Accommodation of unprotected accidents by inherent safety design features in metallic and oxide-fueled LMFBRs
Conference
·
OSTI ID:5799893
This paper presents the results of a study of the effectivness of intrinsic design features to mitigate the consequences of unprotected accidents in metallic and oxide-fueled LMFBRs. The accidents analyzed belong to the class generally considered to lead to core disruption; unprotected loss-of-flow (LOF) and transient over-power (TOP). Results of the study demonstrate the potential for design features to meliorate accident consequences, and in some cases to render them benign. Emphasis is placed on the relative performance of metallic and oxide-fueled core designs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5799893
- Report Number(s):
- CONF-850410-43; ON: DE85012114
- 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
ALLOY NUCLEAR FUELS
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATERIALS
MIXED OXIDE FUELS
NUCLEAR FUELS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
SAFETY
SOLID FUELS
TRANSIENT OVERPOWER ACCIDENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOY NUCLEAR FUELS
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATERIALS
MIXED OXIDE FUELS
NUCLEAR FUELS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
SAFETY
SOLID FUELS
TRANSIENT OVERPOWER ACCIDENTS