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

Conference · Sun Sep 01 04:00:00 EDT 1996

OSTI ID:459825

Konkashbaev, I; Grebenshikov, J ^[1]; Hassanein, A ^[2]

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

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.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE Office of Energy Research, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 459825
• Report Number(s): ANL/TD/CP--89708; CONF-960944--12; ON: DE97003237
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BERYLLIUM
BUILDUP
DIFFUSION
DIVERTORS
DUSTS
GRAPHITE
ITER TOKAMAK
MATHEMATICAL MODELS
PERMEABILITY
POROSITY
THERMONUCLEAR REACTOR MATERIALS
TRITIUM