Published November 2000 | Version v1
Journal article

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

Description

The RF Home Team lithium-cooled test blanket module (TBM) is one of the TBMs 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 by 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 module slightly and test it at ITER extended performance phase with Li-cooled FW. Some results of neutronic, thermal-hydraulic and stress analysis are presented here for TBM with He-cooled FW

Additional details

Identifiers

PII
S0920379600001757;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
49-50
Journal Issue
3-4
Journal Page Range
p. 703-707
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
5. international symposium on fusion nuclear technology
Acronym
ISFNT-5
Dates
19-24 Sep 1999
Place
Rome (Italy)

Optional Information

Copyright
Copyright (c) 2000 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.