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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

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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