Journal of Nuclear Fuel Cycle and Waste Technology

The cemented and paraffin wastes form which are incorporated the concentrated wastes, the cemented waste form which is incorporated the spent ion-exchange resins, and the miscellaneous waste(decontamination paper) were irradiated up to 10+8 rads at 5.43 x 10+5 rads/hr with Co-60(72,023.9 Ci) as an external irradiation source. As a result, the radiolysis gases such as H2, CH4, N2, C2H6, O2, CO and CO2 were measured in all the wastes. The major gas which was generated in all the wastes was hydrogen(H2). The volume of the generated gases showed a difference from 0.029 cm3.atm/1.1g to 0.788 cm3.atm/1.1g according to the type of wastes, and more was generated in the cemented waste form incorporated a spent ion-exchange resin than in the other wastes. More hydrogen(H2) gas was generated in the decontamination paper waste than in the other wastes, and the G(H2) value was 0.12.

Keywords

radioactive waste,waste form,characterization,irradiation,radiolysis,G-value