An assessment of Clinch River Breeder Reactor core disruptive accident energetics
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6971834
A methodology is developed for the evaluation of the energetic consequences of postulated core disruptive accidents (CDAs), in liquid-metal fast breeder reactors. The methodology provides a framework for integrating the results of mechanistic analyses, including whole-core simulations (SAS, SIMMER), special effects analytical evaluations, and simulant material experiments into a probabilistic appreciation of accident evolution paths and respective likelihoods. Detailed quantitative results are presented for the Clinch River Breeder Reactor heterogeneous core design. As a result of this work, new perspectives were generated in the following areas: role of plenum fission gases, presence and role of small recriticalities in the early stages of core disruption, large annular and cylindrical pool recriticalities and associated disassembly yields, energy partition, and the role of structural response of vessel internal structures. The results indicate that a CDA-induced energetic vessel head failure is physically unreasonable.
- Research Organization:
- Purdue Univ., School of Nuclear Engineering, West Lafayette, IN 47907
- OSTI ID:
- 6971834
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 93:3; ISSN NSENA
- 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
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
HETEROGENEOUS REACTOR CORES
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
POWER REACTORS
PROBABILITY
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTORS
RISK ASSESSMENT
S CODES
SIMULATION
SODIUM COOLED REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
HETEROGENEOUS REACTOR CORES
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
POWER REACTORS
PROBABILITY
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTORS
RISK ASSESSMENT
S CODES
SIMULATION
SODIUM COOLED REACTORS