A New Approach to Simulation of Extraction Equilibria in the PUREX Process

REFERENCES

• Kolaric, Z.; Dressler, P. Extraction and coextraction of Tc(VII), Np(IV, VI), Pa(V) and Nb(V) with tributyl phosphate from nitric acid solutions. Solv. Extr. Ion Exch. 1989, 7(4), 625–644.
   Web of Science ®Google Scholar
• Wallwork, A.L.; Denniss, I.S.; Taylor, R.J.; Bothwell, P.; Birkett, J.E.; Baker, S. Modelling of advanced flowsheets using data from miniature contactor trials. Nucl. Energ. 1999, 38(1), 1999, 31–35.
   Web of Science ®Google Scholar
• Ban, Y.; Hotoku, S.; Morita, Y. Selective extraction of U(VI) by counter-current liquid-liquid extraction with N,N-di(2-Ethylhexyl)-2,2-dimethylpropanamide. Solv. Extr. Ion Exch.; 2011, 29 (N 4), 519–533.
   Web of Science ®Google Scholar
• Natarajan, R.; Pandey, N.K.; Vijayakumar, V.; Subbarao R.V. Modeling and simulation of extraction flowsheet for FBR fuel reprocessing. Procedia Chemistry. 2012, 7, 302–308.
   Google Scholar
• Rozen, A.M.; Reshet’ko, Yu.V.; Zel’venskii, M.Ya. Mathematical modelling of extraction procedures for reprocessing nuclear fuel. Soviet Atomic Energy, 1974, 37(3), 895–903.
   Google Scholar
• Puzikov, E.A.; Zilberman, B.Ya.; Fedorov, Yu.S.; Mishin, E.N.; Shmidt, O.V.; Goletsky, N.D.; Sytnik, L.V. Mathematical simulation of steady-state concentration profiles in extraction cascades for reprocessing NPP spent fuel using TBP-compatible processes (Superpurex)”. Radiochemistry, 2004, 46(2), 149–156.
   Google Scholar
• Puzikov, E.A.; Zilberman, B.Ya.; Fedorov, Yu.S.; Blazheva, I.V.; Kudinov, A.S.; Ryabkova, N.V. New data on joint extraction of actinide nitrates and some acids with tributyl phosphate diluted with paraffins and mathematical description of the process by A.M. Rozen’s Model. Radiochemistry, 2013, 55(2), 190–202.
   Google Scholar
• Kumar, Sh.; Koganti, S. B. Modelling of Np(VI) and Np(IV) distribution coefficients in 30% TBP/ n-dodecane/ nitric acid/water biphasic purex system. Ind. J. Chem. Techol. 2001, 8, 41–43.
   Web of Science ®Google Scholar
• Sarsfield, M.J.; Sims, H.E.; Taylor, R.J. Extraction of neptunium (IV) Ions into 30% tri-butyl phosphate from nitric acid. Solvent Extr. Ion Exch. 2009, 27(5), 638–662.
   Web of Science ®Google Scholar
• Zilberman B.Ya.; Fedorov Yu.S.; Puzikov E.A.; Blazheva, I.V. New data on joint extraction of nitric acid, uranium(VI) and tetravalent elements by diluted TBP and new approach to modeling of their distribution. ATALANTE 2008, Montpellier, France, May 19–23, 2008, Paper O1-17.
   Google Scholar
• Puzikov, E.A.; Zilberman, B.Ya.; Fedorov, Yu.S.; Blazheva, I.V.; Kudinov, A.S. A new approach to mathematical description of the extraction of HNO₃, U(VI), and other hexavalent actinides with tributyl phosphate in a mixture with paraffins. Radiochemistry 2013, 55(3), 291–297.
   Google Scholar
• Fedorov, Yu.S; Zilberman, B.Ya.; Poverkova, L.Ya. Neptunium(IV) solvate species in TBP formed by extraction from nitric acid solutions in the presence of uranyl nitrate. Radiokhimiya (rus). 2000, 42(5), 417–422.
   Google Scholar
• Puzikov, E.A.; Blazheva, I.V.; Zilberman, B.Ya.; Fedorov, Yu.S.; Kudinov, A.S.; Ryabkova, N.V.; Sysoeva, A.V.; Goletsky, N.D.; Biragova, Ya.V.; Shadrin A.Yu. Extraction of nitric acid and uranyl nitrate with tributyl phosphate in diluent in the presence of salting-out agents and its mathematical description. Radiochemistry 2013, 55(4), 369–376.
