In cooperation with the Iranian Nuclear Society

Document Type : Research Paper

Author

Nuclear Fuel Cycle Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box: 11365-8486, Tehran - Iran

Abstract

In this study, an effective and efficient separation method for separating praseodymium from cerium was designed, optimized, and successfully implemented. In this method, a special adsorbent for lanthanides (Ln-resin with dimensions of 100 to 150 microns) was used. A peristaltic pump and column with different dimensions (15 to 45 cm) were used to design the desired method. Systematic studies were performed to determine the eluent concentration of nitric acid (from 0.1 to 1 M). The oxidizing properties of cerium were exploited to differentiate the chemical behavior of these two lanthanides. NaBrO3 was used as an oxidizer. Because in the continuation of this research, the target material of enriched cerium will be used, it is necessary to recover cerium as well. Ascorbic acid was used for the reduction of cerium. After changing the oxidation number of cerium, by changing the concentration of nitric acid, it is easily possible to wash the praseodymium and cerium separately and in high resolution using the commonly available acids and low column pressures with an efficiency of over 99%. This method was successfully used to separate praseodymium-143 from irradiated cerium in the reactor, and also to separate 143Pr from the fission-produced lanthanides, the results of which will be presented in another report.

Highlights

  1. S. Shirvani Arani, M. Ghannadi Maragheh, Translation of Chemistry and Analysis of Radionuclides, Laboratory Methods and Teaching Methods, Published by the Research Institute of Nuclear Sciences and Technologies, Iran, (2013) (In Persian).

 

  1. Sharad Lohar, et al, A kit based methodology for convenient formulation of 166Ho-Chitosan complex for treatment of liver cancer, Applied Radiation and Isotopes, 161, 109161 (2020).

 

  1. Agathe Deville, et al, Peptide Receptor Radionuclide Therapy by177Lu-DOTATATE a Secreting Cervical Paraganglioma, Jeremie Tordo Clin Nucl Med, 47, 71 (1 Jan 2022).

 

  1. Clemens Kratochwil, et al, [153Sm]Samarium-labeled FAPI-46 radioligand therapy in a patient with lung metastases of a sarcoma, Eur J Nucl Med Mol Imaging, 48, 3011 (2021).

 

  1. D.F. Peppard, G. Mason, S.W. Moline, The use of dioctyl phosphoric acid extraction in the isolation of carrier-free 90Y, 140La, 144Ce, 143Pr, and 144Pr, Chemistry Journal of Inorganic and Nuclear Chemistry, 5, 141 (1957).

 

  1. Tomitaro Ishimori, Yoshii Kobayashi, Praseodymium-143 from Neutron-Irradiated Uranium, Journal of Nuclears Ciencea nd Technology2, 2, 181 (1965).

 

  1. K.V. Vimalnath, et al, Prospects and problems in the production of 143Pr for radionuclide therapy applications, Radiochim. Acta, 93, 419-426 (2005).

 

  1. K.V. Vimalnath, et al, Production Logistics and Prospects of 142Pr and 143Pr for Radionuclide Therapy (RNT) Applications, 5th International Conference on Isotopes, F425R0149, 103-108.

 

  1. S.E. Hosseini, M. Ghannadi-Maragheh, A. Bahrami-Samani, S. Shirvani-Arani, Evaluation of promethium-147 production as a by-product of the fission molybdenum-99 process in Tehran research reactor, Radiochimica Acta, 109(4), 295-300 (2021).

 

  1. S. Vosoughi, et al, Production of no-carrier-added Ho-166 for targeted therapy purposes, Iranian Journal of Nuclear Medicine, 25, 15-20 (2017).

 

  1. N. Salek, et al, Comparative studies of extraction chromatography and electroamalgamation separation to produce no-carrier added 177Lu by Tehran research reactor, Iranian Journal of Nuclear Medicine, 25(1), 23-33 (2017).

Keywords

  1. S. Shirvani Arani, M. Ghannadi Maragheh, Translation of Chemistry and Analysis of Radionuclides, Laboratory Methods and Teaching Methods, Published by the Research Institute of Nuclear Sciences and Technologies, Iran, (2013) (In Persian).

 

  1. Sharad Lohar, et al, A kit based methodology for convenient formulation of 166Ho-Chitosan complex for treatment of liver cancer, Applied Radiation and Isotopes, 161, 109161 (2020).

 

  1. Agathe Deville, et al, Peptide Receptor Radionuclide Therapy by177Lu-DOTATATE a Secreting Cervical Paraganglioma, Jeremie Tordo Clin Nucl Med, 47, 71 (1 Jan 2022).

 

  1. Clemens Kratochwil, et al, [153Sm]Samarium-labeled FAPI-46 radioligand therapy in a patient with lung metastases of a sarcoma, Eur J Nucl Med Mol Imaging, 48, 3011 (2021).

 

  1. D.F. Peppard, G. Mason, S.W. Moline, The use of dioctyl phosphoric acid extraction in the isolation of carrier-free 90Y, 140La, 144Ce, 143Pr, and 144Pr, Chemistry Journal of Inorganic and Nuclear Chemistry, 5, 141 (1957).

 

  1. Tomitaro Ishimori, Yoshii Kobayashi, Praseodymium-143 from Neutron-Irradiated Uranium, Journal of Nuclears Ciencea nd Technology2, 2, 181 (1965).

 

  1. K.V. Vimalnath, et al, Prospects and problems in the production of 143Pr for radionuclide therapy applications, Radiochim. Acta, 93, 419-426 (2005).

 

  1. K.V. Vimalnath, et al, Production Logistics and Prospects of 142Pr and 143Pr for Radionuclide Therapy (RNT) Applications, 5th International Conference on Isotopes, F425R0149, 103-108.

 

  1. S.E. Hosseini, M. Ghannadi-Maragheh, A. Bahrami-Samani, S. Shirvani-Arani, Evaluation of promethium-147 production as a by-product of the fission molybdenum-99 process in Tehran research reactor, Radiochimica Acta, 109(4), 295-300 (2021).

 

  1. S. Vosoughi, et al, Production of no-carrier-added Ho-166 for targeted therapy purposes, Iranian Journal of Nuclear Medicine, 25, 15-20 (2017).

 

  1. N. Salek, et al, Comparative studies of extraction chromatography and electroamalgamation separation to produce no-carrier added 177Lu by Tehran research reactor, Iranian Journal of Nuclear Medicine, 25(1), 23-33 (2017).