Study on dissolution of glasses for measurement of activity of α, β, and γ emitting nuclides in vitrification radioactive waste sample

Vitrification of radioactive waste sample in Korea was tested in Hanwool NPP. As such, drums of low and intermediate level radioactive waste which include vitrification, are managed temporarily in the NPP sites. To transport radioactive waste from the temporary disposal site to the repository, > 95% of the total activity in a drum should be accounted for based on the radioactive waste acceptance criteria specified by nuclear safety and security commission (NSSC) notice No. 2015-4. We developed a sample dissolution procedure for the measurement of radioactivity in vitrification radioactive waste samples. The ICP-AES analytical results showed that principal constituent elements except SiO2 were quantitatively recovered in dissolving sample with a mixture of aqua regia and HF on a hot plate. This procedure will be applied to vitrification radio-active waste samples for the measurement of α, β, and γ-emitting nuclides