   Google Scholar
• Zilberman, B.Ya.; Fedorov, Yu.S.; Puzikov, E.A.; Blazheva, I.V. Development of the database and adaptation of the mathematical model of the purex process to the conditions of reprocessing of highly burned-up spent nuclear fuel from nuclear power plants. Preprint of the Khlopin Radium Inst.; St. Petersburg, 2009, N 264, 80 p.
   Google Scholar
• Srinivasan, N.; Ramaniah, M.V.; Patil, S.K.; RamKrishna, V.V.; Swarup, R.; Chadha, A.; Avadhani, G.V.N. Tech. Report BARC-736 (Trombay, India), 1974.
   Google Scholar
• Puzikov, E.A.; Zilberman, B.Ya.; Fedorov, Yu.S.; Blazheva, I.V.; Kudinov, A.S.; Goletskii, N.D. Extraction of tetravalent actinides and zirconium from nitric acid solutions with tributyl phosphate in diluent in the presence of uranyl nitrate and its mathematical description within the framework of the new approach. Radiochemistry, 2013, 55(5), 481–485.
   Google Scholar
• Puzikov, E.A.; Zilberman, B.Ya.; Fedorov Yu.S.; Blazheva, I.V.; Palenik, Yu.V.; Kudinov, A.S.; Goletskii, N.D.; Ryabkov, D.V. Mathematical description of admixed acids extraction by diluted tributyl phosphate and co-extraction of their anions with uranyl nitrate. Radiochemistry. 2014, 56(2), 143–147.
   Google Scholar
• Vereshchagin, V.E.;Renard, E.V. Solvent-extraction equilibria in reprocessing fast-reactor uranium-plutonium fuel. Soviet Atomic Energy. 1978, 44(H5H), 487–492.
   Web of Science ®Google Scholar
• Vereshchagin, V.E.;Renard, E.V. Fast-reactor uranium-plutonium extraction by equilibrium water systems with 0.15–1 M HNO3 acidity. Soviet Atomic Energy. 1978, 45(1), 701–705.
   Web of Science ®Google Scholar
• Puzikov, E.A.; Zilberman, B.Ya.; Blazheva, I.V.; Mishin, E.N.; Ryabkova, N.V. New data on extraction of nitric acid with 30% TBP from solutions containing uranyl nitrate. Recent Advances in Actinide Science (Proc. Int. Conf. “Actinides’2005”). RSC Publ.; Cambridge, 2006; pp 515–517.
   Google Scholar
• Blazheva, I.V.; Zilberman, B.Ya.; Fedorov, Yu.S.; Mishin, E.N.; Ryabkova, N.V. New Data on Extraction of Tetravalent Uranium with 30% TBP from Solutions Containing Uranyl Nitrate. Recent Advances in Actinide Science (Proc. Int. Conf. “Actinides’2005”). RSC Publ.; Cambridge, 2006; pp 617–619.
   Google Scholar
• Müller K.; Brendler V.; Foerstendorf H. Aqueous uranium(VI) hydrolysis species characterized by attenuated total reflection Fourier-transform infrared spectroscopy. Inorg Chem. 2008, 47(21) 10127–10134.
   PubMed Web of Science ®Google Scholar
• Ochkin, A.V.; Gladilov, D.V.; Nekhaevskii, S.Yu. Calculatuon of the composition of the organic phase of the H2O – HNO3 – tri-n-butylphosphate system. Russian J Phys. Chem. A, 2009, 83(10), 1802–1806.
   Web of Science ®Google Scholar
• Fedorov, Yu.S.; Zilberman, B.Ya. Extraction of neptunium and plutonium into tributyl phosphate at total loading with uranyl nitrate. Radiochemistry. 1988, 20(4), 572–576.
   Google Scholar
• Garraway, J.; Wilson, P.D. Coextraction of pertechnetate and zirconium by tri-n-butyl phosphate. J. Less-Common Met.; 1985, 106, 183–191.
   Google Scholar
• Zilberman, B.Ya.; Mishin E.N.; Fedorov, Yu.S.; Krinitsyn, A.P.; Puzikov, E.A.; Borovikov, E.A.; Ryazantsev, V.I.; Deniss, I.S.; Wallwork, A.L. Zirconium distribution in counter-current multistage contactors during its extraction from nitric acid solutions in the presence of uranium and technetium. Khimicheskaya Tekhnologiya (Chemi. Eng.), 2001, 2(7), 26–36.
