Nuclear engineering of diagnostic port plugs on ITER

C. S. Pitcher, R. Barnsley, R. Feder, Q. Hu, G. D. Loesser, B. Lyublin, S. Padasalagi, S. Pak, R. Reichle, K. Sato, V. S. Udintsev, C. Walker, M. Walsh, Y. Zhai

Research output: Contribution to journalArticlepeer-review

14 Scopus citations

Abstract

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.

Original languageEnglish (US)
Pages (from-to)667-674
Number of pages8
JournalFusion Engineering and Design
Volume87
Issue number5-6
DOIs
StatePublished - Aug 2012

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • General Materials Science
  • Mechanical Engineering

Keywords

  • Diagnostics
  • ITER
  • Nuclear shielding
  • Port plugs
  • Remote handling
  • Shut-down dose rate

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