TREATMENT OF LOW– AND INTERMEDIATE– LEVEL RADIOACTIVE LIQUID WASTE FROM ALTWATHA SITE USING IRAQI ZEOLITE
Ion exchange material used in this study is synthetic inorganic resin. It is Iraqi synthetic zeolite type Na-A, which was prepared from Iraqi kaolinite. The prepared zeolite pellets were solidified by heat treatment at 600oC for 3 hours. Nine radiochemical experiments were carried out on real (radi...
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フォーマット: | 論文 |
言語: | English |
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University of Baghdad
2007-03-01
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シリーズ: | Journal of Engineering |
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オンライン・アクセス: | https://joe.uobaghdad.edu.iq/index.php/main/article/view/2382 |