Skip to main content
Article
Licensed
Unlicensed Requires Authentication

Design of experiments for the optimization of U(VI) reduction with hydrogen over Pt/SiO2

  • , , EMAIL logo , EMAIL logo and
Published/Copyright: December 19, 2022

Abstract

Significant amount of uranous nitrate is required for reducing Pu(IV) into inextractable Pu(III) for partitioning of U(VI) and Pu(IV) present in the loaded organic phase in PUREX process. Experiments have been conducted for the preparation of uranous nitrate by reducing uranyl nitrate present in nitric acid solution using hydrogen over Pt/SiO2 catalyst. The effect of process variables such as U(VI) concentration, H2 pressure, nitric acid concentration, catalyst quantity, temperature, mixing speed, and hydrazine concentration (for stabilizing U(IV)) on the yield of U(IV) was studied. The process variables were optimized by a two-step statistical approach namely design of experiments. The initial screening of process variables and determination of important variables that affect the production of U(IV) was determined by definitive screening design (DSD) methodology. The DSD yielded three variables affecting the U(VI) reduction to a significant extent were U(VI) concentration, H2 pressure and mixing speed. These significant variables were further optimized using five-level full factorial central composite design (CCD) methodology for understanding the intricate interactions between the variables and the combined effect of all variables at a time influencing the U(VI) reduction. A second-order polynomial equation derived from CCD was subjected to analysis of variance (ANOVA) for estimating the validity of the model and statistical significance of the terms involved in the polynomial. The results revealed that the model can predict the yield of U(IV) generation with 95% confidence in the proposed experimental range.


Corresponding author: Konda Athmaram Venkatesan, Homi Bhabha National Institute, Indira Gandhi Centre for Atomic Research, Kalpakkam, 603 102, Tamil Nadu, India; and Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, 603102, India, E-mail: ; and Nagarajan Sivaraman, Homi Bhabha National Institute, Indira Gandhi Centre for Atomic Research, Kalpakkam, 603 102, Tamil Nadu, India; and Materials Chemistry and Metal Fuel Cycle Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu 603102, India, E-mail:

  1. Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.

  2. Research funding: None declared.

  3. Conflict of interest statement: The authors declare no conflicts of interest regarding this article.

References

1. Ramanujan, A. An introduction to the purex process. IANCAS Bulletin 1998, 14, 11.Search in Google Scholar

2. Pandey, N., Desigan, N., Ramanujam, A. PUREX and THOREX Processes (Aqueous Reprocessing). In Reference Module in Materials Science and Materials Engineering; Elsevier: Oxford, 2016; pp. 1–16.10.1016/B978-0-12-803581-8.02094-4Search in Google Scholar

3. Callerie, G., Detilleux, E., De Beukelaer, R., De Connick, A., Van Caeneghem, J., Valentini, G., Zifferero, M. Reprocessing of fast breeder reactor fuel using aqueous reprocessing technology. In EUR-5010.e; Commission of the European Communities (CEC): Brussels, 1973; pp. 1–50.Search in Google Scholar

4. McKibben, J. M., Chostner, D. F., Orebaugh, E. G. Plutonium Uranium Separation in the PUREX Process Using Mixtures of Hydroxyl Amine Nitrate and Ferrous Sulfamate, DP-1656; Savanna River Laboratory: Aiken, USA, 1983; pp.1–27.10.2172/5521282Search in Google Scholar

5. Govindan, P., Sukumar, S., Subba Rao, R. V. Partitioning of uranium and plutonium by acetohydroxamic acid. Desalination 2008, 232, 166.10.1016/j.desal.2007.12.014Search in Google Scholar

6. Mckibben, J. M., Bercaw, J. E. Hydroxyl Amine Nitrate as a Plutonium Reductant in the Purex Solvent Extraction Process. DP-1248, 1971; pp. 1–20.10.2172/4065655Search in Google Scholar

