Actions for Integral Target Fuel in a Water Cooled Graphite Lattice : Theory-Experiment Correlation

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Integral Target Fuel in a Water Cooled Graphite Lattice : Theory-Experiment Correlation

Author
Bennett, C. L.
Published
United States : [publisher not identified], 1968.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1968.
Physical Description
microfiche : negative ; 11 x 15 cm

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Summary
A complete multi-group Sn transport theory analysis and comparison with experiment has been made for an integral target fuel in a water-cooled graphite lattice, including the investigation of the leakage effect on k∞. Emphasis has been placed on the magnitude, relative importance, and recommended improvements of errors in the theory-experiment comparisons due to either the models or methods used in this study. The improved techniques give results that are in reasonably good agreement with most of the measured lattice parameters.
Report Numbers
BNWL-904
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(45-1)-1830
NSA number: NSA-23-017280
OSTI Identifier 4812665
Research organization: Battelle Pacific Northwest Labs., Richland, WA (United States).
Funding Information
Sponsored by US Atomic Energy Commission (AEC).
Sponsored by USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP).
View MARC record | catkey: 42540194