1 / 16

Production of 100Mo/99mTc and 64Cu Medical Radioisotopes Using 14 MeV Fusion Neutrons

This presentation discusses the production of 100Mo/99mTc and 64Cu medical radioisotopes using 14 MeV fusion neutrons. It covers the production and usage of 99mTc radiopharmaceuticals, alternative solutions to reactor-based techniques, and tests conducted at ENEA. The production of 64Cu as a theranostic radionuclide is also explored. Conclusions and perspectives for the future are provided.

dotson
Download Presentation

Production of 100Mo/99mTc and 64Cu Medical Radioisotopes Using 14 MeV Fusion Neutrons

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript


  1. 100Mo/99mTc and 64Cu medical radioisotopes production using 14 MeV fusion neutrons Antonino Pietropaolo – ENEA, Dept. Fusion and Technologies for NuclearSafety and Security International Collaboration on Advanced NeutronSources (ICANS-XXIII) 13th - 18th October 2019, Chattanooga-Tennessee (US)

  2. On behalf of M. Angelone (ENEA) A. Boschi (Univ. Ferrara) M. Capogni (ENEA) M. Capone (ENEA) N. Cherubini (ENEA) P. De Felice (ENEA) G. DellePiane(ENEA) A. Dodaro(ENEA) A. Duatti (Univ. Ferrara) R. Falconi (ENEA) A. Fazio (ENEA) S. Fiore (ENEA) S. Loreti(ENEA) P. Martini (Univ. Ferrara) G. Pagano (ENEA) M. Pillon(ENEA) A. Pizzuto (ENEA) L. Quintieri (ENEA now STFC) 100Mo/64Cu production with 14 MeV neutrons

  3. Outline • 99Mo/99mTc • How 99mTc radiopharmaceutical is produced and used • 99mTc production via 100Mo(n,2n)99Mo inelastic reactions • Tests in ENEA • 64Cu • The 64Cu theranostic radionuclide • Tests in ENEA • Conclusions and perspectives 100Mo/64Cu production with 14 MeV neutrons

  4. How 99mTc radiopharmaceutical is produced and used 99mTc well suited for medical imaging Short half-life: T1/2 ~ 6 h Optimal g-ray emission:Eg = 140 keV Used in Single PhotonEmissionComputedTomography- SPECT 100Mo/64Cu production with 14 MeV neutrons

  5. How 99mTc radiopharmaceutical is produced and used Direct fission to 99Mo is not very likely Individual Fission Yield = 1.8E-3% Cumulative Fission Yield = 6% 99Mo is thus produced by the main reaction paths: 235U + n 236U  99Zr + 134Te + 3n and235U + n 236U 99Y + 134I + 3n  99Zr and 99Y then decay by b emission to 99Mo. 6-day Ci EoP activity of 99Mo available 6 dayafter99Mo End of Process 100Mo/64Cu production with 14 MeV neutrons

  6. How 99mTc radiopharmaceutical is produced and used 100Mo/64Cu production with 14 MeV neutrons

  7. The global crisis of 2009: search of solutions 100Mo/64Cu production with 14 MeV neutrons

  8. 99mTc production via 100Mo(n,2n)99Mo inelastic reactions Three general methods of 99mTc production (direct or by means of 99Mo precursor) have been identified as short, mid and long term alternative solutions to the reactor based technique: Thermal neutrons 98Mo(n,)99Mo Fast Neutrons 100Mo(n,2n)99Mo Gamma-ray beam 100Mo (g,n)99Mo Accelerated charged-particle beams 96Zr(a,n)99Mo or 100Mo(p,2n)99mTc 100Mo/64Cu production with 14 MeV neutrons

  9. Tests in ENEA • Irradiation of a metallic natural molybdenum powder with 14 MeV neutrons generated in deuteron-tritium (D-T) fusion reaction at the Frascati Neutron Generator • In preparation of the experiment, we performed Monte Carlo (MC) simulations using the Flukacode • These models were benchmarked with experimental data 100Mo/64Cu production with 14 MeV neutrons

  10. Tests in ENEA FNG is a linear electrostaticaccelerator-drivenneutron source Acceleratedparticles: Deuterons (D+) Energy: ED= 300 keV Current: ID= 1 mA Target: Titaniumlayer (3 mm thickness) loaded with tritium/deuterium H.V. TERMINAL ION SOURCE ION SOURCE CHAMBER –EINZEL LENS BENDING MAGNET QUADRUPOLES VACUUM PUMP ACCELERATOR TUBE TARGET 100Mo/64Cu production with 14 MeV neutrons

  11. Tests in ENEA 100Mo/64Cu production with 14 MeV neutrons

  12. Tests in ENEA 100Mo/64Cu production with 14 MeV neutrons

  13. Purification/Elution system University of Ferrara Post-Irradiation PHS Post-Elution PHS Experimental99Mo activity @ FNG (2.3±0.04) kBq g-1 Irradiation time=900 s FNG Y~2.9×1010 n s-1 MC Calculations 2.5 kBq g-1 All the measured activities are assessed by ensuring full traceability to the National Activity Standards maintained at the Italian National Institute of Ionizing Radiation Metrology (ENEA-INMRI). 99Mo Radionuclidic/radiochemical purity assessed 100Mo/64Cu production with 14 MeV neutrons

  14. The 64Cu theranostic 64Zn(n,p)64Cu using 14 MeV neutrons Main production route: 64Ni(p,n)64Cu (in cyclotrons) 64Ni extremely expensive 1 hour irradiation time AS = (13.2 ± 0.4) kBq/g s ~ 0.18 b @ 14 MeV 100Mo/64Cu production with 14 MeV neutrons

  15. The 64Cu theranostic 65Cu(n,2n)64Cu using 14 MeV neutrons 1 hour irradiation time Measurements on eluted 64Cu both in the case of 64Zn and 65Cu were done using g-ray spectrometer (HpGe and Double NaI and with a Liquid Scintillation Counter using the TDCR technique. MCNP simulations have been also performed to enable FISPACT calculations that provide, once known the neutron fluence at the irradiated sample, the produced radionuclide and their activity at different cooling times. Good agreement between measuerments and calculations as in the case of the Moly test. AS=(45.0±0.1) kBq/g s ~ 0.75 b @ 14 MeV 100Mo/64Cu production with 14 MeV neutrons

  16. Coclusions and perspectives 99Mo/99mTc (the diagnostic) More than proof of concept as we extracted a potential radiopharmaceutical (the Pertechnetate with radiochemical and radionuclidic purity fulfilling the Pharmacopoeia requirements A high-brilliance 14 MeV neutron source is needed to produce 99Mo activity suitable to supply hospitals at least at regional level (order of 1013 s-1 neutron emission rate) In ENEA we are working on that (regional funds close to be delivered to ENEA) 64Cu (the theranostic) Proof of concept on two different routes: 64Zn(n,p)64Cu and 65Cu(n,2n)64Cu 64Zn(n,p)64Cu: lower cross section but at the end there is the need to separate two different chemical species (Zn and Cu) 65Cu(n,2n)64Cu: higher cross section but no simple/fast/economic way to separate 64Cu rom 65Cu. One may retain 65Cu in the solution if a high concentration of 64Cu might be achieved. Also in this case a high-brilliance 14 MeV neutron source is needed. 100Mo/64Cu production with 14 MeV neutrons

More Related