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Title: Evaluation of US demo helium-cooled blanket options

Conference ·
OSTI ID:464164

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.

Research Organization:
General Atomic Co., San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Energy Research, Washington, DC (United States)
DOE Contract Number:
AC03-89ER52153
OSTI ID:
464164
Report Number(s):
GA-A22214; CONF-950905-49; ON: DE97004544; TRN: 97:010045
Resource Relation:
Conference: 16. IEEE/NPSS symposium on fusion engineering, Champaign, IL (United States), 1-5 Oct 1995; Other Information: PBD: Oct 1995
Country of Publication:
United States
Language:
English