Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Breeder-in-tube design for a helium-cooled Li sub 2 O tokamak blanket

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6860697

Of the solid breeder designs considered in the Blanket Comparison and Selection Study (BCSS), the lithium oxide breeder with helium coolant and ferritic steel (HT-9) structural material received the highest overall ranking for both tokamak and tandem mirror systems in terms of engineering, economics, safety, and R D requirements. The BCSS blanket surrounding the fusion plasma consists of a number of thin breeder plates externally cooled by flowing helium and internally purged of tritium by a separate helium stream. A detailed review of this design indicated that significant improvements would be realized in the areas of tritium breeding, blanket thickness, blanket energy multiplication, power-conversion efficiency, breeder temperature window, and geometrical integrity of the coolant and purge paths by using a neutron multiplier (beryllium), a higher temperature structural material (vanadium-based alloy), and a tube geometry. The neutronics, thermal-hydraulics, tritium recovery, and structural performance characteristics of this innovative solid breeder design are discussed in this paper. 2 refs., 1 tab.

OSTI ID:
6860697
Report Number(s):
CONF-860610--Summs.
Journal Information:
Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 52; ISSN TANSA; ISSN 0003-018X
Country of Publication:
United States
Language:
English