Abstract Biomedical waste management is an integral part of health care as being the mainstay of hospital cleanliness, hygiene, and maintenance activities. Medical care is crucial for human health but mismanagement of biomedical waste harms the flora and fauna of ecosystem on earth, and badly influences the human health. Due to their stability, biomedical wastes are not eliminated by the solid or sewage treatment plants, and get bioaccumulated in environment, and eventually get to population through various means. They are harmful due to their potential carcinogenicity, genotoxicity, mutagenicity, and other toxicities. Current disposal techniques employed in disposing biomedical wastes are sewage/drains, incineration, and landfills. These practices are normally costly and might transform pollutants from one toxic form to another. Whereas bioremediation is an inexpensive method of employing naturally occurring microorganisms or plants to detoxify man-made pollutants to harmless products that make soil fertile as well in the process. Researchers have also evolved genetically engineered microbes to remediate environmental pollutants including radionuclides. Phytoremediation is also a type of sustainable methods, which is reasonable and competent in handling heavy metals and radioactive waste generated from hospitals. In this article, we have summarized rational applications of bioremediation techniques of using effective microorganisms and plants in enhanced removal of several recalcitrant pollutants including biomedical waste. Our review highlights the challenges and future perspectives to bioremediate non-biodegradable and potentially toxic hospital wastes. cleanliness hygiene activities earth stability environment means carcinogenicity genotoxicity mutagenicity toxicities sewagedrains drains sewage/drains incineration landfills another manmade man made process radionuclides methods hospitals article nonbiodegradable non biodegradable

Resumen Introducción : Una de las áreas de la farmacia vinculadas a la radiación ionizante es la Radiofarmacia que se refiere al estudio, preparación, control y dispensación de los radiofármacos a nivel industrial y hospitalaria. Se entiende como radiofármaco a cualquier producto que esté preparado para su uso con la finalidad diagnóstica y terapéutica que contenga uno o más radionucleidos (isótopos radioactivos) que son utilizados en combinación con moléculas o solos para ser administrados por vía oral o parenteral. El Instituto Nacional de Medicina Nuclear (INAMEN) a nivel nacional lidera ese campo desde 1962 al servicio de la población boliviana. Objetivo : Determinar el uso y diagnóstico de los radiofármacos que son utilizados con mayor frecuencia en medicina nuclear en el INAMEN en la gestión 2021. Metodología : Estudio descriptivo y retrospectivo donde se analizaron los reportes de solicitud de preparación y dispensación de radiofármacos en el laboratorio de Radiofarmacia del INAMEN. Estos datos fueron procesados para determinar que radiofármacos son los más demandados para el diagnóstico y terapia medica nuclear en nuestro departamento. Resultados . Se determinó que de las 2100 solicitudes presentadas al laboratorio de Radiofarmacia, el 42% corresponde al metilen difosfonato-99mTc, el 21% corresponde a los isotopos de 99mTc y el 11% corresponde al isotopo 131I. Conclusión . El análisis de los datos concluye que la principal demanda de radiofármacos es para radiotrazadores de tumores y para la yodoterapia.

Abstract Introduction : One of the areas of pharmacy linked to ionizing radiation is Radiopharmacy, which refers to the study, preparation, control and dispensing of radiopharmaceuticals at an industrial and hospital level. A radiopharmaceutical is understood as any product that is prepared for use for diagnostic and therapeutic purposes that contains one or more radionuclides (radioactive isotopes) that are used in combination with molecules or alone to be administered orally or parenterally. The National Institute of Nuclear Medicine (INAMEN) at the national level has led this field since 1962 at the service of the Bolivian population. Objective : Determine the use and diagnosis of the radiopharmaceuticals that are most frequently used in nuclear medicine in the INAMEN in the 2021 administration. Methodology : Descriptive and retrospective study where the reports requesting the preparation and dispensing of radiopharmaceuticals in the INAMEN Radiopharmacy laboratory were analyzed. These data were processed to determine which radiopharmaceuticals are the most in demand for nuclear medical diagnosis and therapy in our department. Results : It was determined that of the 2100 applications submitted to the Radiopharmacy laboratory, 42% correspond to methylene diphosphonate-99mTc, 21% correspond to 99mTc isotopes and 11% correspond to 131I isotopes. Conclution : The analysis of the data concludes that the main demand for radiopharmaceuticals is for tumor radiotracers and iodotherapy.

