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

نویسندگان

  • A. Hassanein
  • B. Wiechers
  • I. Konkashbaev
چکیده

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 in ̄uences tritium buildup and release in candidate materials is the e€ect of material porosity on tritium di€usion and retention. Di€usion in porous materials, for example, consists of three di€erent processes: along grain boundaries, along microcrystallite boundaries, and in pure crystallite structures. Such di€usion processes have strong nonlinear behavior due to temperature, solubility, and existing trap sites. Therefore, a realistic model for tritium di€usion in porous and neutron-irradiated materials must account for both nonlinear and multidimensional e€ects. A tritium transport computer model Tritium Accumulation in Porous Structure (TRAPS) has been developed to evaluate and predict the kinetics of tritium transport in porous media. This two-dimensional model incorporates tritium di€usion and trapping processes that also account for hydrogen-isotope solubility limits in PFMs. This model is being coupled with the computer model Tritium In Compound System (TRICS) which has been developed to study the e€ects of surface erosion to tritium behavior in PFCs. Ó 1998 Elsevier Science B.V. All rights reserved.

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تاریخ انتشار 1998