Molten fuel motion during a fast-reactor overpower transient
Conference
·
OSTI ID:7325306
Mechanistic models for postfailure fuel behavior during hypothetical transient overpower accidents are currently being developed for incorporation into the MELT accident analysis code. A new model for the fuel-coolant interaction and for the motion of fuel in the coolant channel has been developed and incorporated into the MELT-III code. A major limitation of the mechanistic fuel motion model is its dependence on the uniform interaction region of MELT-III. Consequently, a parallel effort is currently in progress to incorporate a non-uniform interaction region into the MELT code. Combination of the fuel motion and the nonuniform interaction region models will provide the framework for development of a mechanistic fuel plateout/blockage model for transient overpower accidents.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-2170
- OSTI ID:
- 7325306
- Report Number(s):
- HEDL-SA-841; CONF-761001-35
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparison of SAS3A and MELT-III predictions for a transient overpower hypothetical accident
FUMO-E: an internal fuel motion model for annular fuel. [LMFBR]
FUMO-E: an internal fuel motion model for annular fuel. [LMFBR]
Conference
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:7334754
FUMO-E: an internal fuel motion model for annular fuel. [LMFBR]
Conference
·
Sat Oct 31 23:00:00 EST 1981
·
OSTI ID:5536570
FUMO-E: an internal fuel motion model for annular fuel. [LMFBR]
Technical Report
·
Wed Jul 01 00:00:00 EDT 1981
·
OSTI ID:5330810
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
EPITHERMAL REACTORS
EXCURSIONS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
M CODES
MATHEMATICAL MODELS
MELTDOWN
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
EPITHERMAL REACTORS
EXCURSIONS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
M CODES
MATHEMATICAL MODELS
MELTDOWN
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS