Separation and Purification for the Determination of Samarium and its Isotopes in PWR Spent Nuclear Fuels

PWR 사용후핵연료 중 Sm 동위원소 정량을 위한 분리 및 정제

  • 김정석 (한국원자력연구소 원자력화학연구팀) ;
  • 전영신 (한국원자력연구소 원자력화학연구팀) ;
  • 최광순 (한국원자력연구소 원자력화학연구팀) ;
  • 박순달 (한국원자력연구소 원자력화학연구팀) ;
  • 이창헌 (한국원자력연구소 원자력화학연구팀) ;
  • 김원호 (한국원자력연구소 원자력화학연구팀)
  • Received : 2001.03.19
  • Published : 2001.08.25


A method of separation and purification of Sm for quantitation of Sm isotopes from various fission products in PWR spent nuclear fuels has been studied. Simulated solution containing inactive metal ions(Cs, Ba, Gd, Eu, Sm and Nd) in place of radioactive fission products was prepared. Sm was separated with 0.5 M $HNO_3$/80% MeOH after washing with 1 M $HNO_3$/90% MeOH on AG $1{\times}8$, anion exchange resin. Sm was purified on cation exchange resin, AG $50W{\times}8$, pretreated with 0.2 M alpha-hydroxisobutyric acid(pH 4.5-4.6) to remove Ba causing isobaric effect Sm from PWR spent fuel. As a result of mass spectrometric measurement, eluted Sm portion did not include isobars form other elements such as Gd, Eu, Pm, Nd and BaO. The contents of Sm and its isotopes($^{147}Sm$, $^{148}Sm$, $^{149}Sm$, $^{150}Sm$, $^{151}Sm$, $^{152}Sm$ and $^{154}Sm$) in spent fuel were determined by isotope dilution mass spectrometric method spiking $^{154}Sm$.