Neutronic, thermal-hydraulic and stress analysis of RF lithium cooled testblanket module for ITER

Citation
Iv. Vitkovsky et al., Neutronic, thermal-hydraulic and stress analysis of RF lithium cooled testblanket module for ITER, FUSION ENG, 49, 2000, pp. 703-707
Citations number
8
Categorie Soggetti
Nuclear Emgineering
Journal title
FUSION ENGINEERING AND DESIGN
ISSN journal
09203796 → ACNP
Volume
49
Year of publication
2000
Pages
703 - 707
Database
ISI
SICI code
0920-3796(200011)49:<703:NTASAO>2.0.ZU;2-W
Abstract
The RF Home Team lithium-cooled test blanket module (TBM) is one of the TBM s to be tested in international thermonuclear experimental reactor (ITER). To satisfy ITER safety demands, the TBM is enclosed in helium-cooled shell. So, it simulates DEMO reactor by having comparable radial dimensions and b y using all the materials of DEMO reactor, but does not simulate first wall (FW) conditions. To achieve the last task, it is planned to modify this mo dule slightly and test it at ITER extended performance phase with Li-cooled FW. Some results of neutronic, thermal-hydraulic and stress analysis are p resented here for TBM: with He-cooled FW. (C) 2000 Elsevier Science B.V. Al l rights reserved.