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Title: Evaluation of U.S. Demo helium-cooled blanket options

Abstract

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.

Authors:
; ;  [1];  [2]
  1. General Atomics, San Diego, CA (United States)
  2. TSI Research Inc., San Diego, CA (United States)
Publication Date:
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
464979
Report Number(s):
CONF-950905-
ISBN 0-7803-2969-4; TRN: 97:007487
DOE Contract Number:  
AC03-89ER52153
Resource Type:
Conference
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
Subject:
70 PLASMA PHYSICS AND FUSION; BREEDING BLANKETS; TOKAMAK TYPE REACTORS; DEMONSTRATION PLANTS; THERMONUCLEAR POWER PLANTS; HELIUM; VANADIUM ALLOYS; LITHIUM; THERMONUCLEAR REACTOR MATERIALS; DESIGN

Citation Formats

Wong, C P.C., McQuillan, B W, Schleicher, R W, and Cheng, E T. Evaluation of U.S. Demo helium-cooled blanket options. United States: N. p., 1995. Web.
Wong, C P.C., McQuillan, B W, Schleicher, R W, & Cheng, E T. Evaluation of U.S. Demo helium-cooled blanket options. United States.
Wong, C P.C., McQuillan, B W, Schleicher, R W, and Cheng, E T. Sun . "Evaluation of U.S. Demo helium-cooled blanket options". United States.
@article{osti_464979,
title = {Evaluation of U.S. Demo helium-cooled blanket options},
author = {Wong, C P.C. and McQuillan, B W and Schleicher, R W and Cheng, E T},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {12}
}

Conference:
Other availability
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