SASSYS analysis of EBR-II SHRT experiments
Conference
·
OSTI ID:6156233
SASSYS is a general purpose one-dimensional thermal-hydraulic LMR systems analysis code. The application of SASSYS to studies of protected and unprotected transient analysis of LMR designs, such as PRISM and SAFR, is commonplace. This usage requires that a strong validation base exist for SASSYS. Validation of a code such as SASSYS is made up of a variety of activities such as, application of separate component models to model problems where the solution is analytically known, cross comparison with other codes and, most importantly, comparison with experiment. The EBR-II reactor is being used to perform experiments that address a wide range of LMR safety issues. The most important of these so far have been the SHRT series of experiments, begun in 1984, which culminated in the unprotected loss-of-flow and loss-of-heat sink transients performed as a demonstration to an international audience of fast reactor experts. The SASSYS-1 systems thermal hydraulic code for LMR's has been applied to the analysis of selected EBR-II SHRT experiments. The results show that SASSYS can predict the transient thermal hydraulic and reactivity behavior of EBR-II under these conditions. This contributes to the validation of the modelling of EBR-II with SASSYS and of the code itself.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6156233
- Report Number(s):
- CONF-871101-20; ON: DE87011371
- Country of Publication:
- United States
- Language:
- English
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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
ACCIDENTS
BREEDER REACTORS
CENTRIFUGAL PUMPS
COMPUTER CODES
COOLING SYSTEMS
DESIGN
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENT PLANNING
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
ONE-DIMENSIONAL CALCULATIONS
PLANNING
POWER REACTORS
PUMPS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SODIUM COOLED REACTORS
SYSTEMS ANALYSIS
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
ACCIDENTS
BREEDER REACTORS
CENTRIFUGAL PUMPS
COMPUTER CODES
COOLING SYSTEMS
DESIGN
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENT PLANNING
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
ONE-DIMENSIONAL CALCULATIONS
PLANNING
POWER REACTORS
PUMPS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SODIUM COOLED REACTORS
SYSTEMS ANALYSIS
TRANSIENTS