Abstract
Tritium codeposition in sputtered and redeposited surface layers may be a critical issue for next generation tokamak fusion reactors. We review recent codeposition/erosion code/model improvements, and calculations. Updated models for carbon include chemical sputtering yields, sputtered hydrocarbon species, and atomic and molecular processes. Calculations show that a carbon coated divertor with a semi or fullydetached plasma may behave poorly, with predicted codeposition rates of order 10 gT/1000s pulse, and peak net erosion rates of order 10 nm/s. Other materials such as beryllium, tungsten, lithium, or carbon with a non-detached plasma regime, look better. Outstanding research issues include reflection/sticking properties of redeposited carbon/hydrocarbon particles, possible flux dependence of chemical sputtering, and dopant effects.
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© 2002 Springer Science+Business Media Dordrecht
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Brooks, J.N. (2002). Recent Progress In Tritium Codeposition Modeling. In: Hassanein, A. (eds) Hydrogen and Helium Recycling at Plasma Facing Materials. NATO Science Series, vol 54. Springer, Dordrecht. https://doi.org/10.1007/978-94-010-0444-2_3
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DOI: https://doi.org/10.1007/978-94-010-0444-2_3
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