PLUTONIUM RECYCLE VALUES IN THERMAL AND FAST REACTORS AND EXPECTED PATTERNS OF USE OF PLUTONIUM

Technical Report · Thu Oct 31 04:00:00 EST 1963

OSTI ID:4726264

Zebroski, E L; Wolfe, B; Greebler, P; Sueoka, J

Discussions are presented concerning the use of Pu in thermal reactors to reduce the amount of U/sup 235/ makeup required to attain any specified fuel lifetime or to increase the reactivity lifetime available for a specified control strength. Discussions are also included concerning method of calculation of Pu value for thermal recycle, fueling patterns for use with thermal reactor recycle, specialized reactor cycles, results of recycle calculations, reactivity lifetime and control range effects of Pu recycle, fabrication costs for Pu-bearing fuels, and Pu value estimates. Other information is included concerning Pu use in fast reactors and supply and value relations including estimated rate of Pu accumulation from power reactor operation, expected patterns of Pu use, and aspects of Pu buyback. (J.R.D.)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
• NSA Number: NSA-17-019576
• OSTI ID: 4726264
• Report Number(s): HW-75007(Paper 23)
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

CONFERENCE
CONFIGURATION
DISTRIBUTION
ECONOMICS
EQUATIONS
FABRICATION
FAST NEUTRONS
FUELS
LIFETIME
PLUTONIUM
POWER PLANTS
PRODUCTION
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RECYCLING
REPROCESSING
THERMAL NEUTRONS
URANIUM 235