   Google Scholar
• Zilberman, B.Ya.; Blazheva, I.V.; Shadrin, A. Yu.; Puzikov, E.A.; Goletskii, N.D.; Kuharev, D.N.; Borovikov, E.A.; Fedorov, Yu.S. Processing method of irradiated nuclear fuel of nuclear power plants. Patent RU No 2 454 741, Bul. 18; 2012.
   Google Scholar
• Sinegribova, O.A.; Tuvin, J. Interphase zirconium distribution at direct and reversed mass transfer in the system Zr -HNO3 - TBP - diluent. Khimicheskaya Tekhnologiya (Chem. Eng.) 2007, 8(3), 129–133.
   Google Scholar
• Gavrilov, P.M.; Kudryavtsev, E.G.; Revenko, Yu.A.; Bondin, V.V.; Fedorov, Yu.S.; Khaperskaya, A.V.; Anisimov O.P.; Zilberman, B.Ya. Complete Testing of SNF Reprocessing Technology for EDC in the Hot Cells of FSUE MCC. GLOBAL 2011. Makuhari Messe, Japan. 2011, Dec. 11–16. Paper 390993.
   Google Scholar
• Fedorov, Yu.S.; Zilberman, B.Ya.; Goletskiy, N.D.; Puzikov, E.A.; Ryabkov, D.V.; Rodionov, S.A.; Beznosyuk, V.I.; Petrov, Yu.Yu.; Saprykin, V.F.; Murzin, A.A.; Bibichev, B.A.; Aloy, A.S.; Kudinov, A.S.; Blazheva, I.V.; Kurenkov, N.V. Peculiarities of highly burned-up NPP SNF reprocessing and new approach to simulation of solvent extraction processes. GLOBAL 2013. Salt Lake City, UT, 2013, September 29 –October 3. pp 69–78.
   Google Scholar
• Shuvalov, O.N.; Pushlenkov, M.F. The method for calculation of component distribution during counter-current extraction. Radiokhimiya (Rus.), 1961, 4(6), 667–673.
   Google Scholar
• Law, J.D.; Rutledge, V.; Pereira, C.; Copple, J.M.; Frey, K.; Krebs, J.F.; Maggos, L.; Nichols, K.; Wardle, K.; Sadasivan, P.; de Almeida, V.F.; DePaoli, D.W. Requirements for a Dynamic Solvent Extraction Module to Support Development of Advanced Technologies for the Recycle of Used Nuclear Fuel. INL/EXT-11-22473, Idaho National Laboratory, 2011; 29 pp.
   Google Scholar
• Dzekun, E.G.; Mel’nikov, V.D.; Zilberman, B.Ya.; Fedorov, Yu.S.; Mashkin, A.N.; Kukharev, D.N.; Starikov, V.M.; Potapov, V.P. Investigation on conditions of plutomnium accumulation in the head extraction unit during NPP SNF reprocessing (Rus). Radiation Safety (Rus), 2000, 1, 3–10.
   Google Scholar
• Fedorov, Yu.S.; Zilberman, B.Ya.; Puzikov, E.A.; Mishin, E.N. Above-extreme extraction mode in the Purex Process: 1. Calculation of the Pu and U distribution in the head extractor. Radiochemistry 2001, 43(6), 562–568.
   Google Scholar
• Zilberman, B.Ya.; Fedorov, Yu.S.; Kukharev, D.N.; Dzekun, E.G.; Mel’nikov, V.D.; Mashkin, A.N.; Starikov, V.M. Above-Extreme Extraction Mode in the Purex Process: 2. Experiments on Pu and U distribution in the above-extreme operation mode of the head extractor. Radiochemistry 2001, 43(6), 569–574.
   Google Scholar
• Garraway, J.; Wilson, P.D. The technetium-catalised oxidation of hydrazine by nitric acid. J. Less-Common Metals. 1984, 97, 191–203.
   Google Scholar
• Zilberman, B.Ya.; Mashkin, A.N. The influence of extraction on catalytic oxidation of hydrazine by nitric acid in the presence of actinides (Rus) Radiokhimiya (Rus) 1992, 34(4), 34–41.
   Google Scholar
• Colón, C.F.J.; Moffat, H.K.; Rao, R.R. Modeling of liquid-liquid extraction (LLE) equilibria using gibbs energy minimization (GEM) for the System TBP–HNO3–UO2–H2O–diluent. Solv. Extr.Ion Exch. 2013, 31(6), 634–651.
   Web of Science ®Google Scholar