A Study on the Separation of Neodymium from the Simulated Solution of $U_3Si/Al$ Spent Nuclear Fuel

모의 사용후분산핵연료($U_3Si/Al$) 용해용액으로부터 네오디뮴 분리에 관한 연구

  • Choi, Kwang Soon (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Kim, Jung Suk (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Han, Sun Ho (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Park, Soon Dal (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Park, Yeong Jae (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Joe, Kih Soo (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Kim, Won Ho (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute)
  • 최광순 (한국원자력연구소 원자력화학연구팀) ;
  • 김정석 (한국원자력연구소 원자력화학연구팀) ;
  • 한선호 (한국원자력연구소 원자력화학연구팀) ;
  • 박순달 (한국원자력연구소 원자력화학연구팀) ;
  • 박영재 (한국원자력연구소 원자력화학연구팀) ;
  • 조기수 (한국원자력연구소 원자력화학연구팀) ;
  • 김원호 (한국원자력연구소 원자력화학연구팀)
  • Received : 2000.06.14
  • Published : 2000.10.25

Abstract

The separation of Nd from the simulated $U_3Si/Al$ spent fuel solution with sequential two-step anion exchange separation has been studied. To prepare the simulated $U_3Si/Al$ spent nuclear fuel, unirradiated $U_3Si/Al$ whose composition consists of small $U_3Si$ particle dispersed in an Al matrix with Al cladding was dissolved with a mixture of 4 M HCl and 10 M $HNO_3$ and 8 or 15 fission product elements were added to the dissolved solution. The trace amount of silica in the solutions was removed by evaporating to dryness with HF and the U was adsorbed on the first anion exchange resin. Neodymium can be purely isolated from the fission product elements with a methanol-nitric acid eluent using the second anion exchange resin. A large excess of Al didn't influence on the elution velocity of Nd, but reduced the eluted contents of Nd, Al, Eu, Gd, Sm and Sr, A large amount of Al was removed first from the column with 3 mL of loading solution (0.8 M $HNO_3$/99.8% MeOH) before Nd elution by the eluent [0.04 M $HNO_3$-99.8% MeOH(1:9)]. The recovery of Nd was more than 94%, regardless of Al contents. Taking the 9 to 13 mL fraction of eluate was effective to purely isolate Nd.

Keywords

neodymium separation;$U_3Si/Al$ fuel;anion exchange chromatography

Acknowledgement

Supported by : 과학기술부

References

  1. 분석과학 v.11 no.6 김정석;전영신;박용준;이창헌;김원호
  2. J. Nucl. Sci. Tech. v.34 no.12 K.H. Kim;D.B. Lee;C.K. Kim;I.H. Kuk;K.W. Paik
  3. J. Korean Nucl. Soc. v.21 no.4 J.S. Kim(et al.)
  4. ASTM E 321-79 v.12.02 no.135
  5. J. Anal. At. Spectrom. v.14 no.1 T. Prohaska;S. Hann;C. Latkoczy;G. Stingeder
  6. Radiochem. v.40 no.3 M.V. Nikonov(et al.)
  7. Analytical Methods in the Nuclear Fuel Cycle J.E. Rein;IAEA-SM-149/40
  8. Sep. Sci. Tech. v.23 no.10,11 S. Usuda;N. Kohno
  9. J. Radioanal. Chem. v.31 no.31 W. Smulek;M. Borkowski
  10. Anal. Chem. v.58 no.1178 N.L. Elliot;L.W. Green;B.M. Recoskie;R.M. Cassidy
  11. J. Radioanal. Nucl. Chem. Art. v.139 no.1 R.M. Cassidy;S. Elchuk;L.W. Green;C.H. Knight;F.C. Miller;B.M. Recoskie
  12. Anal. Chem. v.58 no.1181 R.M. Cassidy;S. Elchuk;N.L. Elliot;L.W. Green;C.H. Knight;B.M. Recoskie