Modeling developments for the SAS4A and SASSYS computer codes
Description
The SAS4A and SASSYS computer codes are being developed at Argonne National Laboratory for transient analysis of liquid metal cooled reactors. The SAS4A code is designed to analyse severe loss-of-coolant flow and overpower accidents involving coolant boiling, Cladding failures, and fuel melting and relocation. Recent SAS4A modeling developments include extension of the coolant boiling model to treat sudden fission gas release upon pin failure, expansion of the DEFORM fuel behavior model to handle advanced cladding materials and metallic fuel, and addition of metallic fuel modeling capability to the PINACLE and LEVITATE fuel relocation models. The SASSYS code is intended for the analysis of operational and beyond-design-basis transients, and provides a detailed transient thermal and hydraulic simulation of the core, the primary and secondary coolant circuits, and the balance-of-plant, in addition to a detailed model of the plant control and protection systems. Recent SASSYS modeling developments have resulted in detailed representations of the balance of plant piping network and components, including steam generators, feedwater heaters and pumps, and the turbine. 12 refs., 2 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90010056; OSTI; INIS; US Govt. Printing Office Dep.Files
21076259.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- CONF-900804--10
Conference
- Title
- International topical meeting on fast reactor safety.
- Dates
- 12-16 Aug 1990.
- Place
- Snowbird, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21076259
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CORIUM; FEEDWATER; FISSION PRODUCT RELEASE; FUEL CANS; HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; LOSS OF COOLANT; PIPES; PUMPS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; S CODES; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; FBR TYPE REACTORS; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; OXYGEN COMPOUNDS; POLAR SOLVENTS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; SOLVENTS; VAPOR GENERATORS; WATER
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38