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

被引:0
|
作者
D. N. Babkin
N. A. Prokhorov
V. T. Sorokin
A. V. Demin
V. V. Iroshnikov
机构
来源
Atomic Energy | 2012年 / 111卷
关键词
Nuclear Power Plant; Residual Moisture Content; Cement Compound; Spend Resin; Subsequent Disposal;
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摘要
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.
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页码:276 / 281
页数:5
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