In-vessel thermal-hydraulic analysis
Conference
·
OSTI ID:6210792
This paper presents some recent results obtained from the COMMIX-1A code for the EBR-II reactor transient No. 10, Phase 2. Both the reactor vessel and the neutron shield assembly and assembly arrangement in the reactor core are shown. The computational grid system used in COMMIX-1A is presented. Reactor flow and power transients are shown. Velocity and temperature distributions at steady state and t (time) = 60 sec are included. Finally, a comparison between the calculated results from COMMIX-1A and experimental measurements are presented for outlet temperatures for driver subassembly of XX08, top-of-core temperature for driver subassembly of XX08, and low-pressure plenum mass flow respectively.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6210792
- Report Number(s):
- CONF-830132-1; ON: DE83009534
- Country of Publication:
- United States
- Language:
- English
Similar Records
EBR-II in-vessel natural-circulation analysis
EBR-II environmental instrumented subassembly XX08: engineering and assembly
COMMIX-1A three-dimensional in-vessel simulation of the FFTF thermal hydraulics
Technical Report
·
Wed Sep 01 00:00:00 EDT 1982
·
OSTI ID:6607202
EBR-II environmental instrumented subassembly XX08: engineering and assembly
Technical Report
·
Mon May 01 00:00:00 EDT 1978
·
OSTI ID:6591632
COMMIX-1A three-dimensional in-vessel simulation of the FFTF thermal hydraulics
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5339210
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
COMPUTER CALCULATIONS
EBR-2 REACTOR
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
TEMPERATURE DISTRIBUTION
TEMPERATURE GRADIENTS
TRANSIENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
COMPUTER CALCULATIONS
EBR-2 REACTOR
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
TEMPERATURE DISTRIBUTION
TEMPERATURE GRADIENTS
TRANSIENTS