Determination of La in $U_3Si/Al$ Spent Nuclear Fuel by Ion Chromatography-Inductively Coupled Plasma-Mass Spectrometry

Ion Chromatography-Inductively Coupled Plasma-Mass Spectrometry에 의한 $U_3Si/Al$ 사용후핵연료 중 La의 분리 및 정량

  • 한선호 (한국원자력연구소 원자력화학연구팀) ;
  • 최광순 (한국원자력연구소 원자력화학연구팀) ;
  • 김정석 (한국원자력연구소 원자력화학연구팀) ;
  • 전영신 (한국원자력연구소 원자력화학연구팀) ;
  • 박양순 (한국원자력연구소 원자력화학연구팀) ;
  • 지광용 (한국원자력연구소 원자력화학연구팀) ;
  • 김원호 (한국원자력연구소 원자력화학연구팀)
  • Received : 2000.07.27
  • Published : 2000.10.25

Abstract

Lanthanum has been used as one of the burnup monitor in spent nuclear fuel. $U_3Si/Al$ spent nuclear fuel contains small amount of La in high concentration of U and Al. Therefore, chemical separation of La is required to remove matrix elements. At first, ion chromatography (IC) and inductively coupled plasma systems were installed in radiation shielded glove box to handle the radioactive samples. Retention behavior of uranium, aluminum, lanthanum and some interesting fission products (Sr, Zr, Y, Mo, Ru, Pd, Rh, Cs, Ba, Ce, Pr, Nd, Sm, Eu and Cd) was investigated using the CG10 column and ${\alpha}$-HiBA eluent. As all elements were eluted earlier than lanthanum in 0.2 M ${\alpha}$-HiBA eluent, a portion of U and Al was directly passed to waste using a three way valve between the column and the nebulizer. Thus it was possible to determine the lanthanum in a high concentration of U and Al matrix. Retention time of La was about 12 minutes in this separation condition. Optimum range for the determination of La in $U_3Si/Al$ spent nuclear fuel was $1-10{\mu}g/L$ (ppb) with this system and detection limit was $0.25{\mu}g/L$ in case of $200{\mu}L$ of sample volume.

Keywords

IC-ICP-MS;$U_3Si/Al$;spent nuclear fuel;matrix elimination;determination of lanthanum

Acknowledgement

Supported by : 과학기술부

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