Resumen En el contexto bélico actual y ante la creciente preocupación de la población a un posible evento nuclear, cobra importancia una revisión bibliográfica como la presente en la que se recogen los actuales y potenciales tratamientos que la Farmacia Hospitalaria debería tener disponible tanto para paliar como para prevenir los posibles daños derivados de la radiación. Así, se detallan los seis medicamentos comercializados y cuatro fórmulas magistrales que deberían formar parte de un stock de emergencia en lugares cercanos amenazados por la exposición a radionúclidos de yodo, cesio, talio, galio, polonio, tecnecio y uranio. Por otra parte, se recogen nuevos compuestos naturales que, por sus propiedades antioxidantes, antiinflamatoria y/o potencial quelante de metales, podrían llegar a utilizarse como radioprotectores en este tipo de eventos, estando la mayoría disponibles como materia prima y siendo por tanto valorable su elaboración como formulación magistral.

Summary In the current war context and given the growing concern of the population in a possible nuclear event, a bibliographic review such as the current one is important, in which the present and potential treatments that the Hospital Pharmacy should have available both to palliate and to prevent possible damage from radiation. This review includes the 6 marketed drugs and 4 compounding drugs that should form part of an emergency stock in nearby places threatened by exposure to radionuclides of iodine, cesium, thallium, gallium, polonium, technetium and uranium. On the other hand, we describe 9 natural compounds that, due to their antioxidant, anti-inflammatory and/or metal-chelating potential properties, could be used as radioprotectors in this type of event, most of them being available as active pharmaceutical ingredients and their elaboration being therefore valuable as compounded drugs.

Abstract Objective: To measure the potential radiation dose emitted by patients who have recently undergone diagnostic nuclear medicine procedures, in order to establish optimal radiation safety measures for such procedures. Materials and Methods: We evaluated the radiation doses emitted by 175 adult patients in whom technetium-99m, iodine-131, and fluorine-18 radionuclides were administered for bone, kidney, heart, brain, and whole-body scans, as measured with a radiation detector. Those values served as the basis for evaluating whole-body radiopharmaceutical clearance, as well as the risk for the exposure of others to radiation, depending on the time elapsed since administration of the radiopharmaceutical. Results: The mean time to clearance of the radiopharmaceuticals administered, expressed as the effective half-life, ranged from 1.18 ± 0.30 h to 11.41 ± 0.02 h, and the mean maximum cumulative radiation dose at 1.0 m from the patients was 149.74 ± 56.72 µSv. Even at a distance of 0.5 m, the cumulative dose was found to be only half and one tenth of the limits established for exposure of the general public and family members/caregivers (1.0 mSv and 5.0 mSv per episode, respectively). Conclusion: Cumulative radiation doses emitted by patients immediately after diagnostic nuclear medicine procedures are considerably lower than the limits established by the International Commission on Radiological Protection and the International Atomic Energy Agency, and precautionary measures to avoid radiation exposure are therefore not required after such procedures. Objective Methods 17 technetium99m, technetium99m technetiumm technetium 99m, 99m technetium-99m iodine131, iodine131 iodine 131, 131 iodine-131 fluorine18 fluorine 18 fluorine-1 bone kidney heart brain wholebody whole body scans detector Results halflife, halflife life, life half-life 118 1 1.1 030 0 30 0.3 1141 11 41 11.4 002 02 0.0 10 1. 14974 149 74 149.7 5672 56 72 56.7 µSv 05 5 0. memberscaregivers members caregivers (1. 50 5. episode respectively. respectively . respectively) Conclusion Agency iodine13 13 iodine-13 fluorine1 fluorine- 03 3 114 4 11. 00 1497 14 7 149. 567 56. (1 iodine1 iodine-1 ( iodine-

