SASSYS-1 computer code verification with EBR-II test data
Conference
·
OSTI ID:5624188
The EBR-II natural circulation experiment, XX08 Test 8A, is simulated with the SASSYS-1 computer code and the results for the latter are compared with published data taken during the transient at selected points in the core. The SASSYS-1 results provide transient temperature and flow responses for all points of interest simultaneously during one run, once such basic parameters as pipe sizes, initial core flows, and elevations are specified. The SASSYS-1 simulation results for the EBR-II experiment XX08 Test 8A, conducted in March 1979, are within the published plant data uncertainties and, thereby, serve as a partial verification/validation of the SASSYS-1 code.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5624188
- Report Number(s):
- CONF-850410-46; ON: DE85012119
- Resource Relation:
- Conference: ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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EBR-2 REACTOR
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LOSS OF FLOW
NATURAL CONVECTION
COMPUTER CODES
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VALIDATION
ACCIDENTS
BREEDER REACTORS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MASS TRANSFER
POWER REACTORS
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RESEARCH AND TEST REACTORS
SIMULATION
SODIUM COOLED REACTORS
TESTING
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
EBR-2 REACTOR
COMPUTERIZED SIMULATION
LOSS OF FLOW
NATURAL CONVECTION
COMPUTER CODES
S CODES
VALIDATION
ACCIDENTS
BREEDER REACTORS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MASS TRANSFER
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
SODIUM COOLED REACTORS
TESTING
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors