Title :
Evaluation of U.S. Demo helium-cooled blanket options
Author :
Wong, C.P.C. ; McQuillan, B.W. ; Schleicher, R.W. ; Cheng, E.T.
Author_Institution :
Gen. Atomics, San Diego, CA, USA
fDate :
30 Sep-5 Oct 1995
Abstract :
A He-V-Li blanket design was developed as a candidate for the U.S. fusion demonstration power plant. This paper presents an 18 MPa helium-cooled, lithium breeder, V-alloy design that can be coupled to the Brayton cycle with a gross efficiency of 46%. The critical issue of designing to high gas pressure and the compatibility between helium impurities and V-alloy are addressed
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactors; helium; holmium alloys; lithium alloys; vanadium alloys; 18 MPa; Brayton cycle; Demo helium-cooled blanket options; He; He-V-Li blanket design; V-Li-Ho; helium-cooled lithium breeder V-alloy design; high gas pressure; Chemicals; Coolants; Extrapolation; Helium; Impurities; Lithium; Power generation; Solids; Temperature; Thermal resistance;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534429
