Validation of neutronic codes for distorted core configurations with the SNEAK-12 critical assemblies
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6218221
The reactivity effect sof material rearrangements, simulating conditions in a postulated liquid-metal fast breeder reactor accident, were measured in three different critical assemblies: SNEAK-12A, a single-zone core, fueled with enriched uranium metal plates; SNEAK-12B, which had a central test zone fueled with PuO/sub 2/O/sub 2/ rod bundles surrounded by a buffer and a driver zone; and SNEAK-12C, which had nearly the same integral compositions as SNEAK-12B but was loaded totally with plates. The reactivity effects were calculated using current Kernforschungszentrum Karlsruhe methods and data and, in part, also using the corresponding modules of the SIMMER-II accident analysis system. Also, for some configurations, a comparison of measured and calculated fission rate distributions was performed. The evaluation yielded similar results for the three assemblies. For most cases investigated, satisfactory agreement between theory and experiment was reached when two-dimensional transport eigenvalue calculations or exact transport perturbation methods were used. As long as larger deviations occurred, transport results generally were on the conservative side. First-order transport perturbation theory only worked well in a limited number of cases. Diffusion calculations often led to large discrepancies, particularly when the experiments involved fuel dilution.
- Research Organization:
- Kernforschungszentrum Karlsruhe, Institut fur Neutronenphysik und Reaktortechnik, Karlsruhe (DE)
- OSTI ID:
- 6218221
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 100:3; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
RADIATION TRANSPORT
REACTOR ACCIDENTS
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REACTOR CORES
REACTOR MATERIALS
REACTOR SAFETY EXPERIMENTS
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CALCULATION METHODS
CHALCOGENIDES
CONFIGURATION
DIFFUSION
DISTURBANCES
EIGENVALUES
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
RADIATION TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR SAFETY EXPERIMENTS
REACTORS
ROD BUNDLES
SIMULATION
TRANSURANIUM COMPOUNDS