HYDROGEN RELEASE OF REACTOR IRRADIATED RGT-GRAPHITE

Experiments on thermal stimulated hydrogen release of irradiated and c ontrol samples of RGT-graphite were carried out. Processing of two TDS peaks at temperatures near 770 K and 1100 K in a frame of second orde r desorption model gives the values of activation energies 2.8 eV/H-2 and 4.0 eV/H-2. Processing of a third peak at a temperature near 1300 K, which appeared only for graphite samples irradiated in hydrogen, al lows to obtain hydrogen diffusivity in graphite grains D = 1, 8 m(2)/s 10(-4)exp(-2.5 eV/kT). Ir was also shown that simultaneous influence of reactor irradiation and exposition to hydrogen could increase hydro gen retention in graphite.