To provide an extraction and separation method of Ca and Sr existing in a nitric acid solution having a high concentration by using only diglycol amide or a mixed solvent with monoamide, especially a method of recovering efficiently Ca and Sr existing in a radioactive waste liquid generated from reprocessing of a spent nuclear fuel.
In this method, calcium (Ca) and strontium (Sr) in a nitric acid solution containing high-level radioactive waste liquid (HLLW) are extracted and separated efficiently by using a solvent produced by diluting into dodecane, tridentate-ligand digycol amide (DGA) having a long alkyl chain and high lipophilicity. The method enables solvent extraction separation of Ca and Sr included in the nitric acid acidic solution with various concentrations by using only diglycol amide or the mixed extraction solvent with monoamide.
COPYRIGHT: (C)2004,JPO&NCIPI
| JPH0576801 | SOLID-LIQUID SEPARATOR |
| JPH01135501 | FLOW QUANTITY CONTROL APPARATUS FOR MIXER SETTLER |
Tatemori Shoichi
| JP7246303A | ||||
| JP2003243890A | ||||
| JP2002001007A |
Shinjiro Ono
Yasushi Kobayashi
Akio Chiba
Hiroyuki Tomita
Shurin Sakurai
Fujihiro Kanda
Hideo Tanaka
Shinya Hosokawa
Norihiro Fukasawa
Koji Hirayama