Resumo Objetivo: O objetivo deste trabalho foi levantar o potencial de dose de radiação emitida por pacientes em procedimentos diagnósticos, visando a estabelecer cuidados de radioproteção mais otimizados. Materiais e Métodos: Taxas de dose de radiação emitidas por 175 pacientes administrados com os radionuclídeos 99mTc, 131I e 18F para cintilografias óssea, renal, cardíaca, cerebral e corpo inteiro, foram mensuradas com um detector de radiação, servindo para avaliar o clareamento do radiofármaco no organismo e risco de exposição após administração dos radiofármacos. Resultados: O clareamento, representado pela meia-vida efetiva, variou de 1,18 ± 0,30 h até 11,41 ± 0,02 h e a dose de radiação máxima acumulada oferecida pelos pacientes a 1,0 m foi de 149,74 ± 56,72 µSv. Mesmo para distâncias de 0,5 m, as doses estimadas foram, respectivamente, duas e dez vezes inferiores ao nível de restrição para o público geral (1,0 mSv) e exposição médica (5,0 mSv/episódio). Conclusão: Doses de radiação oferecidas por pacientes em procedimentos diagnósticos são inferiores aos níveis de restrição recomendados pela International Commission on Radiological Protection e International Atomic Energy Agency, e assim, cuidados de radioproteção são geralmente desnecessários. Objetivo otimizados Métodos 17 99mTc mTc I F óssea renal cardíaca inteiro radiofármacos Resultados meiavida meia vida efetiva 118 1 18 1,1 030 0 30 0,3 1141 11 41 11,4 002 02 0,0 10 1, 14974 149 74 149,7 5672 56 72 56,7 µSv 05 5 0, respectivamente (1, mSv 5,0 50 (5, mSv/episódio. mSvepisódio mSv/episódio . episódio mSv/episódio) Conclusão Agency assim desnecessários 03 3 114 4 11, 00 1497 14 7 149, 567 56, (1 5, (5 (

Abstract Activities related to the marine exploration of oil and gas reservoirs tend to cause a concentration of natural radionuclides in related materials. As such, knowledge regarding the distribution of radionuclides in sedimentary basins with current oil operations is essential for modeling radiological hazards and possible risks of site contamination. This study investigated the distribution of 226Ra and 228Ra, radioisotopes from the 232U and 232Th decay chains in bottom sediment of the Santos basin. Sediment samples were collected from sites in a sampling grid based on depth contours and were analyzed through high-resolution gamma spectrometry. A distribution model of the spatial variation of these isotopes, the frst of its kind for the Basin, supported the interpretation of similar tendencies in their distribution. From studying the spatial trends of the mean levels of the isotopes with descriptive statistics and variance analysis, latitudinal and bathymetric diferences in the content of radionuclides emerged. These diferences are probably derived from the distinct sources of these elements, as 226Ra originates in the deep ocean from the decay of parent 230Th and from the patterns of sedimentation driven by open ocean circulation, while 228Ra is supplied by terrigenous materials transported by the northward-fowing Brazilian Coastal Current. such contamination Ra U Th basin highresolution high resolution spectrometry Basin analysis emerged elements circulation northwardfowing northward fowing Current

Resumen Los isótopos radiactivos son utilizados en diversos procesos, como en tratamientos médicos nucleares. Después de su uso, dichos isótopos pueden ser descargados en las aguas residuales, ocasionando problemas ambientales y de salud humana. El objetivo de este trabajo fue identificar la presencia de emisiones alfa y beta totales en el río Santa Catarina, Monterrey, Nuevo León, México, como referencia para conocer si existe riesgo para la salud de la población debido a estas descargas de radionúclidos en el agua residual. Se recolectaron muestras puntuales por conveniencia en seis sitios de descarga de agua durante la época de invierno y verano y se trasladaron al Laboratorio ABC para su análisis. Las emisiones alfa y beta variaron conforme a la estación del año, encontrándose concentraciones más altas en verano tanto de alfas como betas de 0.551 Bq/l y 0.842 Bq/l, respectivamente. Ningún valor superó los límites permitidos por la normatividad mexicana para elementos radiactivos, por lo que no representan un riesgo para la salud.

Abstract Radioactive isotopes are used in various processes such as nuclear medical treatments. After their use, these isotopes can be discharged into wastewater, causing environmental and human health problems. The objective of this work was to identify the presence of total alpha and beta emissions in the Santa Catarina River, Monterrey, Nuevo Leon, Mexico, as a reference to know if there is a risk to the health of the population due to these radionuclide discharges in wastewater. Point samples were collected for convenience at six water discharge sites during the winter and summer seasons and taken to the ABC Laboratory for analysis. The alpha and beta emissions varied according to the season of the year, with higher concentrations of both alphas and betas in summer of 0.551 Bq/l and 0.842 Bq/l, respectively. None of the values exceeded the limits allowed by Mexican regulations for radioactive elements and therefore do not represent a health risk.

