A SIMULATION OF IRRADIATION CALCULATIONS ON LUTETIUM-177 PRODUCTION IN RSG-GAS USING U3SI2-AL AND U9MO-AL FUELS

Lena Rosmayani, Anis Rohanda, Raden Farzand Abdullatif

DOI: http://dx.doi.org/10.55981/tdm.2023.6793

Abstract


This research is a simulation of irradiation calculations on the production of the radioisotope Lutetium-177 (177Lu) in the G.A Siwabessy Reactor (RSG-GAS). This study aims to analyze the comparative calculation of 177Lu activity and its purity. One of the production methods of 177Lu in RSG-GAS is carried out by irradiating Lu2O3 targets. This Lu2O3 target irradiation produced the radioisotope 177Lu along with 177mLu as an impurity. For Medical treatment using radioisotopes, the minimum activity for 177Lu is 20 GBq/mg, and the impurity should not exceed 0.1%. Calculations were carried out with thermal neutron flux input at 15 MWt operational power for the RSG-GAS core with U3Si2-Al fuel (density 2.96 gU/cc and 3.55 gU/cc) and U9Mo-Al fuel (density 3.55 gU/cc). Calculations were carried out by simulating 8 days of irradiation using ORIGEN2.1. The results showed that the 177Lu activity resulting from irradiation of Lu2O3 targets at various CIP positions in the U9Mo-Al reactor core was larger than that of the U3Si2-Al core. Until the 30th day, the 177Lu product resulting from irradiation on the U3Si2-Al and U9Mo-Al cores still meets the minimum value of 20 GBq/mg for treatment needs in nuclear medicine, with the activity value of 177Lu resulting from irradiation on the U3Si2-Al core ranging from 241-403 GBq/mg, while the activity of irradiated 177Lu in the U9Mo-Al core ranges from 335-561 GBq/mg. In addition, until the 30th day of decay, 177Lu has a percentage value of 177mLu irradiated in the U9Mo-Al and U3Si2-Al cores of 0.0346% and 0.0344%, respectively. The results are still below the maximum impurity value of 0.1% and thus safe to use as a therapeutic agent.

 

Keywords: 177Lu, Activity, RSG-GAS, ORIGEN2, Irradiation


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References


  1. Dash A, Pillai MR, and Knapp FF Jr., “Production of (177)Lu for Targeted Radionuclide Therapy: Available Options”, Nucl Med Mol Imaging, vol.49, no.2, pp.85– 107, 2015, DOI: 10.1007/s13139-014-0315-z
  2. Pillai, Ambikalmajan M R, and Furn F Russ Knapp Jr, “Evolving Important Role of Lutetium-177 for Therapeutic Nuclear Medicine”, Current radiopharmaceuticals vol.8, no.2, pp 78–85, 2015, DOI: 10.2174/1874471008666150312155959
  3. Market Research Reports, “Global Lutetium Market Outlook to 2027”, Blue Quark Research & Consulting, 2022.
  4. Vogel, W.V., van der Marck, S.C. & Versleijen, M.W.J, “Challenges and Future Options for the Production of Lutetium-177. Eur J Nucl Med Mol Imaging 48”, pp 2329–2335, 2021. DOI: https://doi.org/10.1007/s00259-021-05392-2
  5. Awaludin R, “Radioaktivitas Jenis dan Kemurnian Radionuklida Lutesium-177 diproduksi Menggunakan Reaktor G.A. Siwabessy”, Jurnal Radioisotop dan Radiofarmaka vol.18, no.1,2017.
  6. Widyaningrum, Triani, et al. "Karakteristik Pemisahan Radiolutesium-177/177mlu dan Radioiterbium-169/175yb pada Kolom Resin Ln-eichrom", Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) vol.16, no.1, pp. 1-14, 2015.
  7. Banerjee S., Pillai, M.R.A and Russ Knap F.F, “Lutetium-177 Therapeutic Radiopharmaceuticals: Linking Chemistry, Radiochemistry, and Practical Applications”, Chemical reviews vol.115, no.8 pp 2934-2974, 2015, DOI: 10.1021/cr500171e
  8. Maiyesni M, Febriana S, Kambali I, and Kurniasih D, “Spectral Comparison of NeutronIrradiated Natural and Enriched Ytterbium Targets for Lu-177 Production”, Atom Indonesia, vol.45, no.3, pp.133–7, 2019, DOI: 10.17146/aij.2019.930
  9. Kuznetsov R.A., Bobrovskaya K.S., and Svetukhin V.V., "Production of Lutetium-177: Process Aspects", Radiochemistry, vol. 61, pp. 381-395, 2019, DOI: 10.1134/S1066362219040015
  10. Boraas, Matthew, et al, Nuclear Batteries and Radioisotopes. Germany: Springer International Publishing, 2018.
  11. Husnayani, Ihda, “Calculation of Radionuclide Content Of Nuclear Materials Using Origen2.1 Computer Code,” Sigma Epsilon vol.19, no.1, pp.20-25, 2015.
  12. Rohanda, A., Waris, A., Kurniadi, R. et al, “Validation and Improvement of Gamma Heating Calculation Methods for the G.A. Siwabessy Multipurpose Reactor”, NUCL SCI TECH 31, 112 (2020). DOI : https://doi.org/10.1007/s41365-020-00824-4
  13. Surbakti, T., Surian P., Farisy Y., and Imron M., "Analysis of Safety Reactivity Factor on RSGGAS Core using New Fuel" ,In Journal of Physics: Conference Series, vol. 1485, no. 1, p. 012007. IOP Publishing, 2020.


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