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Desorption of lithium 7 isotope from a degraded amberlite lithiated mixed-bed-resin
Author(s)
Basitere, Moses
Date Issued
2011
Type
Thesis
Publisher
Cape Peninsula University of Technology
Abstract
Lithium 7 (⁷Li⁺) is an isotope, which is used in the nuclear industry as lithium hydroxide
(⁷LiOH) for the chemical control (pH control) of the high purity reactor coolant water process
in order to prevent corrosion in the Pressurised Water Reactor (PWR). Furthermore, the ⁷Li⁺
isotope is used in an ionic form in the nuclear grade cation ion-exchange resin. This resin is
used to purify the nuclear reactor coolant water by reducing cationic corrosion by-products
such as Cesium and Cobalt, which are generated from nuclear fission reactions. In view of
the fact that an inorganic salt of the isotope is used as an alkali sing agent in the PWR, the use
of lithiated resin prevents the removal of the ⁷Li⁺ isotope in the coolant water. As most users
of the nuclear grade resin purchase their resin in bulk, it follows that the resin has to be
evaluated in order to determine its usability. In certain cases, the resin may be considered
unusable as a result of the degradation caused by unsuitable transportation and storage
conditions. These, in turn, perpetuate the release of leachates, which may further contribute to
corrosion in the PWR. This necessitated the undertaking of this study, which was to evaluate
whether it is possible to recover the high value ⁷Li⁺ isotope from a degraded nuclear grade
resin in such a way that the isotope may be used in the PWR.
(⁷LiOH) for the chemical control (pH control) of the high purity reactor coolant water process
in order to prevent corrosion in the Pressurised Water Reactor (PWR). Furthermore, the ⁷Li⁺
isotope is used in an ionic form in the nuclear grade cation ion-exchange resin. This resin is
used to purify the nuclear reactor coolant water by reducing cationic corrosion by-products
such as Cesium and Cobalt, which are generated from nuclear fission reactions. In view of
the fact that an inorganic salt of the isotope is used as an alkali sing agent in the PWR, the use
of lithiated resin prevents the removal of the ⁷Li⁺ isotope in the coolant water. As most users
of the nuclear grade resin purchase their resin in bulk, it follows that the resin has to be
evaluated in order to determine its usability. In certain cases, the resin may be considered
unusable as a result of the degradation caused by unsuitable transportation and storage
conditions. These, in turn, perpetuate the release of leachates, which may further contribute to
corrosion in the PWR. This necessitated the undertaking of this study, which was to evaluate
whether it is possible to recover the high value ⁷Li⁺ isotope from a degraded nuclear grade
resin in such a way that the isotope may be used in the PWR.
Additional information
Thesis (MTech (Chemical Engineering))--Cape Peninsula University of Technology, 2011.
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Name
205198120_Basitere_M_Mtech_Chemical Engineering_Eng_2011_20114674.pdf
Description
Thesis
Size
41.66 MB
Format
Adobe PDF
Checksum
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