Comparison of FFTF (Fast Flux Test Facility) feedback reactivities with SASSYS calculations in a loss-of-flow-without-scram event
Conference
·
OSTI ID:6877122
The Cycle 8A static tests conducted in the Fast Flux Test Facility (FFTF) during 1986 have resulted in the separation of various feedback reactivity components. These feedback components, described by closed-form equations depending only on the reactor temperature field, can be regarded as database for the validation and/or calibration of feedback mechanistic models. The SASSYS safety analysis code contains the most developed feedback reactivity models and was selected for the comparison study between database and mechanistic calculations for the FFTF. Although detailed feedback models for control rod repositioning and core radial expansion/bowing exist, only the simple models were available in SASSYS at the time of this study. The results are described in this paper.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6877122
- Report Number(s):
- WHC-SA-0285; CONF-880506-25; ON: DE89000516
- Country of Publication:
- United States
- Language:
- English
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· Trans. Am. Nucl. Soc.; (United States)
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
DATA BASE MANAGEMENT
EPITHERMAL REACTORS
FAST REACTORS
FEEDBACK
FFTF REACTOR
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
MANAGEMENT
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
S CODES
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
DATA BASE MANAGEMENT
EPITHERMAL REACTORS
FAST REACTORS
FEEDBACK
FFTF REACTOR
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
MANAGEMENT
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
S CODES
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS