• 文献标题:   Removal of Cs, Sr, U and Pu species from simulated nuclear waste effluent using graphene oxide
  • 文献类型:   Article
  • 作  者:   CAREY T, WILLIAMS CD, MCARTHUR DJ, MALKINSON T, THOMPSON OR, BAIDAK A, MURTAGH L, GLODAN G, MORGAN SP, BANFORD AW
  • 作者关键词:   graphene oxide, nuclear decommissioning, effluent, decontamination, radionuclide sorption, ion exchange
  • 出版物名称:   JOURNAL OF RADIOANALYTICAL NUCLEAR CHEMISTRY
  • ISSN:   0236-5731 EI 1588-2780
  • 通讯作者地址:   Natl Nucl Lab
  • 被引频次:   3
  • DOI:   10.1007/s10967-018-5931-0
  • 出版年:   2018

▎ 摘  要

This article reports the findings from a series of radioactive experimental trials which have examined the sorption properties of graphene oxide focused on four key radionuclides commonly linked to effluent challenges in the nuclear industry-Cs, Sr, U and Pu. Unlike previous experimental studies, simulated effluent waste solutions were utilised with compositions typical of those found at the Sellafield nuclear site, UK. Molecular dynamics simulations were performed in parallel to elucidate the functional groups to which radionuclides preferentially adsorb.