Comparison of the SASSYS/SAS4A radial core expansion reactivity feedback model and the empirical correlation for the FFTF
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6830060
The present emphasis on inherent safety for liquid-metal reactor designs has resulted in a need to represent the various reactivity feedback mechanisms as accurately as possible. The dominant negative reactivity feedback has been found to result from radial expansion of the core for most postulated anticipated transient without scram events. For this reasons, a more detailed model for calculating the reactivity feedback from radial core expansion, including subassembly bowing has been recently developed for use with the SASSYS/SAS4A code system. The purpose of this summary is to present an extension to the model so that it is more suitable for handling a core restraint design as used in the Fast Flux Test Facility (FFTF), and to compare the SASSYS/SAS4A results using this model to the empirical correlation presently being used to account for radial core expansion reactivity feedback in the FFTF.
- Research Organization:
- Argonne National Lab., IL (USA)
- OSTI ID:
- 6830060
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
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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
ACCURACY
ATWS
COMPUTER CODES
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
KINETICS
LIQUID METAL COOLED REACTORS
POWER DISTRIBUTION
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE RESTRAINTS
REACTOR CORES
REACTOR KINETICS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
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RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RESTRAINTS
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SODIUM COOLED REACTORS
TEST REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACCURACY
ATWS
COMPUTER CODES
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
KINETICS
LIQUID METAL COOLED REACTORS
POWER DISTRIBUTION
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE RESTRAINTS
REACTOR CORES
REACTOR KINETICS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RESTRAINTS
S CODES
SODIUM COOLED REACTORS
TEST REACTORS