NON-ASYMPTOTIC LATTICE PARAMETERS IN A DRY UO$sub 2$ BLANKET-MEASUREMENTS AND CALCULATIONS
Technical Report
·
OSTI ID:4114965
The ratios of epicadmium to subcadmium capture in U/sup 238/, of U/sup 238/ capture to U/sup 235/ fission, of U/sup 238/ fission t o U/sup 235/ fission, and of epicadmium to subcadmium fission in U/sup 235/ were measured in a UO/sub 2/ blanket in a UO/sub 2/- Zr--H/sub 2/O seed blanket-seed slab core with a water to nonwater volume ratio of 0.142. The results were compared with calculations by a design model using a one-dimensional few group diffusion program and with calculations by a one-dimensional, multigroup P-3 transport code. (D.C.W
- Research Organization:
- Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-18-009580
- OSTI ID:
- 4114965
- Report Number(s):
- WAPD-T-1632; CONF-187-47
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BLANKETS
CADMIUM
CADMIUM RATIO
CAPTURE
COMPUTERS
CONFERENCE
CONFIGURATION
DENSITY
EPITHERMAL NEUTRONS
EQUATIONS
ERRORS
FAST FISSION FACTOR
FERTILE MATERIALS
FISSION
FISSIONABLE MATERIALS
FUELS
GROUP THEORY
MEASURED VALUES
MODERATORS
NEUTRON FLUX
NEUTRONS
NEW YORK
NUMERICALS
PLATES
PROGRAMMING
REACTOR CORE
REACTOR TECHNOLOGY
SPECTRA
TEMPERATURE
THERMAL FISSION FACTOR
THERMAL NEUTRONS
THERMAL UTILIZATION
URANIUM 235
URANIUM 238
URANIUM DIOXIDE
USA
VOLUME
WATER MODERATOR
ZIRCONIUM
CADMIUM
CADMIUM RATIO
CAPTURE
COMPUTERS
CONFERENCE
CONFIGURATION
DENSITY
EPITHERMAL NEUTRONS
EQUATIONS
ERRORS
FAST FISSION FACTOR
FERTILE MATERIALS
FISSION
FISSIONABLE MATERIALS
FUELS
GROUP THEORY
MEASURED VALUES
MODERATORS
NEUTRON FLUX
NEUTRONS
NEW YORK
NUMERICALS
PLATES
PROGRAMMING
REACTOR CORE
REACTOR TECHNOLOGY
SPECTRA
TEMPERATURE
THERMAL FISSION FACTOR
THERMAL NEUTRONS
THERMAL UTILIZATION
URANIUM 235
URANIUM 238
URANIUM DIOXIDE
USA
VOLUME
WATER MODERATOR
ZIRCONIUM