Abstract The crude oil that reached the Brazilian coast in 2019 was the most significant environmental disaster ever recorded in Brazilian marine waters, with severe ecological and economic repercussions not fully dimensioned and understood. One consequence of this kind of oil spill is the absorbed dose delivered to marine organisms. The biota exposure to radiation can introduce consequences that range from fertility decrease to death of exposed population. Therefore, the current study aims to use the ICRP reference organisms (flatfish, crab, and brown seaweed) to assess marine biota exposure due to uranium and thorium series radiation. The oil spill scenario, as well as the reference biota, were simulated in MCNP. Thorium series stood out for presenting a significant contribution to the dose. Furthermore, it was noticed that a remedial action capable of removing Tl-208 would significantly decrease the effects of radiation on marine biota. Finally, dose conversion coefficients for both uranium and thorium series were obtained as oil activity concentration functions. The results obtained here can be used in an oil spill event along with other worldwide recognized models. In addition, the dose coefficients can be used strategically to assess the maximum exposure time for emergency oil control, removal, and mitigation.

Simultaneous analysis of radionuclides in water had not been performed by mass spectrometry of the magnetic sector. Some international organizations indicate that it is necessary to know the contamination of drinking-water, including radioactive aspects. The novelty of this study was to determine simultaneously radioisotope radium, thorium, uranium and lead stable. Experiments were performed in an accredited laboratory (International Organization for Standardization/International Electrotechnical Commission-7025:2005). The radionuclides of thorium, uranium and some of their descendants were obtained. The reported values are in the range of 7E-7-24.28 µg L-1. Their presence decreases in the order thorium>uranium>radium in drinking water and uranium>thorium>radium in seawater. These results do not represent any risk to the population because very low concentrations were determined.

RESUMEN La contaminación por elementos radioactivos y su transferencia a través de la cadena trófica puede llegar a tener efectos nocivos en los ecosistemas y la salud humana siendo por ello importante su monitoreo continuo. El presente estudio tuvo como objetivo caracterizar la concentración de radionúclidos de origen natural y antropogénico en sedimentos marinos de tres áreas en el noroccidente de la Antártica, monte submarino Orca, bahía Almirantazgo y ensenada Mackellar, con el fin de evaluar posibles niveles de riesgo, fuentes y rutas de transporte. Las mediciones se realizaron usando un espectrómetro Canberra de alta resolución y la precisión y exactitud metodológica fue evaluada mediante el análisis de materiales de referencia certificada del Organismo Internacional de Energía Atómica (OIEA), SOIL-6 y Moss SOIL-447. Los resultados mostraron una baja concentración de actividad del 137Cs en los sedimentos marino, disminuyendo hacia la zona profunda, validando la vía atmosférica como ruta principal de transporte de este radionúclido de origen antrópico. La concentración de actividad de los radionúclidos de origen natural 226Ra y 40K, confirman el origen volcánico de la región, corroborando las etapas de evolución geológica del sector, y los cambios en la fuente de material al manto. Los índices de peligro de radiación calculados mostraron que las concentraciones de actividad actuales de los elementos radioactivos no representan un riesgo para la salud. Resulta importante a futuro mejorar el entendimiento de la relación del hidrotermalismo en la zona con la concentración de actividad de radionúclidos de origen natural.

ABSTRACT Contamination by radioactive elements and their transfer through the trophic chain can have harmful effects on ecosystems and human health, therefore its continuous monitoring is important. The present study aimed to characterize the concentration of radionuclides of natural and anthropogenic origin in marine sediments from three areas in the northwest of Antarctica, Orca Seamount, Admiralty Bay and Mackellar Inlet, in order to evaluate possible risk levels, sources and transportation routes. Measurements were made using a high-resolution Canberra spectrometer and methodological precision and accuracy was assessed by analyzing reference materials certified by the International Atomic Energy Agency (IAEA), SOIL-6 and Moss SOIL-447. The results showed a low concentration of 137Cs activity in the marine sediments, decreasing towards the deep zone, validating the atmospheric pathway as the main transport route for this radionuclide of anthropic origin. The activity concentration of radionuclides of natural origin 226Ra and 40K, confirm the volcanic origin of the region, corroborating the geological evolution stages of the sector, and the changes in the source of material to the mantle. The calculated radiation hazard indexes showed that current activity concentrations of radioactive elements do not pose a health risk. It is important in the future to improve the understanding of the relationship between hydrothermalism in the area and the activity concentration of radionuclides of natural origin.

