发明名称 PRETREATMENT METHOD FOR NUCLIDE ANALYSIS OF RADIOACTIVATED GRAPHITE, NUCLIDE SEPARATION METHOD AND PRETREATMENT EQUIPMENT OF NUCLIDE ANALYSIS
摘要 PROBLEM TO BE SOLVED: To separate transuranium elements by fixing radionuclides in radioactivated graphite waste generated from nuclear facilities in liquid, solving in liquid, suppressing or preventing generation of radioactive gas and making it coexist in common sediment. SOLUTION: The separation process comprises a liquefacient loading process (S2) for loading liquefacient in radioactivated graphite, a heating/melting process (S4) for heating and melting the radioactivated graphite loaded with the liquefacient, and a water solving process (S5) for melting the heated and molten radioactivated graphite in water. COPYRIGHT: (C)2006,JPO&NCIPI
申请公布号 JP2005338019(A) 申请公布日期 2005.12.08
申请号 JP20040160563 申请日期 2004.05.31
申请人 TOSHIBA CORP 发明人 MURATA EIICHI;HARUGUCHI YOSHIKO;MIKURA MICHITAKA;HOSAKA KATSUMI;HATAKEYAMA HIDEO
分类号 G01N1/04;G01T1/167;G21C17/00;G21F9/10;G21F9/30;(IPC1-7):G21C17/00 主分类号 G01N1/04
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