A HEURISTIC STUDY OF PLUTONIUM VALUE IN A FAST OXIDE BREEDER
Technical Report
·
OSTI ID:4745927
Results of an investigation concerning the indifference values of Pu are presented. It is noted that if the range of Pu compositions is limited, it may be possible to obtain approximately constant values ior some of the Pu isotopes. The investigation was conducted to obtain an indication of Pu value in a fast spectrum reactor, to trace the changing value of Pu in a fast reactor, and to assign indifference values to at least some Pu isotopes. Results indicate that Pu/sup 239/ has an appreciably higher value than U/sup 235/ in fast reactors and that thermally exposed Pu containing high fractions of Pu/sup 241/ is a more desirable fuel for fast reactors. (J.R.D.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-17-007545
- OSTI ID:
- 4745927
- Report Number(s):
- HW-72304
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BENZENE
BREEDING
BURNUP
CONCENTRATION
DECOMPOSITION
ECONOMICS
EFFICIENCY
EQUATIONS
FAST NEUTRONS
FERTILE MATERIALS
FISSIONABLE MATERIALS
FUELS
IODINE
IRRADIATION
ISOTOPES
MATERIALS TESTING
NEUTRON FLUX
NUMERICALS
PLUTONIUM
PLUTONIUM 239
PLUTONIUM 241
PLUTONIUM OXIDES
POWER PLANTS
PRODUCTION
RADIATION CHEMISTRY
RADIOLYSIS
REACTION KINETICS
REACTOR TECHNOLOGY
REPROCESSING
SPECTRA
THERMAL NEUTRONS
URANIUM 235
URANIUM OXIDES
BREEDING
BURNUP
CONCENTRATION
DECOMPOSITION
ECONOMICS
EFFICIENCY
EQUATIONS
FAST NEUTRONS
FERTILE MATERIALS
FISSIONABLE MATERIALS
FUELS
IODINE
IRRADIATION
ISOTOPES
MATERIALS TESTING
NEUTRON FLUX
NUMERICALS
PLUTONIUM
PLUTONIUM 239
PLUTONIUM 241
PLUTONIUM OXIDES
POWER PLANTS
PRODUCTION
RADIATION CHEMISTRY
RADIOLYSIS
REACTION KINETICS
REACTOR TECHNOLOGY
REPROCESSING
SPECTRA
THERMAL NEUTRONS
URANIUM 235
URANIUM OXIDES