SASSYS-1 modelling of RVACS (Reactor Vessel Auxiliary Cooling System)/RACS (Reactor Air Cooling System) heat removal in an LMR (Liquid Metal Reactor)
The SASSYS-1 Liquid Metal Reactor (LMR) systems analysis code contains a model for transient analysis of heat removal by a RVACS (Reactor Vessel Auxiliary Cooling System) or a RACS (Reactor Air Cooling System) in an LMR (Liquid Metal Reactor). This air-side RVACS/RACS model is coupled with the sodium-side primary loop thermal hydraulics model in SASSYS-1 to give a complete treatment of the problem. Application of this model to an unprotected loss-of-flow event in the PRISM reactor shows that in the long run the RVACS cooling is sufficient to prevent unacceptably high system temperatures in this case. Part II provides a general description of the RVACS/RACS model. Part III lists some of the basic equations used in the model, and Part IV describes an application to an unprotected LOF (Loss-of-Flow) event in PRISM.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5993270
- Report Number(s):
- CONF-871101-15; ON: DE87011370; TRN: 87-035096
- Resource Relation:
- Conference: California State Air Resources Board, Los Angeles, CA, USA, 15 Nov 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Validation of the RVACS (Reactor Vessel Auxiliary Cooling System)/RACS (Reactor Air Cooling System) model in SASSYS-1
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HEAT TRANSFER
S CODES
LMFBR TYPE REACTORS
REACTOR VESSELS
REACTOR COOLING SYSTEMS
COMPUTERIZED SIMULATION
FINITE DIFFERENCE METHOD
HYDRAULICS
LOSS OF FLOW
MATHEMATICAL MODELS
REACTOR SAFETY
SYSTEMS ANALYSIS
TRANSIENTS
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
ITERATIVE METHODS
LIQUID METAL COOLED REACTORS
MECHANICS
NUMERICAL SOLUTION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SIMULATION
210500* - Power Reactors
Breeding
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)