Published August 2012 | Version v1
Journal article

Nuclear engineering of diagnostic port plugs on ITER

  • 1. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)
  • 2. Princeton Plasma Physics Lab, Princeton, NJ (United States)
  • 3. Institute of Plasma Physics, Chinese Academy of Sciences (China)
  • 4. Efremov, St. Petersburg (Russian Federation)
  • 5. Institute for Plasma Research, Gandhinagar, Gujarat (India)
  • 6. National Fusion Research Institute, Daejeon (Korea, Republic of)
  • 7. Japan Atomic Energy Agency, Naka, Ibaraki (Japan)

Description

The nuclear engineering infrastructure of port-based diagnostics on ITER is presented, including the equatorial and upper port plug generic designs, the adopted modular concept, the loads and associated load response and the remote handling. A modular approach is adopted for the internal shielding modules as this helps to reduce the dominant electromagnetic loads, reduces interfaces and accelerates remote handling. Extensive use of gun-drilling is employed to produce water channels in the stainless steel plate and forgings used to construct the port plugs and modules. The French Nuclear Code RCC-MR (2007) is employed in the design and the manufacturing. An integrated remote handling scheme is described, including a description of maintenance operations in the Hot Cell Facility.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2012.01.043

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2012.01.043;
PII
S0920-3796(12)00054-3;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
87
Journal Issue
5-6
Journal Page Range
p. 667-674
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
10. international symposium on fusion nuclear technology
Acronym
ISFNT-10
Dates
11-16 Sep 2011
Place
Portland, OR (United States)

Optional Information

Copyright
Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.