Results of an integration study of a diagnostics port plug in ITER

Sophie Salasca, Bruno Cantone, André Grosman, Basilio Esposito, Fabio Moro, Daniele Morocco, Rosaria Villari, Maurizio Angelone, Esther Rincon, Carlos Hidalgo, Daniel Nagy, Gabor Kocsis, Paulo Varela, Gabor Porempovics, Guillaume Perrollaz, Kunal Patel, Yuri Krivchenkov, Michael Walsh

Research output: Contribution to journalArticle

3 Citations (Scopus)


Diagnostics in ITER are mandatory to characterize the parameters of plasma and study its interactions with plasma-facing components. Diagnostics components in the vicinity of the plasma are supported by metallic structures called port plugs. At the tokamak mid-plane, these components are installed in port plugs through intermediate structures called drawers. Apart from hosting the diagnostics, the port plugs act as shielding against neutrons and gammas, in order to limit the nuclear loads in crucial components (such as diagnostics and superconducting coils) as well as the dose levels in the controlled zones of the tokamak. The radiation shielding function of the port plugs is ensured through an optimized mixture of heavy metallic materials and water, forming shielding blocks surrounding the diagnostics and called Diagnostic Shield Modules (DSMs). These DSMs constitute the rear part of the drawers (the front part being composed of the Diagnostic First Wall). This paper presents the main results of a study performed in Europe on the integration of a particular diagnostics port plug, the Equatorial Port Plug 1 (EPP1). The paper first provides the results of the EPP1 diagnostics integration analysis. In a second step it focuses on the design of the EPP1 DSMs and summarizes the major results of a thorough set of analyses aiming at studying the DSMs behaviour under different loads, suggesting recommendations to improve their current design.

Original languageEnglish
Pages (from-to)602-606
Number of pages5
JournalFusion Engineering and Design
Issue number6-8
Publication statusPublished - Mar 14 2013


  • Diagnostics
  • ITER
  • Integration
  • Port plugs
  • Shield modules

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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  • Cite this

    Salasca, S., Cantone, B., Grosman, A., Esposito, B., Moro, F., Morocco, D., Villari, R., Angelone, M., Rincon, E., Hidalgo, C., Nagy, D., Kocsis, G., Varela, P., Porempovics, G., Perrollaz, G., Patel, K., Krivchenkov, Y., & Walsh, M. (2013). Results of an integration study of a diagnostics port plug in ITER. Fusion Engineering and Design, 88(6-8), 602-606.