Additional capabilities and benchmarking with the SPERT transients for heavy water application of the PARET code
Conference
·
OSTI ID:5273038
The capabilities of the PARET code have been expanded to include the ability to compute steady-state and transient results for heavy water reactors. A comparison is provided between PARET and the SPERT II series of transients. Another significant improvement in the code is the addition of a restart capability. The current capabilities of the code are summarized. 7 refs., 12 figs., 3 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- ACDA; DOE/IE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5273038
- Report Number(s):
- CONF-8909141-9; ON: DE90003801; TRN: 90-000955
- Resource Relation:
- Conference: 12. international meeting on reduced enrichment for research and test reactors, Berlin (Germany, F.R.), 10-13 Sep 1989
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HEAVY WATER COOLED REACTORS
TRANSIENTS
SPERT-2 REACTOR
BENCHMARKS
CLADDING
EXPERIMENTAL DATA
FEEDBACK
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
NUSSELT NUMBER
P CODES
PERFORMANCE TESTING
PRESSURE EFFECTS
REACTOR START-UP
SIMULATION
SPERT-1 REACTOR
SYSTEMS ANALYSIS
TEMPERATURE EFFECTS
COMPUTER CODES
DATA
DEPOSITION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FLUID MECHANICS
HEAVY WATER MODERATED REACTORS
INFORMATION
MECHANICS
NUMERICAL DATA
OPERATION
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
START-UP
SURFACE COATING
TANK TYPE REACTORS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
990200 - Mathematics & Computers
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HEAVY WATER COOLED REACTORS
TRANSIENTS
SPERT-2 REACTOR
BENCHMARKS
CLADDING
EXPERIMENTAL DATA
FEEDBACK
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
NUSSELT NUMBER
P CODES
PERFORMANCE TESTING
PRESSURE EFFECTS
REACTOR START-UP
SIMULATION
SPERT-1 REACTOR
SYSTEMS ANALYSIS
TEMPERATURE EFFECTS
COMPUTER CODES
DATA
DEPOSITION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FLUID MECHANICS
HEAVY WATER MODERATED REACTORS
INFORMATION
MECHANICS
NUMERICAL DATA
OPERATION
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
START-UP
SURFACE COATING
TANK TYPE REACTORS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
990200 - Mathematics & Computers