On May 2019, the members of the Anthropocene Working Group completed a binding vote to affirm some of the key questions that have been agreed in 2016: the Anthropocene should be considered as a formal chronostratigraphic unit, defined by a Global Boundary Stratotype Section and Point (GSSP), using one of the stratigraphic signals around the mid-twentieth century of the Common Era. The fallout from nuclear weapons testing appears as the most suitable GSSP. In this article, the main anthropogenic markers are discussed as well as the sources or human-made radiation and the signature of nuclear weapons testing. The appearance of 239+240Pu in the early 1950s and the clear peak, in 1963, makes a good marker. High resolution archives include layers of sedimentary rocks, lacustrine and marine sediments and corals and polar ice cores. A coupled application of other radioactive isotopes, as 137Cs, 14C and 241Am, may be useful to categorize distinct fallout signatures. A site to define the Anthropocene (golden spike) would ideally be located between 30º and 60º north of the equator. Nevertheless, results obtained in sediments on the Brazilian coast showed that both 239+240Pu and 137Cs signatures could be detected and quantified as markers of this “atomic age”. 2019 2016 unit GSSP, GSSP , (GSSP) midtwentieth mid twentieth Era article humanmade human made 239240Pu Pu 239 240Pu s peak 1963 marker rocks cores isotopes Cs C 241Am Am golden spike º equator Nevertheless atomic age. age . age” 201 (GSSP 23 196 20 2 19 1

Abstract: The Generalized Integral Transform Technique (GITT) was employed to simulate transient one-dimensional flow in variably saturated porous media, as well as radioactive waste transport within different layers (a solid waste pile, nearby soil, and a granular aquifer) towards the edge of a uranium mining installation under institutional control. Computational codes, written using the Mathematica software system, were implemented and tested for solution of the coupled advection-dispersion equations for an arbitrary number of daughter products within a radioactive chain migrating in saturated and unsaturated soil layers. The computer simulations were verified in great detail against results obtained using the built-in routine NDSolve of the Mathematica platform and the HYDRUS-1D software system. The present work reports the main results for 238U chain radionuclide transport using data extracted from a safety assessment of solid waste repositories at a uranium mining and milling installation in Caetité, state of Bahia, Brazil, operated by INB (Indústrias Nucleares do Brasil). Concentration evolutions of the various radionuclides obtained with the simulations were analyzed for five different cases to explore variations in the infiltration and recharge rates, the effect of assuming physical equilibrium or non-equilibrium transport conditions, and of different initial concentrations of some of the radionuclides.

ABSTRACT Various nuclear and related analytical techniques applied to study different environmental problems in Havana city are presented. The environmental analysis by means of Neutron and Gamma Activation analyses, X-ray Fluorescence Atomic Abortion and Induced Coupled Plasma spectroscopies and Low Background , Gamma Spectrometry, have allowed to obtain important information about the behavior of heavy metals, antibiotics and radionuclides in sediments, urban and agricultural soils, waters, beach sands, urban dusts and agricultural products farmed in the Havana city.

RESUMEN Se resumen las diferentes experiencias en la aplicación de las técnicas nucleares y conexas en el estudio de diversos problemas ambientales de la Ciudad de La Habana. El análisis medioambiental mediante las técnicas de Análisis por Activación Neutrónica (AAN) y Gamma (AAG), Fluorescencia de Rayos X (FRX), Espectrometría por Absorción Atómica (EAA) y por Inducción de plasma acoplado (ICP), así como la Espectrometría Gamma de Bajo Fondo (EGBF), han permitido obtener información muy relevante sobre el comportamiento de los metales pesados, antibióticos y radionúclidos en los sedimentos marinos y fluviales, suelos urbanos y agrícolas, aguas, arenas de balnearios, polvos urbanos y productos de la agricultura urbana de la ciudad de La Habana.

Abstract It is recognized worldwide that the security of radioactive substances is very important and that the design of facilities where these sources are used and stored must cater for the implementation of good security measures, including the shielding of some treatment and diagnostic rooms. The radiation protection assessment of a nuclear medicine facility consists of the evaluation of the annual effective dose both to workers occupationally exposed and to members of the public. This assessment take into account the radionuclides involved, the facility features, the working procedures, the expected number of patients per year, the administered activity, the distribution of rooms, the thickness and physical materials of walls, floors and ceilings and so on. The assessment results were compared to the design requirements established by the Cuban regulatory body in order to determine whether or not, the nuclear medicine facility complies with those requirements, both for workers and for members of the public. The work presented is useful for facility designer that uses unsealed radionuclides and for the regulatory body.

