Post-Initiating Phase Neutronics Analysis of an Unprotected LOF Event in CRBRP
Conference
·
OSTI ID:6355160
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- General Electric Co., San Jose, CA (United States)
The reactor system is expected to achieve permanent subcriticality in a loss-of-flow (LOF) event by virtue of fuel removal from the core even under the hypothetical assumption that both shutdown systems fail to function. Based on the analysis performed by S.K. Rhow, et al., adequate fuel removal would occur in the CRBRP heterogeneous core during a meltout period after the initiating phase of the unprotected LOF event. This paper discusses reactivity levels relative to fuel removal in the accident progression beyond the initiating phase for the CRBRP core at the beginning of cycle 1 (BOC-1).
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6355160
- Report Number(s):
- CONF-830609--11; ON: DE83010763
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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
Beginning of Cycle 1 (BOC-1)
CLINCH RIVER BREEDER REACTOR
CRITICALITY
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
Loss-of-Flow (LOF)
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
REACTIVITY WORTHS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
Reactivity Levels
SAFETY
SODIUM COOLED REACTORS
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
Beginning of Cycle 1 (BOC-1)
CLINCH RIVER BREEDER REACTOR
CRITICALITY
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
Loss-of-Flow (LOF)
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
REACTIVITY WORTHS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
Reactivity Levels
SAFETY
SODIUM COOLED REACTORS