NUCLEAR ANALYSIS OF A U-233 THERMAL BREEDER
Technical Report
·
OSTI ID:4326120
Work performed under contract with The Detroit Edison Co. and the Dow Chemical Co. A critical mass of 10 to 20 kg and a breeding ratio of about 1-0 have been calculated for a U/sup 233/-bismuth fueled and graphite moderated reactor- Breeding losses caused by a high U/sup 233/ alpha in the intermediate energy region are shown to be significant. (W.D.M.)
- Research Organization:
- Nuclear Development Associates, Inc., White Plains, N.Y.
- NSA Number:
- NSA-12-013473
- OSTI ID:
- 4326120
- Report Number(s):
- NDA-14-26
- Country of Publication:
- United States
- Language:
- English
Similar Records
A FEASIBILITY STUDY OF FAST U$sup 233$-Th BREEDER REACTORS
THE EFFECT OF HYDROGEN IN A FAST POWER BREEDER REACTOR
A CONCEPTUAL DESIGN OF A THORIUM-URANIUM (233) POWER BREEDER REACTOR
Technical Report
·
Mon Oct 10 00:00:00 EDT 1960
·
OSTI ID:4827931
THE EFFECT OF HYDROGEN IN A FAST POWER BREEDER REACTOR
Technical Report
·
Mon Jun 21 00:00:00 EDT 1954
·
OSTI ID:4287566
A CONCEPTUAL DESIGN OF A THORIUM-URANIUM (233) POWER BREEDER REACTOR
Technical Report
·
Sun Jan 31 23:00:00 EST 1954
·
OSTI ID:4331827