Quantitative Analysis of Trace Metals in Lithium Molten Salt by ICP-AES

ICP-AES를 이용한 리튬 용융염내의 미량 금속성분원소 정량에 관한 연구

  • Kim, Do-Yang (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Pyo, Hyung-Yeal (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Park, Yong-Joon (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Park, Yang-Soon (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Kim, Won-Ho (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute)
  • 김도양 (한국원자력연구소 원자력화학연구팀) ;
  • 표형열 (한국원자력연구소 원자력화학연구팀) ;
  • 박용준 (한국원자력연구소 원자력화학연구팀) ;
  • 박양순 (한국원자력연구소 원자력화학연구팀) ;
  • 김원호 (한국원자력연구소 원자력화학연구팀)
  • Received : 2000.03.09
  • Published : 2000.06.25

Abstract

The quantitative analysis of various trace metals including fission products in lithium molten salts has been performed using a inductively coupled plasma atomic emission spectrometer (ICP-AES). The spectral interferences of lithium content, 500, 1,000 and 2,000 mg/L, in the sample solution were investigated using an optimum wavelength for the respective metal species. As a result, the line intensities for Y, Nd, Sr, and La had no influences from the lithium content up to 2,000 mg/L, while Mo, Ba, Ru, Pd, Rh, Zr and Ce showed spectral interferences of 10% to 50%. The group separation of metals from lithium in the molten salts solution was carried out by adding ammonia water into the solution. The recovery of Ru, Y, Rh, Zr, Nd, Ce, La and Eu was found to be over 90%, while Mo, Ba, Pd, and Sr provided low recovery percentages.

Keywords

Lithium molten salt;ICP-AES;Analysis of fission product;Group separation

Acknowledgement

Supported by : 과학기술부

References

  1. The Chemistry of the Transuranium Element C. Keller
  2. Analyst v.112 P. M. Jimenez;M. Gallego;M. Valcarcel
  3. USAEC Division of Technical Information v.75 Analysis of Essential Nuclear Reactor Materials C. J. Rodden
  4. Radiochim. Acta v.1 A. Guillon;M. Colonomos;R. Sauvagnac
  5. CONF-9407103 Electrochemical separation of actinides and fission products in molten salt R. L. Gay;L. F. Grantham;S. P. Fusselman
  6. Proceedings of GLOVAL '95 Analysis of reduction behavior of oxide fuels by lithium using UO₂and simulated materials T. Usami;M. Iizuka;T. Koyama
  7. Proceedings of GLOVAL '95 Development of lithium process for reprocessing LWR spent fuel M. Fujie;Y. Shoji;T. Kobayashi
  8. ANL/CMT/CP-84354 Pyroprocessing oxide spent nuclear fuels for efficient disposal C. C. Mcpheeters;R. D. Pierce;T. P. Mulcahey
  9. ANL/CMT/CP-89562 Treatment of oxide spent nuclear fuel using the lithium reduction process E. J. Karell;R. D. Pierce;T. P. Mulcahey
  10. Nucl. Technol. v.93 T. Inoue;M. Sakata;H. Miyashiro
  11. J. Inorg. Nucl. Chem. v.6 T. Sato
  12. Nucl. Technol. v.80 H. Kleykamp
  13. J. Chromatogr. v.482 W. Buchberger;K. Winsauer
  14. Spectrochimica Acta v.38B M. A. Floyd;R. W. Morrow;R. B. Farrar
  15. EDB-9504 Solubility of molten salt into liquid lithium M. Hirotake;N. Teruhito;I. Yasuhiko