Targeted separation of radionuclides from contaminated concrete waste generated from decommissioning of nuclear power plants

A chemical treatment process for removal of radionuclides associated with concrete from the decommissioning of nuclear power plants was adopted using a simple and effective precipitation method. Major radionuclides Co-60 and Eu-152 present in the concrete were confirmed to be selectively removed from the dissolved-concrete liquor as precipitates by pH-adjustment to pH 9. It was evaluated that HFO and HAO played important roles in the co-precipitation of Eu and Co, respectively. Nuclide decontamination factors were at least 6666 for Co-60 and 10,000 for Eu-152, respectively, and high enough to meet the requirement for release of decontaminated radioactive wastewaters in Korea.

Automated summary

A chemical treatment process using a precipitation method was adopted to remove radionuclides associated with concrete from decommissioning of nuclear power plants. Co-60 and Eu-152 were selectively removed from dissolved-concrete liquor as precipitates, with decontamination factors of at least 6666 for Co-60 and 10,000 for Eu-152, meeting the release requirement for decontaminated radioactive wastewaters in Korea.