Heat-treatment and storage technology for spent ion-exchange resins for new-generation nuclear power plants

• Published in: Atomic energy (New York, N.Y.) Vol. 111; no. 4; pp. 276 - 281
• Main Authors: Babkin, D. N., Prokhorov, N. A., Sorokin, V. T., Demin, A. V., Iroshnikov, V. V.
• Format: Journal Article
• Language: English
• Published: Boston Springer US 01.02.2012; Springer; Springer Nature B.V
• Subjects: Barrels (containers); Casks; Cement; Computer storage device industry; Drying; Experiments; Hadrons; Heat; Heat treatment; Heavy Ions; Ion exchange; Moisture content; Nuclear Chemistry; Nuclear Energy; Nuclear Physics; Nuclear power generation; Nuclear power plants; Physics; Physics and Astronomy; Polymers; Pressure gauges; Radioactive wastes; Resins; Solidification; Solids; Studies; Technology application; Cement Compound; Nuclear Power Plant; Residual Moisture Content; Spend Resin; Subsequent Disposal
• ISSN: 1063-4258; 1573-8205
• DOI: 10.1007/s10512-012-9488-7

A technology for thermovacuum drying of spent radioactively contaminated ion-exchange resins was developed. It was shown experimentally that thermovacuum drying yields a product suitable for long-term storage and subsequent disposal. Recommendations were made for using NZK and KMZ concrete and metal casks for holding dry, spent, low- and medium-activity ion-exchange resins without additional solidification. Because the volume of the product obtained is greatly reduced, thermovacuum drying will decrease by at least 15-fold (from 100 to 7) the number of casks required for long-term storage and subsequent disposal of spent ion-exchange resins produced in one year of operation of a single VVER-1200 power-generating unit.