RADIATION PROTECTION ›› 2022, Vol. 42 ›› Issue (4): 280-286.

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Determination of 55Fe and 63Ni in spent resin of nuclear power plant using radiochemical separation and liquid scintillation counting

MA Lina, WANG Lusheng, SONG Lijuan, ZHANG Hui, DAI Xiongxin   

  1. China Institute for Radiation Protection, Shanxi Provincial Key Laboratory for TranslationalNuclear Medicine and Precision Protection, Taiyuan 030006
  • Received:2021-06-04 Online:2022-07-20 Published:2022-08-15

Abstract: In this work, a method for sequential determination of 55Fe and 63Ni in spent resins of nuclear power plants was developed. After decomposing the spent resin sample, 55Fe and 63Ni ions were first precipitated in the form of hydroxide and subsequently purified by anion exchange chromatography and dimethylglyoxime precipitation. After purification, 55Fe and 63Ni were determined by liquid scintillation counting (LSC). The average chemical recovery rate of 55Fe and 63Ni was 86% and 90% respectively. The decontamination factors of interfering radionuclides such as 60Co, 65Zn and 54Mn by the sequential determination method were higher than 1 000. The deviation of expected and measured values was less than ±10% through the validation of the analytical method with spiked samples. The measured average activities of 55Fe and 63Ni in a set of spent resin samples from its primary loop of a nuclear power plant were (76.2±1.4) kBq/g and (120.0±5.1) kBq/g, respectively.

Key words: 55Fe, 63Ni, spent ion-exchange resin, LSC, sequential determination

CLC Number: 

  • O658.1+3