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U.S. Department of Energy
Office of Scientific and Technical Information

Flibe/Be/He/FS concept (R = 1)

Technical Report ·
DOI:https://doi.org/10.2172/5841581· OSTI ID:5841581
The blanket concept is described. Beryllium, in the form of pebbles nominally 1 cm diameter in a 20 cm thick bed, is employed to multiply neutrons. The multiplier zone is followed by a zone of silicon carbide (SiC) which slows neutrons. Neutrons are captured in the Lithium-6 carried in the molten fluoride salt (LiF + BeF- melting point, 363/sup 0/C) to breed tritium and release extra energy in exothermic nuclear rections. The salt flows slowly through tubes in the blanket and out to a simple flash separator where the tritium is removed. Helium flows radially through the Be pebble bed and SiC region carrying the heat out to the thermal conversion plant. The tubes are coated either on the inside or outside with a 10 ..mu..m tungsten barrier by chemical vapor deposition to cut down tritium permeation to the helium coolant circuit. With the tungsten barrier on the inside the tritium inventory in the tube walls is small and tungsten will contribute to corrosion inhibition. A 1-mm aluminum jacket on the steam generator tubes keeps the tritium permeation to the steam down to 30 curies per day. The design can be converted into a fission-suppressed fissile breeder by thickening the beryllium zone by a factor of 2 or so and adding ThF/sub 4/ to the salt in which case 6 tonnes of uranium-233 would be produced per year.
Research Organization:
Lawrence Livermore National Lab., CA (USA)
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
5841581
Report Number(s):
UCID-20233; ON: DE86011009
Country of Publication:
United States
Language:
English