抄録
Separation of 238Pu and 242Cm from irradiated 241Am was performed by means of solvent extraction using bis-(2-ethylhexyl) phosphoric acid (HDEHP). From a 0.1M nitric acid mixed solution, 238Pu and 242Cm were extracted by 50% HDEHP xylene or dodecane solution, leaving 241Am(V) in the aqueous solution. The extraction was made immediately after reducing Am(VI) to Am(V) with hydrogen peroxide. The 242Cm and 238Pu were stripped from the organic solution into 1M nitric acid and 9M hydrochloric acid-2.5% ferrous sulfamate solutions, respectively. The decontamination factor of 241Am for 242Cm was 30±10 for one cycle of the separation procedure. The yield of 238Pu, 241Am or 242Cm was 80, 95-97 or 70-98%, respectively.
