发明名称 Extracting method of radioactive 99Mo from low enriched uranium target
摘要 <p>The method comprises heating a target of low enriched uranium (LEU) of high voluminal mass containing alloy particles of LEU; dissolving the target of LEU in an alkaline solution; and extracting molybdenum-99 ( 9> 9>Mo) from the alkaline solution in which the target of LEU is dissolved. The target of LEU includes a target of uranium alloy of plate or annular type, and has a uranium density of >= 8 g-U/cm 3>. The heating step is carried out at a temperature of 700-800[deg] C for 10 minutes to 12 hours in an atmosphere of vacuum or inert. The method comprises heating a target of low enriched uranium (LEU) of high voluminal mass containing alloy particles of LEU; dissolving the target of LEU in an alkaline solution; and extracting molybdenum-99 ( 9> 9>Mo) from the alkaline solution in which the target of LEU is dissolved. The target of LEU includes a target of uranium alloy of plate or annular type, and has a uranium density of >= 8 g-U/cm 3>. The heating step is carried out at a temperature of 700-800[deg] C for 10 minutes to 12 hours in an atmosphere of vacuum or inert. The target of LEU after the heating step exists in a form of uranium aluminizing to a fraction of >= 80%. The extraction step is performed by a method consisting of adsorption, chromatography, ion exchange and separation by precipitation.</p>
申请公布号 KR101460690(B1) 申请公布日期 2014.11.11
申请号 KR20120089406 申请日期 2012.08.16
申请人 发明人
分类号 G21D5/00 主分类号 G21D5/00
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