Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Simulation and determination of the appropriate radiotracer to study the behavior of cerium element in radiochemical processes

Document Type : Research Paper

Authors

A. Bahrami Samani 1
B. Taheri 2
I. Dehghan 2
S. Shirvani Arani 1

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

2 Department of Engineering, University of Kashan, Postal Code: 8731753153, Kashan - Iran

https://doi.org/10.24200/nst.2024.1615
Abstract
Liquid wastes containing fission fragments are valuable sources of useful radioisotopes that can be extracted using suitable radiochemical methods. This article addresses the challenge of unavailable waste by simulating a solution equivalent to the liquid waste from a 99Mo production facility using the MCNPX code and preparing it with laboratory-available salts. Various radiotracers of elements were subsequently produced via the neutron activation method and added to the equivalent solution. Investigations focused on tracing cerium in the process, utilizing the 145.4 keV gamma radiation from 141Ce produced during activation. The irradiation mechanism and spectroscopy were simulated using the MCNPX code, and the results were compared with experimental measurements.

Highlights

  1. Papagiannopoulou D. Technetium-99m radiochemistry for pharmaceutical applications. Journal of Labelled Compounds and Radiopharmaceuticals. 2017;60(11):502-520. doi: https://doi.org/10.1002/jlcr.3531.

 

  1. Nawar M.F, Türler A. New strategies for a sustainable 99mTc supply to meet increasing medical demands: Promising solutions for current problems. Frontiers in Chemistry. 2022;10.

 

  1. Tabasi M, Samani B, Shirvani Arani S, Ghannadi Maragheh M, Mohammadi A. Assessment of Mo-99 radioisotope supply chain using LEU in Iran. Journal of Nuclear Science and Technology (JonSat). 2021;42(3):104-110.

 

  1. Cozzi A, Johnson F. Waste Management Strategies for Production of Mo-99. Savannah River Site (SRS). Aiken, SC (United States). 2017.

 

  1. Management of radioactive waste from 99Mo production by nuclear fission, IAEA-TECDOC-1051, W. T. Section, International Atomic Energy Agency. 2013.

 

  1. Hosseini S.E, Ghannadi-Maragheh M, Bahrami-Samani A, Shirvani-Arani S. Evaluation of promethium-147 production as a by-product of the fission molybdenum-99 process in Tehran research reactor. Radiochimica Acta. 2021;109(4):295-300. doi: doi:10.1515/ract-2020-0081.

 

  1. Nuclear Energy Agency. JANIS 4.1. https://www.oecd-nea.org/jcms/pl_39910/janis accessed.

 

  1. Yang L, Sundaresan G, Sun M, Jose P, Hoffman D, McDonagh P.R, Lamichhane N, Cutler C.S, Perezc B.J.M, Zweit J. Intrinsically radiolabeled multifunctional cerium oxide nanoparticles for in vivo studies. Journal of Materials Chemistry B. 2013;1(10):1421-1431. doi: 10.1039/C2TB00404F.

 

  1. Vimalnath K.V, Rajeswari A, Sarma H.D, Dash A, Chakraborty S. Ce-141-labeled DOTMP: A theranostic option in management of pain due to skeletal metastases. Journal of Labelled Compounds and Radiopharmaceuticals. 2019;62(4):178-189. doi: https://doi.org/10.1002/jlcr.3710.

 

  1. Soltani F, Samani A.B, Sadeghi M, Arani S.S, Yavari K. Production of cerium-141 using ceria and nanoceria powder: a potential radioisotope for simultaneous therapeutic and diagnostic applications. Journal of Radioanalytical and Nuclear Chemistry. 2015;303(1):385-391, 2015/01/01. doi: 10.1007/ s10967-014-3335-3.

 

  1. Ayodele O.L, Sanusi K.O, Kahn M.T. Nuclear battery: a source of environmentally friendly energy. Journal of Engineering, Design and Technology. 2018.

 

  1. Fenske E.K, Roach B.D, Hexel C.R, Glasgow D.C, Stewart I.R, Partridge J.D, Giaquinto J.M. Inline gamma-spectrometry of fission product elements after rapid high-pressure ion chromatographic separation. Journal of Radioanalytical and Nuclear Chemistry. 2020;324(2):759-771. 2020/05/01. doi: 10.1007/s10967-020-07103-x.

 

  1. Lindstrom R.M, Fleming R.F. Dead time, pileup, and accurate gamma-ray spectrometry. 1995.

 

  1. Ramebäck H, Lagerkvist P, Holmgren S, Jonsson S, Sandström B, Tovedal A, Vesterlund A, Vidmar T, Kastlander J. On the accuracy of gamma spectrometric isotope ratio measurements of uranium. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2016;815:57-61.

 

  1. Morley S.M, Seiner B, Finn E, Greenwood L, Smith S.C, Gregory S, Haney M, Lucas D, Arrigo L, Beacham T, Swearingen K, Friese J, Douglas M, Metz L. Integrated separation scheme for measuring a suite of fission and activation products from a fresh mixed fission and activation product sample. Journal of Radioanalytical and Nuclear Chemistry. 2015;304(2):509-515. 2015/05/01. doi: 10.1007/ s10967-014-3826-2.

 

  1. Morrison S.S, Clark S.B, Eggemeyer T.A, Finn E.C, Hines C.C, King M.D, Metz L.A, Morley S.M, Snow M.S, Wall D.E, Seiner B.N. Activation product analysis in a mixed sample containing both fission and neutron activation products. Journal of Radioanalytical and Nuclear Chemistry. 2017;314(3):2501-2506. 2017/12/01. doi: 10.1007/ s10967-017-5563-9.

