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Stabilization and volume reduction of radioactive spent ion exchange resins 被引量:1

Stabilization and volume reduction of radioactive spent ion exchange resins
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摘要 Stabilization and volume reduction Of spent radioactive ion-exchange resins (IERs) were studied. Stabilization technology includes volume reduction with wet Chemical oxidation process and immobilization of the residue into cement. Under suitable conditions, the exhaussted radioactive ion-exchange resins were dissolved successfully in a H2,O2-Fe2+/Cu2+ catalytic oxidation system (Fenton reagent). The analytical results indicated that the radioactive nuclides loaded in the resins were concentrated in decomposed solution and solid residues. The process parameters of wet chemical oxidation and solidification were also obtained. The decomposition ratios were 100% and more than 90% for canon and anion IERs respectively. The waste volume was decreased by 40% compared with that of original spent resins. Stabilization and volume reduction Of spent radioactive ion-exchange resins (IERs) were studied. Stabilization technology includes volume reduction with wet Chemical oxidation process and immobilization of the residue into cement. Under suitable conditions, the exhaussted radioactive ion-exchange resins were dissolved successfully in a H2,O2-Fe2+/Cu2+ catalytic oxidation system (Fenton reagent). The analytical results indicated that the radioactive nuclides loaded in the resins were concentrated in decomposed solution and solid residues. The process parameters of wet chemical oxidation and solidification were also obtained. The decomposition ratios were 100% and more than 90% for canon and anion IERs respectively. The waste volume was decreased by 40% compared with that of original spent resins.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2001年第1期68-72,共5页 核技术(英文)
关键词 离子交换树脂 水泥固化 湿式化学氧化 放射性废料处理 Radioactive spent resin, Solidification, Wet chemical oxidation
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  • 1Giuffre M. Waste Manage,1984, 2:1,31
  • 2Place B G. Engineering study for the treatment of spention exchange resin resultingfromnuclear process applications.WHC-EP-0375(DE91404550), 1990, 9:7
  • 3Bater R. Wet oxidation of organic ion-exchange resins with hydrogenperoxide-radwaste processdevelopment, Radioactive waste management 2. BNES, London, 1989
  • 4Haber F, Weiss J. Royal Soc London, 1985, 1157A:332
  • 5Nonhebel D C, Walton J C, Free-radicalchemistry. Cambridge University Press, 1974
  • 6Walling C, Kato S.J Chem Soc, 1971, 8:4275

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