Isotope exchange reaction between tritiated water and hydrogen on SiC

摘要: Abstract SiC has been considered as a primary candidate material for first wall component in future fusion reactor because it claimed that excellent high-temperature properties, good chemical stability and low activation. However, the behavior of tritium on not discussed yet. In this study, trapping capacity surface was experimentally obtained at temperature range 25–800 °C consideration to experimental system. The capacity, which independent water vapor pressure gas phase temperature, determined about 10 6 Bq/cm 2 . isotope exchange reaction rate between tritiated hydrogen quantified 25, 500 700 change condition by numerical curve fitting method applying serial model. observed be constant 3.48 × 10 −5 m/s. Additionally release from atmosphere predicted compared with graphite stainless steel.