Comparison of SAS3A and MELT-III predictions for a transient overpower hypothetical accident
Conference
·
OSTI ID:7334754
A comparison is made of the predictions of the two major codes SAS3A and MELT-III for the hypothetical unprotected transient overpower accident in the FFTF. The predictions of temperatures, fuel restructuring, fuel melting, reactivity feedbacks, and core power are compared.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-2170
- OSTI ID:
- 7334754
- Report Number(s):
- HEDL-SA-842; CONF-761001-10
- Country of Publication:
- United States
- Language:
- English
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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
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
KINETICS
LIQUID METAL COOLED REACTORS
MATHEMATICAL MODELS
MELTING
PHASE TRANSFORMATIONS
POWER DISTRIBUTION
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEMPERATURE DISTRIBUTION
TEST REACTORS
TRANSIENTS
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
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
KINETICS
LIQUID METAL COOLED REACTORS
MATHEMATICAL MODELS
MELTING
PHASE TRANSFORMATIONS
POWER DISTRIBUTION
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEMPERATURE DISTRIBUTION
TEST REACTORS
TRANSIENTS