Resumen A nivel mundial se reconoce que la seguridad de las sustancias radiactivas es muy importante y que el diseño de las instalaciones, donde se utilizan y almacenan las mismas, tienen que implementar medidas de seguridad adecuadas, incluyendo el blindaje de algunos locales de tratamiento y diagnóstico. La evaluación de la protección radiológica de una instalación de medicina nuclear consiste en la determinación de la dosis efectiva anual, tanto para los trabajadores ocupacionalmente expuestos a las radiaciones como para los miembros del público. Esta evaluación tuvo en consideración los radionúclidos involucrados, las características de la instalación, los procedimientos de trabajo, la cantidad de pacientes que se espera tratar o diagnosticar por año, la actividad administrada, la distribución de los locales y el espesor de los materiales empleados en las paredes, pisos y techo, entre otros. Los resultados obtenidos de la evaluación fueron comparados con los requerimientos de diseño establecidos por el órgano regulador cubano para determinar si cumplen o no con tales requerimientos para los trabajadores expuestos y miembros del público. El trabajo presentado resulta útil para diseñadores de instalaciones que utilizan sustancias abiertas y para el órgano regulador.

Abstract At INFN-LNL (Istituto Nazionale di Fisica Nucleare- Laboratori Nazionali di Legnaro) SPES (Selective Production of Exotic Species), a new facility for the production of radioactive ion beams is being constructed at INFN-LNL (Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali di Legnaro). Radioactive ion beams of neutron-rich nuclei with high purity, in the range of mass between 80 and 160 amu, will be produced by nuclear reactions induced by 40 MeV protons from a cyclotron. The goal of the ISOLPHARM project is to provide a feasibility study for an innovative technology for the production of extremely very high specific activity beta emitting radionuclides as radiopharmaceutical precursors. The ISOL method, adopted in the ISOLPHARM project (a branch of the SPES project), gives the possibility of obtaining pure isobaric beams. In this way, no isotopic contaminations will be present in the beam and afterwards in a proper trapping substrate. The ground-breaking idea of the ISOLPHARM method was granted an International patent (INFN).

Resumen En INFN-LNL (Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali di Legnaro) SPES (Producción selectiva de especies exóticas), se está construyendo una nueva instalación para la producción de haces de iones radiactivos en INFN-LNL (Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali di Legnaro). Se producirán haces de iones radiactivos de núcleos ricos en neutrones con alta pureza, en el rango de masa entre 80 y 160 amu, por reacciones nucleares inducidas por protones de 40 MeV de un ciclotrón. El objetivo del proyecto ISOLPHARM es proporcionar un estudio de viabilidad para una tecnología innovadora para la producción de radionúclidos emisores de beta de actividad específica extremadamente alta como precursores radiofarmacéuticos. El método ISOL, adoptado en el proyecto ISOLPHARM (una rama del proyecto SPES), ofrece la posibilidad de obtener haces isobáricos puros. De esta manera, no habrá contaminaciones isotópicas en el haz y luego en un sustrato de atrapamiento adecuado. La idea pionera del método ISOLPHARM recibió una patente internacional (INFN).

Abstract We utilize various nuclear reaction codes with the aim to guide, interpret, and support the experiments in the proton-induced production measurements of radionuclides for the development of innovative radio-pharmaceuticals. The understanding of reaction cross sections at low-intermediate energies is crucial in this context and requires the knowledge of nuclear models available in different codes, such as EMPIRE, TALYS, and FLUKA. These nuclear reaction codes serve as tool to interpret the measurement of production cross-sections and to complete the measurements with estimates of production of contaminants and/or stable isotopes that are difficult to measure. We illustrate different model calculations to simulate isotope production useful in experiments devoted to the measurement of proton-induced production of the two theranostic radio-isotopes 67Cu and 47Sc.

Resumen Utilizamos varios códigos de reacción nuclear con el objetivo de guiar, interpretar y respaldar los experimentos en las mediciones de producción de radionúclidos inducidas por protones para el desarrollo de productos radio-farmacéuticos innovadores. La comprensión de las secciones eficaces de reacción en energías intermedias bajas es crucial en este contexto y requiere el conocimiento de modelos nucleares disponibles en diferentes códigos, como EMPIRE, TALYS y FLUKA. Estos códigos de reacción nuclear sirven como herramienta para interpretar la medición de secciones eficaces de producción y para completar las mediciones con estimaciones de producción de contaminantes y / o isótopos estables que son difíciles de medir. Ilustramos diferentes cálculos de modelos para simular la producción de isótopos útiles en experimentos dedicados a la medición de la producción inducida por protones de los dos isótopos teranósticos 67Cu y 47Sc.