| 摘要 |
FIELD: nuclear power engineering. SUBSTANCE: method consists in extraction processing of irradiated nuclear fuel using diluted tributyl phosphate and includes following steps: extracting Zr together with U, Pu, Np, and Tc; washing extract under conditions favoring retention of Zr in extract; completely reextracting Np, Tc, and Zr into nitric acid containing hydrazine nitrate and hydrogen peroxide; separating Pu with mediation of U(IV); and barrier washing of extract to remove simultaneously Pu and Np by the aid of lower hydroxamic acids as nonionic complexing agent. Solution from the latter operation is returned into combined Np, Tc, and Zr reextraction stage. EFFECT: enabled purification of uranium product in one cycle. 5 cl, 2 dwg, 1 tbl |