7. Paviet-Hartmann, P., Riddle, C., Campbell, K., Mausolf, E. Overview of reductants utilized in nuclear fuel reprocessing/recycling. Int. Nucl. Fuel Cycle Conf. Glob. 2013 Nucl. Energy a Crossroads. 2013, 1, 79.Search in Google Scholar

8. Richardson, G. L., Swanson, J. L. Plutonium Partitioning in the PUREX Process with Hydrazine Stabilized Hydroxylamine Nitrate, HEDL-TME-75-31; Westinghouse Hanford Company: USA, 1975.10.2172/4173805Search in Google Scholar

9. Tison, E., Bretault, P. COGEMA experience in uranous nitrate preparation. In WM’06 Conference, Tucson AZ, 2006.Search in Google Scholar

10. Swanson, J. L. Platinum Catalyzed Hydrazine Reduction of plutonium(IV) and Uranium(VI); Battelle Pacific Northwest Laboratories: Washigton, 1971.10.2172/4007561Search in Google Scholar

11. Ghandour, M. A., Abo-Doma, R. A., Gomaa, E. A. The electroreduction (polarographically) of uranyl ion in nitric acid and nitric acid-methanol mixture media. Electrochim. Acta 1982, 27, 159.10.1016/0013-4686(82)80075-3Search in Google Scholar

12. Yuan, Z., Yan, T., Zheng, W., Shuang, H., Xian, L., Bian, X., Zuo, C., Li, C., Cao, Z. Efficient uranous nitrate production using membrane electrolysis. J. Radioanal. Nucl. Chem. 2013, 298, 179.10.1007/s10967-013-2463-5Search in Google Scholar

13. Reshmi, V., Pandey, N. K., Sivasubramanian, R., Ganesh, S., Ahmed, M. K., Kamachi Mudali, U., Natarajan, R. Process modeling of in-situ electrochemical partitioning of uranium and plutonium in purex process: benchmark results with uranium reduction. Desalination Water Treat. 2012, 38, 29.10.5004/dwt.2012.2289Search in Google Scholar

14. Miller, F. C., Hiledbrandt, B. W., Cassidy, R. M. Large Scale Electrolytic Reduction of U(VI) to U(IV); Atomic Energy of canada Limited: Chalk River, Ontario, 1977.Search in Google Scholar

15. Sini, K., Mishra, S., Mallika, C., Pandey, N. K., Lawrence, F., Kamachi Mudali, U., Natarajan, R. Reduction of uranyl nitrate ions in a continuous flow electrochemical reactor. J. Radioanal. Nucl. Chem. 2013, 295, 1505.10.1007/s10967-012-1940-6Search in Google Scholar

16. Nair, M. K. T., Singh, R. K., Bajpai, D. D., Venugopaian, A. K., Singh, R. R., Gurba, P. B., Thomas, M. Role of ion transfer membrane in the production of uranous nitrate; BARC/992/E/002, BARC: Mumbai, 1992.Search in Google Scholar

17. Bell, J. T., Billings, M. R. Photoreduction of the uranyl ion with argon laser light and ethanol-III. The photochemical reduction of dioxouranium(VI) to dioxouranium(V). J. Inorg. Nucl. Chem. 1975, 37, 2529.10.1002/chin.197608027Search in Google Scholar

18. Li, Z. J., Huang, Z. W., Guo, W. L., Wang, L., Zheng, L. R., Chai, Z. F., Shi, W. Q. Enhanced photocatalytic removal of uranium(VI) from aqueous solution by magnetic TiO2/Fe3O4 and its graphene composite. Environ. Sci. Technol. 2017, 51, 5666.10.1021/acs.est.6b05313Search in Google Scholar PubMed

19. Wang, L., Song, H., Yuan, L., Li, Z., Zhang, Y., Gibson, J. K., Zheng, L., Chai, Z., Shi, W. Efficient U(VI) reduction and sequestration by Ti2CTx MXene. Environ. Sci. Technol. 2018, 52, 10748.10.1021/acs.est.8b03711Search in Google Scholar PubMed

