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Feasibility study on vitrification of low- and intermediate-level radioactive waste from pressurized water reactors

Journal Article · · Waste Management
;  [1]
  1. Korea Electric Power Research Inst., Taejon (Korea, Republic of). Nuclear Power Research Lab.
In order to obtain annual generation volume and composition data for low- and intermediate-level radioactive waste (LILW), characteristics and generation trends for each waste which was produced at nuclear power plants (NPPs) in Korea were investigated. Of the three different types of melters, the platinum crucible was found to be most suitable for the performance of vitrification experiments and hence, was used to help better understand the optimal waste contents in borosilicate glass waste forms with respect to waste types. After the performance of vitrification experiments, compressive strength tests showed that the final waste glass product, containing up to 40 vol% of ashy pyrolyzed/oxidized at 400--800 C, showed good mechanical stability and homogeneity in the glass matrix. Economical assessment was performed with some considerations given for equipment having already been adopted for LILW treatment in Korea for four treatment strategies with melters selected from a technical assessment. For each strategy, the capital and the operation cost were estimated, and the disposal volume was calculated with reasonably estimated volume reduction factors with regard to waste type and treatment concept.
OSTI ID:
308157
Journal Information:
Waste Management, Journal Name: Waste Management Journal Issue: 3 Vol. 18; ISSN WAMAE2; ISSN 0956-053X
Country of Publication:
United States
Language:
English