Fuel relocation modeling in the SAS4A accident analysis code system
Conference
·
OSTI ID:6065222
SAS4A is a new code system which has been designed for analyzing 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 modeling 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 motion experiment analyses are also presented.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6065222
- Report Number(s):
- CONF-850410-27; ON: DE85005104
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel relocation modeling in the SAS4A accident analysis code system
Status and validation of the SAS4A accident-analysis code system
Simulating unprotected accidents for advanced liquid metal reactors using the SAS4A accident analysis code
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:5547382
Status and validation of the SAS4A accident-analysis code system
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6488100
Simulating unprotected accidents for advanced liquid metal reactors using the SAS4A accident analysis code
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:5011228
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 CALCULATIONS
CORIUM
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENT FAILURE
HYDRAULICS
HYDRODYNAMICS
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
CORIUM
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENT FAILURE
HYDRAULICS
HYDRODYNAMICS
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY