14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives.
Molecules
; 23(8)2018 Jul 27.
Article
en En
| MEDLINE
| ID: mdl-30060449
ABSTRACT
BACKGROUND:
the gamma-emitting radionuclide Technetium-99m (99mTc) is still the workhorse of Single Photon Emission Computed Tomography (SPECT) as it is used worldwide for the diagnosis of a variety of phatological conditions. 99mTc is obtained from 99Mo/99mTc generators as pertechnetate ion, which is the ubiquitous starting material for the preparation of 99mTc radiopharmaceuticals. 99Mo in such generators is currently produced in nuclear fission reactors as a by-product of 235U fission. Here we investigated an alternative route for the production of 99Mo by irradiating a natural metallic molybdenum powder using a 14-MeV accelerator-driven neutron source.METHODS:
after irradiation, an efficient isolation and purification of the final 99mTc-pertechnetate was carried out by means of solvent extraction. Monte Carlo simulations allowed reliable predictions of 99Mo production rates for a newly designed 14-MeV neutron source (New Sorgentina Fusion Source).RESULTS:
in traceable metrological conditions, a level of radionuclidic purity consistent with accepted pharmaceutical quality standards, was achieved.CONCLUSIONS:
we showed that this source, featuring a nominal neutron emission rate of about 1015 s-1, may potentially supply an appreciable fraction of the current 99Mo global demand. This study highlights that a robust and viable solution, alternative to nuclear fission reactors, can be accomplished to secure the long-term supply of 99Mo.Palabras clave
Texto completo:
1
Colección:
01-internacional
Base de datos:
MEDLINE
Asunto principal:
Radioisótopos
/
Tecnecio
/
Molibdeno
Tipo de estudio:
Guideline
Idioma:
En
Revista:
Molecules
Asunto de la revista:
BIOLOGIA
Año:
2018
Tipo del documento:
Article
País de afiliación:
Italia