Published September 1996 | Version v1
Report Open

Tritium containment in the dust and debris of plasma-facing materials produced during operations

  • 1. Troitsk Inst. for Innovation and Fusion Research (Russian Federation)
  • 2. Argonne National Lab., IL (United States)

Description

Tritium behavior in plasma-facing components of future tokamak reactors such as ITER is an essential factor in evaluating and choosing a successful candidate for a plasma-facing material (PFM). One important parameter that influence tritium build-up and release in the Generated dust of PFMs is the effect of material porosity on tritium behavior. Diffusion in porous materials, for example, consists of three different diffusion processes: along grain boundaries, along micro-crystallites, and diffusion in pure structure crystallites. A model is developed to evaluate and assess the sensitivity of tritium accumulation and permeation of candidate materials due to porosity. Specific laboratory experiments relevant to reactor conditions, in currently existing and available facilities, are required to help in selecting the best candidate material

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE97003237; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
5 p.
Report number
ANL--TD/CP-89708

Conference

Title
19. symposium on fusion technology (SOFT-19).
Dates
16-20 Sep 1996.
Place
Lisbon (Portugal).

Optional Information

Contract/Grant/Project number
Contract W-31109-ENG-38
Funding organization
USDOE Office of Energy Research, Washington, DC (United States).
Secondary number(s)
CONF-960944--12.