A study of tritium decontamination of deposits by UV irradiation
作者： Y. Oya , W. Shu , S. O'hira , T. Hayashi , H. Nakamura
DOI: 10.1016/S0022-3115(00)00440-2
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摘要: Abstract To develop a new method for decontamination of tritium retained in the carbon fiber composites (CFC) tiles and other components D–T fusion reactors, preliminary experiment using ultra violet (UV) light source was performed. Samples simulating co-deposited layer were prepared by glow discharge C 2 H tungsten or CFC substrate. The UV from xenon excimer lump (172 nm) irradiated to samples 423 K. Small amounts species released only heating procedure By irradiation, large quantities hydrogen, hydrocarbons samples. Fourier Transform Infrared (FT-IR) analysis showed formed on sample acetylene C–H bonds decomposed irradiation with light. It is concluded that combination causes release surface materials.
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