Testoni P.,Fusion for Energy F4E |
Oliva A.B.,Fusion for Energy F4E |
Portone A.,Fusion for Energy F4E |
Carin Y.,Fusion for Energy F4E |
And 8 more authors.
Fusion Engineering and Design | Year: 2011
Fusion for energy (F4E), the European Domestic Agency for ITER, is involved in a relevant number of activities in the area of electromagnetic analysis in support of ITER general design, and of specific requirement of the EU in-kind procurement. In this context, its main activity is linked with the electromagnetic analysis of several ITER components (blanket shield modules and first wall panels, blanket cooling manifolds, TBM port plug, etc.) subjected to electro-dynamical loads. Another important activity is related to the ITER superconducting magnets, namely the quench detection of the ITER TF coils and the Joule losses in the magnets cold structures. Last, but not least, a further activity is on going on the error field analysis due to tolerances in both construction and assembly of ITER magnets. © 2011 Elsevier B.V. All rights reserved. Source
Kim B.-Y.,ITER Organization |
Marconi M.,LTCalcoli |
Neviere J.-C.,Comex Nucleaire |
Merola M.,ITER Organization |
And 3 more authors.
Fusion Engineering and Design | Year: 2015
In three of the ITER equatorial ports, tritium breeding blanket concepts will be validated and tested using mock-up breeding blankets called test blanket modules (TBM). In these ports, two TBM-Sets are mechanically attached in a TBM Frame to form a TBM port plug (TBM PP). The ITER Organization is responsible for the design and manufacture of both this TBM Frame and the Dummy TBMs which will fill them. As a part of this development, in 2013, a conceptual design review (CDR) of TBM PP with two dummy TBMs revealed the need for improvement of design performance, interfaces and maintainability. This paper presents the main design improvements after the CDR as well as associated feasibility analysis of the improved design focusing on the attachment. Finally the work plan for the Preliminary Design phase is summarized. © 2015 Elsevier B.V. Source
Kim B.Y.,ITER Organization |
Sabourin F.,ITER Organization |
Merola M.,ITER Organization |
Giancarli L.,ITER Organization |
And 5 more authors.
Fusion Engineering and Design | Year: 2014
The test blanket module port plug (TBM PP) consists of a TBM frame and two TBM-sets. However, at any time of the ITER operation, a TBM set can be replaced by a dummy TBM. The frame provides a standardized interface with the vacuum vessel (VV)/port structure and provides thermal isolation from the shield blanket. As one of the plasma-facing components, it shall withstand heat loads while at the same time provide adequate neutron shielding for the VV and magnet coils. The frame design shall provide a stable engineering solution to hold TBM-sets and also provide a mean for rapid remote handling replacement and refurbishment. This paper presents main design features of the conceptual design of TBM PP with two dummy TBMs. Also analysis results are summarized to evaluate shielding, hydraulic, and thermal and structural performances of the TBM PP design. © 2014 ITER Organization. Source