QUARTERLY STATUS REPORT ON TURRET REACTOR EXPERIMENT FOR PERIOD ENDING AUGUST 20, 1960
The Turret reactor program will study the practical effects on both the reactor and the coolant system of using porous, unclad fuel elements. In pursuit of this fundamental objective, efforts will be directed toward detailed study of the following points: (1) the behavior of unclad, porous graphite fuel elements at high temperatures under operating reactor conditions with respect to release of fission products and with respect to the degree of burn-up of uranium which may be practicably achieved in fuel elements of this general nature; (2) the operation of a hightemperatare coolant loop highly contaminated with fission products (specifically, the nature of the fission products deposited, mechanisms of deposition, and effects of various types of sunfaces and flow parameters, as well as maintenance techniques and applicable methods of fission product removal); (3) the basic requirements and effectiveness of gas-coolant purification systems for closed-cycle contaminated gas loops of this nature; and (4) the degree to which low-cost, chemically and mechanically simple fuel- reprocessing methods may be applied to fuel elements of this general character. Developments are summarized on the reactor, coolant system, gas-cleanup system, reactor facility, and materials. (W.D.M.)
- Research Organization:
- Los Alamos Scientific Lab., N. Mex.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-36
- NSA Number:
- NSA-15-003707
- OSTI ID:
- 4110097
- Report Number(s):
- LAMS-2469
- Country of Publication:
- United States
- Language:
- English
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