Fuel relocation modeling in the SAS4A accident analysis code system

Conference · Tue Dec 31 23:00:00 EST 1985

OSTI ID:5547382

Tentner, A M; Miles, K J; Kalimullah,; Hill, D J

The SAS4A code system has been designed for the analysis of the initial phase of Hypothetical Core Disruptive Accidents (HCDAs) up to gross melting or failure of the subassembly walls. During such postulated accident scenarios as the Loss-of-Flow (LOF) and Transient-Overpower (TOP) events, the relocation of the fuel plays a key role in determining the sequence of events and the amount of energy produced before neutronic shutdown. This paper discusses the general strategy used in modelong the various phenomena which lead to fuel relocation and presents the key fuel relocation models used in SAS4A. The implications of these models for the whole-core accident analysis as well as recent results of fuel relocation are emphasized. 12 refs.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5547382
• Report Number(s): CONF-860501-11; ON: DE86012114
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
ENERGY SOURCES
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL PINS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATERIALS
MELTDOWN
NUCLEAR FUELS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR MATERIALS
REACTORS
S CODES
TRANSIENT OVERPOWER ACCIDENTS