20. Sidhu, M. S., Kohli, K. B., Bhatia, P. V. K., Sandhu, S. S. Photochemical reduction of uranyl ion with triethylamine. J. Radioanal. Nucl. Chem. Lett. 1994, 187, 375.10.1007/BF02163602Search in Google Scholar

21. Ananiev, A. V., Tananaev, I. G., Shilov, V. P. Heterogeneous catalytic redox reactions in the chemistry and technology of the nuclear fuel cycle. Russ. Chem. Rev. 2005, 74, 1039.10.1070/RC2005v074n11ABEH001186Search in Google Scholar

22. Deptuła, A., Łada, W., Olczak, T., Chmielewski, A. G. Application of Pt/Al2O3 catalysts produced by sol-gel process to uranyl ion reduction. Nukleonika 2006, 51, 79.Search in Google Scholar

23. Boltoeva, M. Y., Trefilova, A. V., Anan’ev, A. V. Catalytic reduction of U(VI) with hydrazine on palladium catalysts in acid solutions. Radiochem. 2008, 50, 38.10.1134/S1066362208010050Search in Google Scholar

24. Xia, L., Hu, S. S., He, H., Li, B., Xiao, Y., Peng, A., Xiao, J. Research of thermodynamic and kinetics in preparing U(IV) by reducing and catalyzing U(VI) with hydrazine. Radiochim. Acta 2015, 103, 423.10.1515/ract-2014-2314Search in Google Scholar

25. Bin, L. I., Hui, H. E., Bo-Fa, D. I. N. G, Qiu-Yue, Z. H. A. N. G., Xiao-Hong, H. U. A. N. G., Yan-Xin, C. H. E. N., Hong-Bin, T. Platinum catalyzed Reduction of U(VI) with hydrazine in nitric acid solutions. J. Nucl. Radiochem. 2013, 35, 24–28.Search in Google Scholar

26. Anan’ev, A. V., Shilov, V. P., Afonas Eva, T. V., Mikhailova, N. A., Milovanov, A. I. Catalytic reduction of U (VI) with hydrazine and formic acid in HNO3 solutions. Radiochemistry 2001, 43, 39.10.1023/A:1012817921110Search in Google Scholar

27. Sahu, A., Vincent, T., Shah, J. G., Wattal, P. K. Catalytic reduction of U(VI) to U(IV) using hydrogen with platinum loaded on alumina and silica. J. Radioanal. Nucl. Chem. 2014, 300, 163.10.1007/s10967-014-2996-2Search in Google Scholar

28. Ramakrishna Reddy, S., Pandey, N. K., Mondal, S., Sivaraman, N. Catalytic reduction of U(VI) with hydrazine using Pt/SiO2 catalyst in nitric acid medium—kinetics and equilibrium. J. Radioanal. Nucl. Chem. 2020, 325, 425.10.1007/s10967-020-07265-8Search in Google Scholar

29. Pandey, N. K., Reddy, R., Mishra, S., Murali, R., Joshi, J. B. Study on the kinetics of catalytic hydrogenation of U (VI) in nitric acid solution using a bubble reactor. Ind. Eng. Chem. Res. 2018, 57, 3482–3488.10.1021/acs.iecr.7b04293Search in Google Scholar

30. Montgomery, D. Design and Analysis of Experiments, 5th ed.; John Wiley & Sons: New york, 2001.Search in Google Scholar

31. Davies, W., Gray, W., McLeod, K. C. Coulometric determination of uranium with a platinum working electrode. Talanta 1970, 17, 937.10.1016/0039-9140(70)80136-9Search in Google Scholar PubMed

32. Chitnis, R. T., Kulkarni, R. T., Rege, S. G., Mukherjee, A. Volumetric method for the determination of uranium in the active process solutions. J. Radioanal. Chem. 1978, 45, 331.10.1007/BF02519600Search in Google Scholar

