., 12 fig.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6004430
- Report Number(s):
- LA-UR-91-826; CONF-910714--4; ON: DE91009945
- Country of Publication:
- United States
- Language:
- English
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· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6178346
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AIR FLOW
BENCHMARKS
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
CONTAINERS
COOLANTS
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
GAS FLOW
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NUMERICAL DATA
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANKS
TEST FACILITIES
TEST REACTORS
TWO-PHASE FLOW
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AIR FLOW
BENCHMARKS
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
CONTAINERS
COOLANTS
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
GAS FLOW
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NUMERICAL DATA
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANKS
TEST FACILITIES
TEST REACTORS
TWO-PHASE FLOW