Equilibration studies of an inorganic ion exchange material with liquid nuclear waste simulant using radiotracer techniques

1978 ◽  
Vol 43 (1) ◽  
pp. 93-100 ◽  
Author(s):  
R. M. Merrill ◽  
P. E. Harrison
Keyword(s):  
Ion Exchange ◽  
Nuclear Waste ◽  
Inorganic Ion ◽  
Exchange Material ◽  
Radiotracer Techniques

Radiocesium removal from high level liquid waste and immobilisation in sodium silicotitanate for geological disposal

2001 ◽  
Vol 89 (3) ◽  
Author(s):  
T. Tomasberger ◽  
A.C. Veltkamp ◽  
A. S. Booij ◽  
U. W. Scherer
Keyword(s):  
Ion Exchange ◽  
Fission Product ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
Geological Disposal ◽  
Inorganic Ion ◽  
Exchange Material ◽  
Leaching Behaviour ◽  
Concentration Factors ◽  
High Level

The isolation of the fission product cesium from high-level alkaline liquid waste is studied with inorganic ion-exchange materials. High separation and concentration factors can be obtained using sodium silicotitanate (CST). The leaching behaviour of cesium from CST was studied in clay porewater and Quinary brine at 90 °C. It is shown that cesium leaching in Quinary brine can be drastically reduced by thermal treatment of cesium loaded CST above 1000 °C. To this end, neutralisation of the ion exchange material before heating is required in order to reduce cesium volatility. It is concluded that CST is a good candidate material for geological disposal of the fission product cesium.

Use inorganic ion exchange materials as precoat filters for nuclear waste effluent treatment

2004 ◽  
Vol 60 ◽  
pp. 85-95 ◽  
Author(s):  
Risto Harjula ◽  
Jukka Lehto ◽  
Airi Paajanen ◽  
Esko Tusa ◽  
P. Yarnell
Keyword(s):  
Ion Exchange ◽  
Nuclear Waste ◽  
Effluent Treatment ◽  
Inorganic Ion

Removal of radiocobalt from EDTA-complexes using oxidation and selective ion exchange

2009 ◽  
Vol 60 (4) ◽  
pp. 1097-1101 ◽  
Author(s):  
L. K. Malinen ◽  
R. Koivula ◽  
R. Harjula
Keyword(s):  
Ion Exchange ◽  
Uv Irradiation ◽  
Ethylenediaminetetraacetic Acid ◽  
Tio2 Photocatalyst ◽  
Edta Complex ◽  
Inorganic Ion ◽  
Edta Complexes ◽  
Degussa P25 ◽  
Exchange Material ◽  
Equimolar Solution

Methods for the removal of radiocobalt from an ethylenediaminetetraacetic acid (EDTA) complex of Co(II) (aqueous solution containing 10 μM Co(II) and 10 μM or 50 μM EDTA traced with 57Co) are presented. The studies examined a combination of different oxidation methods and the sorption of 57Co on a selective inorganic ion exchange material, CoTreat. The oxidation methods used were ultraviolet (UV) irradiation with and without hydrogen peroxide (H2O2), as well as ozonation alone or in combination with UV irradiation. Also, the possible contribution of Degussa P25 TiO2 photocatalyst to degradation of EDTA was studied. The best results for the equimolar solution of Co(II) and EDTA were achieved by combining ozonation, UV irradiation, Degussa P25 TiO2 and CoTreat, with approximately 94% sorption of 57Co. High values for the 57Co sorption were also achieved by ozonation (∼88%) and UV irradiation (∼90%) in the presence of CoTreat and Degussa P25 TiO2. A surplus of EDTA over Co(II) was also tested using 10 μM Co(II) and 50 μM EDTA. Only a slight decrease, to ∼88% sorption of 57Co, was detected compared to the value (∼90%) obtained with 10 μM EDTA.

Xtractite: An Inorganic Ion-Exchange Material for Sorption of Radionuclides

2018 ◽  
pp. 119-131
Author(s):  
Allen W. Apblett ◽  
Nicholas Materer ◽  
Cory Perkins ◽  
Evgueni Kadossov ◽  
Shoaib Shaikh ◽  
...  
Keyword(s):  
Ion Exchange ◽  
Inorganic Ion ◽  
Exchange Material

scholarly journals Synthesis, Characterization and Application of a Derivatized Acidic Salt of a Tetravalent Metal. Pyridine Anchored on to Tin(IV) Tungstoselenate

2000 ◽  
Vol 18 (6) ◽  
pp. 551-560
Author(s):  
S.A. Nabi ◽  
A. Islam ◽  
N. Rahman
Keyword(s):  
Ion Exchange ◽  
Metal Ions ◽  
Ion Exchanger ◽  
Inorganic Ion ◽  
Chemical Studies ◽  
Acidic Salt ◽  
Ft Ir ◽  
Exchange Material ◽  
Ph Range ◽  
Dta Studies

The inorgano-organic ion-exchanger, tin(IV) tungstoselenate–pyridine, has been prepared by derivatizing the inorganic ion-exchange material, tin(IV) tungstoselenate, with an organic moiety, pyridine. Chemical studies showed the tin(IV) tungstoselenate/pyridine mole ratio to be 806.5:1, indicating a weak sorption of pyridine on to the surface of the tin(IV) tungstoselenate. The material was characterized on the basis of SEM, FT-IR, TGA and DTA studies. The uptake of Cu2+, Ni2+, Fe2+ and Fe3+ ions was found to be much higher on tin(IV) tungstoselenate–pyridine relative to tin(IV) tungstoselenate. The uptake of these metal ions as a function of loading and pH was also studied when the following affinity order was observed: Cu2+ > Co2+ > Ni2+ > Fe2+ > Fe3+. The uptake of metal ions increased initially with loading but became constant at higher loading. The most favourable pH range was found to be that between 3.5 and 4.5.

Study of Inorganic Ion Exchange Material MgMn0.25Ti0.75O3

2012 ◽  
Vol 511 ◽  
pp. 113-116
Author(s):  
Jin He Jiang
Keyword(s):  
Ion Exchange ◽  
Experimental Results ◽  
Insertion Reaction ◽  
X Ray ◽  
Thermal Crystallization ◽  
Inorganic Ion ◽  
Crystallization Method ◽  
Treated Sample ◽  
Exchange Material ◽  
Saturation Capacity

The MgMn0.25Ti0.75O3 was synthesized by a coprecipitation/thermal crystallization method. The extraction/insertion reaction with this material was investigation by X-ray, saturation capacity of exchange, and Kd measurement. The acid treatments of MgMn0.25Ti0.75O3 caused Mg2+ extractions of more than 74%, while the dissolutions of Mn4+ and Ti4+ were less than 8.2%. The experimental results have proved that the acid-treated sample has a capacity of exchange 9.5mmol•g-1 for Li+ in the solution.

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