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A PRELIMINARY STUDY OF THE TURRET EXPERIMENT--AN OPERATING TEST OF UNCLAD FUEL AT HIGH TEMPERATURE

Technical Report ·
DOI:https://doi.org/10.2172/4263064· OSTI ID:4263064

A preliminary study has been made of an impregnated graphite reactor to produce helium at 2400 F for process heat uses. The proposed facility will determine the characteristics and problems associated with operation of unclad graphite fuel. Volatile fission products will escape from the fuel elements into the helium stream, which will be continuously purified. Laboratory studies have shown that impregnated graphite will perform satisfactorily at the proposed conditions, and a simple fuel cycle has been developed. (auth)

Research Organization:
Los Alamos Scientific Lab., N. Mex.
DOE Contract Number:
W-7405-ENG-36
NSA Number:
NSA-13-013090
OSTI ID:
4263064
Report Number(s):
LA-2303
Country of Publication:
United States
Language:
English

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