화학공학소재연구정보센터
홈 로그인 로그아웃 연락처 사이트맵
Journal of the Korean Industrial and Engineering Chemistry, Vol.12, No.3, 294-299, May, 2001
Export Citation
U/Np/Tc 계의 공추출 및 순차 분리 연구
Co-extraction and Sequential Stripping of Np/U/Tc System
김광욱†, 김수호, 송기찬, 이일희
  • 한국원자력연구소, 대전 305-350
Kwang Wook Kim†, Soo Ho Kim, Kee Chan Song, and Eil Hee Lee
  • Korea Atomic Energy Research Institute, Daejeon 305-350, Korea
E-mail:
초록
소멸처리 독성 및 대상 핵종인 U과 Tc, Np을 방사성 고준위 폐액으로부터 제거하기 위해 30 vol.% TBP를 이용한 이들 핵종의 공추출 및 순차분리 연구가 수행되었다. U, Tc, Np의 추출 및 역추출 거동 실험으로부터 U, Tc, Np 공추출 → Tc 분리 → Np 분리 → U 분리의 순서와 분리 조건이 제시되었다. U,Tc, Np의 공추출 시 Np의 추출율을 증진시키기 위하여 용액 중에 공존하는 Np(V)를 Np(VI)으로 전해 산화하는 방법이 필요하였으며, 역추출을 위해 Tc는 5 M 질산을, Np은 Np(VI)를 Np(V)으로 전해환원을, U은 0.3 M Na2CO3을 사용하는 것이 적절하였다. 추출 상비(O/A) 및 역추출 상비(A/O)는 모두 2 ~ 3을 유지하는 것이 필요하였다.
In order to remove U, Tc, Np, the target nuclides for transmutation, from the high-level radioactive waste, a process for co-extraction and sequential stripping of the nuclides was studied by using 30 vol.% TBP. On the basis of our experiments on extraction and stripping of each element of U, Tc, and Np, a combination of co-extraction of U, Tc, Np → Tc stripping → Np stripping → U stripping has been suggested. To increase of Np extraction yield, the electrolytic oxidation of Np(V) in Np solution was required at the step of co-extraction. In order to strip the extracted elements, sequentially 5 M nitric acid for Tc, electrolytic reduction of Np(VI) to Np(V) for Np, and 0.3 M sodium carbonate for U were used, respectively. The phase ratio (O/A or A/O) of the co-extraction and stripping were maintained at around 2 ~ 3.
Keywords:uranium;neptunium;technetium;TBP;glassy carbon fiber;electrochemical;oxidation;reduction
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