 

  1. Abedi E, Ebrahimkhani M, Davari A, Mirvakili S.M, Tabasi M, Ghannadi Maragheh M. Neutronic and thermal-hydraulic analysis of fission molybdenum-99 production at Tehran Research Reactor using LEU plate targets. Applied Radiation and Isotopes. 2016;118:160-166.

Keywords

Radiotracer
Neutron activation
141Ce
HPGe
MCNPX
  1. Papagiannopoulou D. Technetium-99m radiochemistry for pharmaceutical applications. Journal of Labelled Compounds and Radiopharmaceuticals. 2017;60(11):502-520. doi: https://doi.org/10.1002/jlcr.3531.

 

  1. Nawar M.F, Türler A. New strategies for a sustainable 99mTc supply to meet increasing medical demands: Promising solutions for current problems. Frontiers in Chemistry. 2022;10.

 

  1. Tabasi M, Samani B, Shirvani Arani S, Ghannadi Maragheh M, Mohammadi A. Assessment of Mo-99 radioisotope supply chain using LEU in Iran. Journal of Nuclear Science and Technology (JonSat). 2021;42(3):104-110.

 

  1. Cozzi A, Johnson F. Waste Management Strategies for Production of Mo-99. Savannah River Site (SRS). Aiken, SC (United States). 2017.

 

  1. Management of radioactive waste from 99Mo production by nuclear fission, IAEA-TECDOC-1051, W. T. Section, International Atomic Energy Agency. 2013.

 

  1. Hosseini S.E, Ghannadi-Maragheh M, Bahrami-Samani A, Shirvani-Arani S. Evaluation of promethium-147 production as a by-product of the fission molybdenum-99 process in Tehran research reactor. Radiochimica Acta. 2021;109(4):295-300. doi: doi:10.1515/ract-2020-0081.

 

  1. Nuclear Energy Agency. JANIS 4.1. https://www.oecd-nea.org/jcms/pl_39910/janis accessed.

 

  1. Yang L, Sundaresan G, Sun M, Jose P, Hoffman D, McDonagh P.R, Lamichhane N, Cutler C.S, Perezc B.J.M, Zweit J. Intrinsically radiolabeled multifunctional cerium oxide nanoparticles for in vivo studies. Journal of Materials Chemistry B. 2013;1(10):1421-1431. doi: 10.1039/C2TB00404F.

 

  1. Vimalnath K.V, Rajeswari A, Sarma H.D, Dash A, Chakraborty S. Ce-141-labeled DOTMP: A theranostic option in management of pain due to skeletal metastases. Journal of Labelled Compounds and Radiopharmaceuticals. 2019;62(4):178-189. doi: https://doi.org/10.1002/jlcr.3710.

 

  1. Soltani F, Samani A.B, Sadeghi M, Arani S.S, Yavari K. Production of cerium-141 using ceria and nanoceria powder: a potential radioisotope for simultaneous therapeutic and diagnostic applications. Journal of Radioanalytical and Nuclear Chemistry. 2015;303(1):385-391, 2015/01/01. doi: 10.1007/ s10967-014-3335-3.

 

  1. Ayodele O.L, Sanusi K.O, Kahn M.T. Nuclear battery: a source of environmentally friendly energy. Journal of Engineering, Design and Technology. 2018.

 

  1. Fenske E.K, Roach B.D, Hexel C.R, Glasgow D.C, Stewart I.R, Partridge J.D, Giaquinto J.M. Inline gamma-spectrometry of fission product elements after rapid high-pressure ion chromatographic separation. Journal of Radioanalytical and Nuclear Chemistry. 2020;324(2):759-771. 2020/05/01. doi: 10.1007/s10967-020-07103-x.

 

  1. Lindstrom R.M, Fleming R.F. Dead time, pileup, and accurate gamma-ray spectrometry. 1995.

 

  1. Ramebäck H, Lagerkvist P, Holmgren S, Jonsson S, Sandström B, Tovedal A, Vesterlund A, Vidmar T, Kastlander J. On the accuracy of gamma spectrometric isotope ratio measurements of uranium. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2016;815:57-61.

 

  1. Morley S.M, Seiner B, Finn E, Greenwood L, Smith S.C, Gregory S, Haney M, Lucas D, Arrigo L, Beacham T, Swearingen K, Friese J, Douglas M, Metz L. Integrated separation scheme for measuring a suite of fission and activation products from a fresh mixed fission and activation product sample. Journal of Radioanalytical and Nuclear Chemistry. 2015;304(2):509-515. 2015/05/01. doi: 10.1007/ s10967-014-3826-2.

 

  1. Morrison S.S, Clark S.B, Eggemeyer T.A, Finn E.C, Hines C.C, King M.D, Metz L.A, Morley S.M, Snow M.S, Wall D.E, Seiner B.N. Activation product analysis in a mixed sample containing both fission and neutron activation products. Journal of Radioanalytical and Nuclear Chemistry. 2017;314(3):2501-2506. 2017/12/01. doi: 10.1007/ s10967-017-5563-9.

 

  1. Abedi E, Ebrahimkhani M, Davari A, Mirvakili S.M, Tabasi M, Ghannadi Maragheh M. Neutronic and thermal-hydraulic analysis of fission molybdenum-99 production at Tehran Research Reactor using LEU plate targets. Applied Radiation and Isotopes. 2016;118:160-166.

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