A model for tritium transport in fusion reactor components: The FUS-TPC code

F. Franza, A. Ciampichetti, I. Ricapito, M. Zucchetti

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18 Citations (Scopus)

Abstract

Hydrogen dissolves in and permeates through most materials, thus it is important to understand the permeation, diffusion and dissolution phenomena of atomic hydrogen in materials in which hydrogen and its isotopes are present. In this work the problem of tritium transport from lead-lithium breeder through different heat transfer surfaces to the environment has been studied and analyzed by means of a computational code. The code (FUS-TPC) is a new fusion-devoted version of the fast-fission one called Sodium-Cooled Fast Reactor Tritium Permeation Code (SFR-TPC). The main features of the model inside the code are described. A simulation, using the code, was performed by adopting the configuration of the European configuration of the Helium Cooled Lead Lithium (HCLL) blanket for DEMO. © 2012 Elsevier B.V. All rights reserved.
Original languageEnglish
Pages (from-to)299 - 302
Number of pages4
JournalFusion Engineering and Design
Volume87
Issue number4
DOIs
Publication statusPublished - May 2012
Externally publishedYes

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All Science Journal Classification (ASJC) codes

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

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