• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.2
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• pp.123-132
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• 2007

This study was performed to evaluate the co- and mutual separation for Am, Cm and RE elements from the simulated multi-component solution equivalent to real HLW level by a Zr-DEHPA(di-(2-ethylhexyl) phosphoric acid containing Zirconium)/$NDD(n-dodecane)-HNO_3$ extraction system. Zr-DEHPA was self-synthesized and the optimal condition of (15g/L Zr-1M DEHPA)/NDD-1M $HNO_3$ was selected taking into consideration of prevention of the third phase, and effects of concentration of DEHPA, nitric acid and impregnant amount of Zr on the co-extraction of Am, Cm and RE. In that condition, the extraction yields were 81% (Am), 85% (Cm), more than 80% (RE elements), 98% (Mo), 85% (Fe), 98% (U), 73% (Np), and less than 5% (other elements) so that the system developed for the co-extraction of Am-Cm/RE was proved to be available. For that, however, U, Np, Mo and Fe was elucidated to have to be removed in advance, and Zr inducing the third phase formation was found to be practically excluded. The co-extracted Am-Cm/RE were sequentially separated in an order of Am-Cm (stripping agent : 0.05 M DTPA-1M Lactic acid of pH 3.6)${\rightarrow}RE$ (stripping agent : 5M $HNO_3$), and then their separation factors were evaluated. At above conditions, Am of 65.4%, Cm of 63.9%, RE (except for Y) of more than 85% were stripped.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.377.1-377
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• 2001

• Applied Chemistry for Engineering
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• v.8 no.6
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• pp.1006-1013
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• 1997

This study was carried out to elucidate the chemical characteristics of mutual separation for Am and Eu, which were selected as a stand-in from minor actinide and rare earth elements, by solvent extraction with di-(2-ethylhexyl)phosphoric acid containing zirconium at batch system. As results, 92.3% of Am and 99.1% of Eu were coextracted with 1M DEHPA/n-dodecane containing zirconium (Zr $concentration=8.7g/{\ell}$) at 0.5M $HNO_3$ in the extraction step. The extraction yields of Am and Eu were proportionally increased with the concentration of Zr in Zr salt of 1M DEHPA/n-dodecane having the synergistic effect. In the lst stripping step for the selective separation of Am, 38.1% of Am and 3% of Eu were stripped with the mixed solution of 0.05M DTPA and 1M lactic acid adjusted pH of 3.0. At that time, the separation factor calculated from the distribution coefficients of Am and Eu was 14.2. In the 2nd Stipping step to remove the Eu remained the organic phase after the lst stripping step, 94.4% 0f Eu was stripped into aqueous phase with 6M $HNO_3$.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.11a
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• pp.305-306
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• 2006

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.521-526
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• 1998

군분리공정의 관심대상 핵종인 잔존 U, MA인 Am, Np 및 백금족원소의 장수명핵종인 Tc을 방사성모의용액으로부터 효과적으로 분리할 수 있었다. 각 단위공정에 주입되는 용액의 농도를 기준으로 하여 볼 때 잔존 U 제거 공정에서 U, Np, 및 Tc의 회수율은 각각 99.1%. 31.9%, 및 99.5%였다. 개미산 탈질 공정에서는 탈질 용액의 총 산도를 0.4M 이하까지 감소시켰으며, 부수적으로 후속용매추출 공정 전반에 걸쳐 문제 핵종으로 작용하는 Zr, Mo, Fe 등을 각각 99.8%, 94.2%, 22.4% 침전 제거시킬 수 있었다. 마지막으로 DEHPA에 의한 AM/RE 상호분리 공정에서는 연속적인 선택적역추출에 의해 Am 및 Np 의 회수율은 각각 99.8% 및 98.2％ 정도였고, Am의 경우 7.6%읜 Fe및 81.6% 의 Mo가, Np의 경우 5.8%의 Fe이 불순물로서 여전히 존재하고 있다. 한편 RE 생성물에서는 97～99.9%의 RE가 회수 제거되었다.