An improved steam generator model for the SASSYS code

Conference · Tue Oct 31 23:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5478117

Pizzica, P A ^[1]

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1. Argonne National Laboratory, IL (USA)

A new steam generator model has been developed for the SASSYS computer code, which analyzes accident conditions in a liquid-metal-cooled fast reactor. It has been incorporated into the new SASSYS balance-of-plant model, but it can also function as a stand-alone model. The model provides a full solution of the steady-state condition before the transient calculation begins for given sodium and water flow rates, inlet and outlet sodium temperatures, and inlet enthalpy and region lengths on the water side.

• OSTI ID: 5478117
• Report Number(s): CONF-891103--
• Journal Information: Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 60; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
BOILING
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
CONTROL ELEMENTS
COOLING SYSTEMS
CRAY COMPUTERS
EFFICIENCY
ENERGY SYSTEMS
ENERGY TRANSFER
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
LIQUID METAL COOLED REACTORS
MECHANICS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
S CODES
SAFETY
SECONDARY COOLANT CIRCUITS
SIMULATION
STEAM GENERATORS
TRANSIENTS
VAPOR GENERATORS
WATER