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Measurement of Recovery for Validation of Pretreatment Method in Solidified Cement Ion-Exchange Resin Samples

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

We established pretreatment method of solidified cement ion-exchange resin samples generated before 2003 in nuclear power plants for measurement of non-volatile radionuclide activity. A microwave digestion system (MDS) with mixed acid (HCl-HNO3-HF-H2O2) was used to dissolve cement and to desorb non-volatile elements such as Ce, Co, Cs, Fe, Nb, Ni, Re, Sr and U from mixed ion-exchange resin. The content of Ce, Co, Fe, Nb, Ni, Re, Sr, U and Cs after pretreatment of cement plus mixed ion-exchange resin was measured by ICP-AES and ICP-MS, respectively. As iron and strontium are also present in cement, their content after dissolving a certain amount of cement was measured by ICP-AES. All elements except Nb were quantitatively recovered. Especially since the Nb recovery was low at 72.0±2.5%, the MDS following addition of the mixed acid to the resin was operated once more for desorbing Nb from it. Finally the recovery of Nb was over 95%. This sample pretreatment method will be applied to solidified cement ion-exchange resin samples generated in nuclear power plants for assessment of radionuclide inventory.

저자
  • Kwang Soon Choi(Korea Atomic Energy Research Institute (KAERI)) Corresponding author
  • Gi Yong Kim(Korea Atomic Energy Research Institute (KAERI))
  • Jung-Weon Choi(Korea Atomic Energy Research Institute (KAERI))
  • Jung Bo Yoo(Korea Atomic Energy Research Institute (KAERI))
  • Tae-Hong Park(Korea Atomic Energy Research Institute (KAERI))