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


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.


Supported by : 과학기술부


  1. Technical Note 23
  2. J. Chromatogr. A. v.739 no.139 S. Rollin;Z. Kopatjtic;B. Wernli;B. Magyar
  3. J. Anal. Chem. v.362 no.433 W. Kerl;J.S. Becker;W. Dannecker;H.-J. Dietze
  4. J. Anal. At. Spectrom. v.14 no.875 J.M. Barrero Moreno;M. Betti;G. Nicolaou
  5. J. Anal. At. Spectrom. v.10 no.381 J.I. Garcia Alonso;F. Sena;P. Arbore;M. Betti;L. Koch
  6. J. Radioanal. Nucl. Chem. v.194 no.7 M.R. Smith;O.T. Farmer;J.H. Reeves;D.W. Koppenaal
  7. Analytical Science & Technology v.10 no.4 K.S. Park;S.T. Kim
  8. Anal. Chem. v.58 no.1181 R.M. Cassidy;E. Elchuck;N.L. Elliot;L.W. Green;C.H. Knight;B.M. Recoskie
  9. Standard Test Method for Atom Percent Fission in Uranium Fuel (Radiochemical Method) ASTM E219-80 American Society for Testing and materials
  10. Analytical Science & Technology v.11 no.4 Y.W. Heo;J.I. Gil;H.B. Lim
  11. Anal. Chem. v.56 no.474 C.H. Knight;R.M. Cassidy;B.M. Recoskie;L.W. Green
  12. ASTM E692-79 American Society for Testing and materials Standard Test Method for Cesium-137 in irradiated nuclear Fuels by high resolution gamma-ray spectral analysis
  13. Analytical Science & Technology v.11 no.2 K.S. Park;S.Y. Song;U.S. Shim;S.T. Kim
  14. J. Anal. At. Spectrom. v.12 no.355 J.M. Barrero Moreno;M. Betti;J.I. Garcia Alonso
  15. J. Anal. At. Spectrom. v.11 no.929 J.M. Barrero Moreno;J.I. Garcia Alonso;P. Arbore;G. Nicolaou;L. Koch
  16. ASTM E321-79 American Society for Testing and materials Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)
  17. Proceedings of the Korean Nuclear Society, Autumn meeting Jung Suk Kim;Kwang Soon Choi;Young Shin Jeon;Yang Soon Park;Sung Ho Han;Do Yang Kim;Kwang Yong Jee
  18. J. Radioanal. Nucl. Chem. v.139 no.55 R.M. Cassidy;S. Elchuck;L.W. Green;C.H. Knight;F.C. Miller;B.M. Recoskie