Molten clad motion model for fast reactor loss-of-flow accidents. [LMFBR]
Journal Article
·
· Nucl. Sci. Eng.; (United States)
The motion and location of the molten clad during an unprotected loss-of-flow accident in liquid-metal fast breeder reactors are very important because of their effect on the reactivity and the subsequent fuel motion. The study presented analyzes the clad relocation problem based on a single-channel film flow model and a simple thermal transient model for fuel pins. The motion of molten clad induced by sodium vapor streaming undergoes initial rapid upward acceleration, slowing down, flow reversal, and eventual slumping down into liquid sodium at the lower end of the heated section. A possibility for freezing of the molten clad at the unheated upper plenum region as well as bottom freezing and blockage formation were also included in the analysis. A sample calculation has been made for the case of R-series 7-pin tests in the Transient Reactor Test Facility. The agreement of the overall physical behavior of the clad motion with the post-test observations is quite satisfactory.
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 7334727
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 60:4; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Multichannel model for relocation of molten fuel cladding in unprotected loss-of-flow accidents in liquid-metal fast breeder reactors
Multichannel clad-relocation model for fast-reactor loss-of-flow accidents
Molten fuel containment analysis for SLSF experiments. [LMFBR]
Journal Article
·
Wed Jan 31 23:00:00 EST 1979
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:6493735
Multichannel clad-relocation model for fast-reactor loss-of-flow accidents
Technical Report
·
Wed Aug 01 00:00:00 EDT 1979
·
OSTI ID:5943049
Molten fuel containment analysis for SLSF experiments. [LMFBR]
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:5981990
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
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATHEMATICAL MODELS
MELTDOWN
REACTOR ACCIDENTS
REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATHEMATICAL MODELS
MELTDOWN
REACTOR ACCIDENTS
REACTORS