An analysis of initiating and transition phases for an unprotected loss-of-flow accident in an axially heterogeneous fast breeder reactor core
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6611475
An unprotected loss-of-flow (LOF) event has been analyzed for a 1000-MW (electric) axially heterogenous core (AHC) at the end of an equilibrium cycle, using a realistic model to evaluate the AHC safety potential. The SAS3D code was used for the initiating phase analysis, while a phenomenological approach was employed for the transition phase. The SAS3D results showed that the system rapidly approached subcriticality after experiencing a benign power burst, because of axially flattened fuel worth distribution and reduced sodium-void worth particularly around the core center. During the transition phase, fuel-steel discharge into the interassembly gaps, coupled with engagement of the upper axial blanket material in the core region, was found to result in permanent subcriticality and nonenergetic termination of the LOF event.
- Research Organization:
- Energy Research Lab., Hitachi, Ltd., 1168 Moriyama-cho, Hitachi-shi, Ibaraki-ken 316
- OSTI ID:
- 6611475
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 76:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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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
ALKALI METALS
ALLOYS
BREEDER REACTORS
BREEDING BLANKETS
BURNUP
COMPUTER CODES
ELEMENTS
EPITHERMAL REACTORS
EQUILIBRIUM
FAST REACTORS
FBR TYPE REACTORS
HETEROGENEOUS REACTOR CORES
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF FLOW
MATERIALS
METALS
MOLTEN METAL-WATER REACTIONS
PHASE TRANSFORMATIONS
POWER DISTRIBUTION
POWER RANGE 100-1000 MW
REACTIVITY COEFFICIENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
S CODES
SAFETY
SODIUM
STEELS
SUBCRITICALITY
VOID COEFFICIENT
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
ALLOYS
BREEDER REACTORS
BREEDING BLANKETS
BURNUP
COMPUTER CODES
ELEMENTS
EPITHERMAL REACTORS
EQUILIBRIUM
FAST REACTORS
FBR TYPE REACTORS
HETEROGENEOUS REACTOR CORES
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF FLOW
MATERIALS
METALS
MOLTEN METAL-WATER REACTIONS
PHASE TRANSFORMATIONS
POWER DISTRIBUTION
POWER RANGE 100-1000 MW
REACTIVITY COEFFICIENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
S CODES
SAFETY
SODIUM
STEELS
SUBCRITICALITY
VOID COEFFICIENT