Probabilities of inherent shutdown of unprotected events in innovative liquid metal reactors
Conference
·
OSTI ID:5017816
The uncertainty in predicting the effectiveness of inherent shutdown in innovative liquid metal cooled reactors with metallic fuel results from three broad contributing areas of uncertainty: (1) the inability to exactly predict the frequency of ATWS events with potential to challenge the safety systems and require inherent shutdown; (2) the approximation of representing all such events by a selected set of ''generic scenarios''; and (3) the inability to exactly calculate the core response to the selected generic scenarios. This paper discusses the work being done to address each of these contributing areas, identifies the design and research approaches being used at Argonne National Laboratory to reducing the key contributions to uncertainties in inherent shutdown, and presents results. The conditional probabilities (given ATWS initiation) of achieving temperatures capable of defeating inherent shutdown are shown to range from /approximately/0.1% to negligible for current designs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5017816
- Report Number(s):
- CONF-880506-3; ON: DE88009946
- Country of Publication:
- United States
- Language:
- English
Similar Records
Uncertainties in inherent shutdown of generic unprotected loss-of-flow and transient overpower events in innovative designs
Probabilities of inherent shutdown of unprotected events in innovative liquid metal reactors
Impacts of reactivity feedback uncertainties on inherent shutdown in innovative designs
Technical Report
·
Thu Oct 01 00:00:00 EDT 1987
·
OSTI ID:713938
Probabilities of inherent shutdown of unprotected events in innovative liquid metal reactors
Conference
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Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6174532
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Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:7054002
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
BREEDER REACTORS
DATA BASE MANAGEMENT
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MANAGEMENT
MATHEMATICAL MODELS
PROBABILITY
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
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SEISMIC EFFECTS
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210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DATA BASE MANAGEMENT
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MANAGEMENT
MATHEMATICAL MODELS
PROBABILITY
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SEISMIC EFFECTS
SHUTDOWNS
TRANSIENTS