33. Ganesh, S., Khan, F., Ahmed, M. K., Pandey, S. Sequential determination of uranium (IV), free acidity and hydrazine in a single aliquot. J. Radioanal. Nucl. Chem. 2010, 286, 33.10.1007/s10967-010-0663-9Search in Google Scholar

34. Srinivasan, T. G., Vasudeva Rao, P. R. Free acidity measurement - a review. Talanta 2014, 118, 162.10.1016/j.talanta.2013.10.017Search in Google Scholar PubMed

35. Paiva, A. P., Malik, P. Recent advances on the chemistry of solvent extraction applied to the reprocessing of spent nuclear fuels and radioactive wastes. J. Radioanal. Nucl. Chem. 2004, 261, 485.10.1023/B:JRNC.0000034890.23325.b5Search in Google Scholar

36. Dey, P. K. Spent Fuel Reprocessing : An Overview; INCAS: Kalpakkam, 2003.Search in Google Scholar

37. Raymond, H. M., Montgomery, D. C., Anderson-Cook, C. M. Response Surface Methodology- Process and Product Optimization Using Designed Experiments, 4th ed.; John Wiley & Sons: New Jersey, 2016.Search in Google Scholar

38. Cox, D. R., Reid, N. The Theory of the Design of Experiments; Chapman & Hall/CRC: New York, 2000.10.1201/9781420035834Search in Google Scholar

39. Mason, R. L., Gunst, R. F., Hess, J. L. Statistical Design and Analysis of Experiments: With Applications To Engineering and Science, 2nd ed.; John Wiley & Sons: New Jersey, 1990.Search in Google Scholar

40. Khajeh, M., Bohlooli, M., Jahanbin, E., Ghaffari-Moghaddam, M., Moghaddam, Z. S. Box-Behnken design in modeling of solid-phase tea waste extraction for the removal of uranium from water samples. Radiochim. Acta 2015, 103, 379.10.1515/ract-2014-2348Search in Google Scholar

41. Olsen, A. M., Schwerdt, I., Jolley, A., Halverson, N., Richards, B., Mc Donald IV, L. W. A response surface model of morphological changes in UO2 and U3 O8 following high temperature aging. Radiochim. Acta 2019, 107, 449.10.1515/ract-2018-3040Search in Google Scholar

42. Fatemi, F., Arabieh, M., Jahani, S. Application of response surface methodology to optimize uranium biological leaching at high pulp density. Radiochim. Acta 2016, 104, 239.10.1515/ract-2015-2495Search in Google Scholar

43. Sood, D. D., Patil, S. K. Chemistry of nuclear fuel reprocessing: current status. J. Radioanal. Nucl. Chem. 1996, 203, 547.10.1007/BF02041529Search in Google Scholar

44. Jones, B., Nachtsheim, C. J. Definitive screening designs with added two-level categorical factors. J. Qual. Technol. 2013, 45, 121.10.1080/00224065.2013.11917921Search in Google Scholar

45. Jones, B., Nachtsheim, C. J. A class of three-level designs for definitive screening in the presence of second-order effects. J. Qual. Technol. 2011, 43, 1.10.1080/00224065.2011.11917841Search in Google Scholar

46. Yang, X., Gao, Y., Jiang, M., He, D., Liao, S., Hou, D., Yan, X., Long, W., Wu, Y., Tan, N. Preparation, characterization, uranium (VI) biosorption models, and conditions optimization by response surface methodology (RSM) for amidoxime-functionalized marine fungus materials. Radiochim. Acta 2017, 105, 449.10.1515/ract-2016-2678Search in Google Scholar


Supplementary Material

The online version of this article offers supplementary material (https://doi.org/10.1515/ract-2022-0049)


Received: 2022-05-21
Accepted: 2022-12-02
Published Online: 2022-12-19
Published in Print: 2023-03-28

© 2022 Walter de Gruyter GmbH, Berlin/Boston

Downloaded on 17.4.2026 from https://www.degruyterbrill.com/document/doi/10.1515/ract-2022-0049/html
Scroll to top button