Lithium cooled blanket of RF DEMO reactor

Authors
Citation
Ir. Kirillov, Lithium cooled blanket of RF DEMO reactor, FUSION ENG, 49, 2000, pp. 457-465
Citations number
6
Categorie Soggetti
Nuclear Emgineering
Journal title
FUSION ENGINEERING AND DESIGN
ISSN journal
09203796 → ACNP
Volume
49
Year of publication
2000
Pages
457 - 465
Database
ISI
SICI code
0920-3796(200011)49:<457:LCBORD>2.0.ZU;2-M
Abstract
Two blanket options are considered for RF DEMO-S reactor (fusion power simi lar to2.4 GW) with steady-state operation: lithium (Li) self-cooled and cer amic breeder helium-cooled ones. Lithium-cooled blanket, which uses Li as c oolant and tritium breeder and V-Cr-Ti (vanadium-chrome-titanium) alloy as structural material, is described here. Poloidal type of Li flow is chosen under the assumption that electroinsulating coating is developed on the int erface of Li/structure material. Results of preliminary neutronic, thermal- hydraulic and stress analysis are presented. The steam turbine cycle conver ting the thermal to electric energy is recommended with intermediate sodium loop on the basis of the FBR experience. (C) 2000 Elsevier Science B.V. Al l rights reserved.