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

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...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2012-02, Vol.111 (4), p.276-281
Main Authors: Babkin, D. N., Prokhorov, N. A., Sorokin, V. T., Demin, A. V., Iroshnikov, V. V.
Format: Article
Language:English
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
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Summary: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.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-012-9488-7