Hybrid grafted ion exchanger for decontamination of radioactive cesium in Fukushima Prefecture and other contaminated areas

We have developed a material that can be used to remove cesium (Cs) in Fukushima Prefecture and other contaminated areas. The developed material was prepared by radiation-induced graft polymerization of ammonium 12-molybdophosphate and acrylonitrile onto nonwoven polyethylene fabric. To evaluate the...

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Bibliographic Details
Published inJournal of radioanalytical and nuclear chemistry Vol. 293; no. 2; pp. 703 - 709
Main Authors Iwanade, Akio, Kasai, Noboru, Hoshina, Hiroyuki, Ueki, Yuji, Saiki, Seiichi, Seko, Noriaki
Format Journal Article
LanguageEnglish
Published Dordrecht Springer Netherlands 01.08.2012
Springer
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Summary:We have developed a material that can be used to remove cesium (Cs) in Fukushima Prefecture and other contaminated areas. The developed material was prepared by radiation-induced graft polymerization of ammonium 12-molybdophosphate and acrylonitrile onto nonwoven polyethylene fabric. To evaluate the adsorption performance of the developed material, we conducted batch and column experiments by using a Cs solution with a concentration of 1 ppm at pH 7. In the batch study, the adsorbent was able to remove 90, 87 and 64 % of Cs from pure water, acidic water and seawater, respectively. In the column study, adsorbent packed in a column with a diameter of 7 mm and a height of 5 cm was able to remove nearly the entire amount of dissolved Cs. The solution (1 ppm Cs at pH 7) was pumped into the column at a space velocity of 300 h −1 , in which the Cs adsorption capacity at the breakthrough point reached 54 g-Cs/kg-adsorbent. Adsorbent grafted into a cartridge with a diameter of 4 cm and a height of 3.8 cm was used in a field test on removing dissolved radioactive Cs in Iitate-mura, and this test was conducted successfully.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-012-1721-2