NON-RECYCLE BURNOUT ANALYSIS OF PLUTONIUM FUELS. Status Report-Part A
Technical Report
·
OSTI ID:4728304
Activities in an investigation concerning the relations of cross sections and neutron spectra as they affect the burnup characteristics of Pu are reported The isotope Pu/sup 240/ is shown to be useful in greater fractional burnups than can be achieved using materials such as U/sup 238/ or Th. Lowenrichment fuel cycles utilizing U/sup 238/ as the fertile material can achieve comparable lifetimes only with efficient neutron economies and with total fuel material requirements of the order of 100 times greater than those necessary with Pu/sup 240/. On the other hand, U/sup 235/ reactors without fertile material are limited to shorter reactivity lifetimes unless very large quantities of B or similar poisons are employed. (J.R.D.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-17-015392
- OSTI ID:
- 4728304
- Report Number(s):
- HW-57176
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis on fuel breeding capability of FBR core region based on minor actinide recycling doping
Delayed neutron method for measurement of fissile/fertile content of samples ranging from environmental to irradiated fuel
Delayed neutron method for measurement of fissile/fertile content of samples ranging from environmental to irradiated fuel
Journal Article
·
Tue Sep 30 00:00:00 EDT 2014
· AIP Conference Proceedings
·
OSTI ID:22307871
Delayed neutron method for measurement of fissile/fertile content of samples ranging from environmental to irradiated fuel
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6880687
Delayed neutron method for measurement of fissile/fertile content of samples ranging from environmental to irradiated fuel
Conference
·
Sun Jul 01 00:00:00 EDT 1984
· Nucl. Mater. Manage.; (United States)
·
OSTI ID:6318149