发明名称 PROCESSING METHOD AND ITS PROCESSING APPARATUS OF RADIOACTIVE WASTE LIQUID
摘要 PROBLEM TO BE SOLVED: To resolve a problem that solidifying sodium stably for long, which is a counter ion of sulfate ion, is difficult because due to isolation of sodium, pH of interstitial water of solidified object rises and there was a fear of solving of bentonite postulated for use in underground disposal site. SOLUTION: In the disposal method for radioactive waste liquid including sodium sulfate generated out of nuclear facilities, by adding hydrogen peroxide in the waste liquid as an auxiliary agent raising mineralization reaction rate when organic compound contained in the radioactive waste liquid is mineralize by ozonation treatment and closure of nuclides in waste is raised, mineralization becomes possible and cement solid stable for long period can be obtained. COPYRIGHT: (C)2006,JPO&NCIPI
申请公布号 JP2005283414(A) 申请公布日期 2005.10.13
申请号 JP20040099548 申请日期 2004.03.30
申请人 TOSHIBA CORP;TOSHIBA PLANT SYSTEMS & SERVICES CORP 发明人 MIYAMOTO MASAYA;MIKURA MICHITAKA;SATO TATSUAKI;SAKURAI MANABU;TAKADA TAKAO;FUKUSHIMA TADASHI;MORIKAWA JUNICHI;TAJIMA FUMIO
分类号 G21F9/06;G21F9/16;(IPC1-7):G21F9/06 主分类号 G21F9/06
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