Evaluation of U.S. Demo helium-cooled blanket options
Conference
·
OSTI ID:464979
- General Atomics, San Diego, CA (United States)
- TSI Research Inc., San Diego, CA (United States)
A He-V-Li blanket design was developed as a candidate for the US 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.
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC03-89ER52153
- OSTI ID:
- 464979
- Report Number(s):
- CONF-950905-; ISBN 0-7803-2969-4; TRN: 97:007487
- Resource Relation:
- Conference: 16. IEEE/NPSS symposium on fusion engineering, Champaign, IL (United States), 1-5 Oct 1995; Other Information: PBD: 1995; Related Information: Is Part Of 1995 IEEE 16. symposium on fusion engineering. Volume 2; Miley, G.H.; Elliott, C. [eds.] [Univ. of Illinois, Urbana, IL (United States). Fusion Studies Lab.]; PB: 851 p.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of US demo helium-cooled blanket options
A helium-cooled blanket design of the low aspect ratio reactor
Helium-Cooled Refractory Alloys First Wall and Blanket Evaluation
Conference
·
Sun Oct 01 00:00:00 EDT 1995
·
OSTI ID:464979
A helium-cooled blanket design of the low aspect ratio reactor
Conference
·
Sun Mar 01 00:00:00 EST 1998
·
OSTI ID:464979
+2 more
Helium-Cooled Refractory Alloys First Wall and Blanket Evaluation
Conference
·
Sun Aug 01 00:00:00 EDT 1999
·
OSTI ID:464979
+14 more