Tritium behavior in eroded dust and debris of plasma-facing materials.

Conference · Tue Mar 10 04:00:00 EST 1998

OSTI ID:10681

Hassanein, A

Tritium behavior in plasma-facing components (PFCs) of future tokamak reactors such as ITER is an essential factor in evaluating and choosing the ideal plasma-facing materials (PFMs). One important parameter that influences tritium buildup and release in candidate materials is the effect of material porosity on tritium diffusion and retention. Diffusion in porous materials, for example, consists of three different processes: along grain boundaries, along microcrystalline boundaries, and in pure crystallite structures. Such diffusion processes have strong nonlinear behavior due to temperature, volubility, and existing trap sites. Therefore, a realistic model for tritium diffusion in porous and neutron-irradiated materials must account for both nonlinear and multidimensional effects. A tritium transport computer model, TRAPS, has been developed to evaluate and predict the kinetics of tritium transport in porous media. This two-dimensional model incorporates tritium diffusion and trapping processes that also account for hydrogen-isotope volubility limits in PFMs. This model is being coupled with the computer model, TRICS, which has been developed to study the effect of surface erosion on tritium behavior in PFCs.

• Research Organization: Argonne National Lab., IL (US)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10681
• Report Number(s): ANL/TD/CP-95858
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CORROSION PRODUCTS
DIFFUSION
DUSTS
EROSION
FIRST WALL
KINETICS
POROUS MATERIALS
T CODES
THERMONUCLEAR REACTOR MATERIALS
TOKAMAK TYPE REACTORS
TRITIUM