Brazilian Journal of Radiation Sciences - BJRS ISSN 2319-0612 One way to impact radiation protection safety culture is by establishing adequate and proper communication processes among all the actors involved in radiation applications, in various fields such as industry, environmental conservation, analytical sciences, agriculture, medical diagnosis and therapy, and other areas. In this context, the BJRS as an open access journal, supported by the Brazilian Radiation Protection Society - SBPR, an IRPA associate society, aims to disseminate scientific articles on the major disciplines on radiation sciences, including: Biological and Health Effects of Radiation, Radiation Protection of Patients, Workers, and Members of the Public, Radiation Measurements and Dosimetry, International Recommendations and Regulations, Protection of the Environment, Education and Training, Technology and Development, Communication with Society, Stakeholder Engagement and Involvement, Safety Culture and Risk Perception, Emergency Preparedness and Response, Radioactive Waste Management, Safe Transport of Radioactive Materials, Nuclear Safety, Safeguards and Security of Radioactive Material Nuclear Law Nuclear Reactor Technology: new concepts Nuclear Fuel Cycle.
Sociedade Brasileira de Proteção Radiológica
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Application of Feedforward Neural Networks for Virtual Sensor Implementation in Nuclear Reactors
This study builds on a line of research developed at the Nuclear and Energy Research Institute (IPEN), focused on the use of Artificial Neural Networks (ANNs) to provide sensor redundancy in nuclear reactors. The proposed methodology consists of training a Feedforward Neural Network (FFNN) to estimate the value of one reactor variable based on measurements from other variables. The feasibility was demonstrated using data from IPEN’s nuclear research reactor and a scaled model. While previous works relied on data from a single operating cycle of the reactor, this study tested network performance using data from multiple cycles to assess accuracy and generalization, and to identify deficiencies in the method. One fault-free cycle was selected for training and validation, while five others were used for testing, featuring different events. Three temperature variables, three radiation variables, one power measurement, and one safety rod position were chosen as output sensors for the ANNs to estimate. Performance was evaluated using the Mean Absolute Percentage Error (MAPE). All ANNs performed well during training. However, only two temperature variables were estimated across all the test cycles with similar accuracy as in the training and validation process, with MAPE values below 3%. Other ANNs performed poorly, with instances of persistent offsets or failure to track the general shape of the measured signals. The results underscore the challenges posed by strong input-output correlations and the difficulty in capturing the full complexity of functional relationships within reactor variables.
Copyright (c) 2026 Frederico Emidio Wu, Thadeu das Neves Conti https://creativecommons.org/licenses/by/4.0
Committed Effective Dose by Ingestion Food Grown in PEPB
Radionuclides can be incorporated through ingestion and within the human body, they become a source of internal exposure. Therefore, identifying and quantifying the radionuclides present in food is an important step in environmental monitoring and radiological protection. From this perspective, the activity concentrations of 40K, 226Ra, 228Ra and 228Th were calculated for six organic crop samples: avocado, cabbage, carrot, persimmon, pineapple and onion, from the PEPB (stands for Pedra Branca State Park), Conservation Unit. Radionuclide analysis was conducted using gamma spectrometry with the use of a High Purity Germanium (HPGe) detector in conjunction with the Genie 2000 software package. The activity concentrations of the radionuclides were calculated based on simulated detection efficiencies. The highest activity concentration of 40K was obtained for the carrot (101.83 ± 15.47) Bq.kg-1, and the highest effective dose value, 1.64 µSv.year-1, was obtained for avocado. The concentration of 226Ra activity was below the minimum detectable activity in all samples. Concentrations of 228Ra were only detected in cabbage and carrots. Activity concentrations of 228Th were detected in all samples, although at low levels. Estimated ingestion doses are within the limits established by the ICRP 119. Thus, the consumption of these organic foods grown in the PEPB is radiologically safe.
The Meeting on Nuclear Applications (ENAN)
Copyright (c) 2026 Nadia Rodrigues dos Santos, Alessandro Mariano Domingues, Izabella Soares de Souza, Carlos Omar Pastrana Orejuela, Rosa Jimenez Bermudez, Ademir Xavier da Silva, Edmilson Monteiro de Souza, Inayá Corrêa Barbosa Lima https://creativecommons.org/licenses/by/4.0
Influence of dose rate on radiotherapy treatment of the U87MG cell line through cell viability
Glioblastoma multiforme is a tumor that affects glial cells and is common in humans, being the most aggressive of gliomas. Patients, after diagnosis, have an average survival of just over a year, even when undergoing standard treatment. Given the low estimated survival of patients with this type of tumor, the objective of the study is to investigate the contribution of dose rate in radiotherapeutic treatment using a human glioblastoma cell line called U87MG, through the MTT (brometo de 3-[4,5-dimetiltiazol-2-il]-2,5-difenil tetrazólio) cell viability assay. Three dose rates were tested, including 400 cGy/min which is used clinically in patients, as well as 1.400 and 3.300 cGy/min from a clinical linear accelerator. Sterile culture plates with U87MG cells were irradiated, then, manipulated in the laboratory for the execution of the cell viability assay. The irradiated plates showed lower cell viability than the non-irradiated group, but there was no significant difference in viability among the different tested dose rates.
Copyright (c) 2025 Arthur Rocha, Ruy Rayol Neto, Debora Assis Carneiro, Delano Valdivino Batista, Luiz Antonio Ribeiro da Rosa, Mariana Paranhos Stelling, Simone Coutinho Cardoso https://creativecommons.org/licenses/by/4.0
Re-characterization of pneumatic station position for short irradiations of IEA-R1 reactor for use in k0-method
This work presents the re-characterization of pneumatic station irradiation position of IEA-R1 reactor for use in k0-INAA method. The thermal-epithermal neutron flux ratio f and the epithermal neutron flux distribution factor α of the IPEN IEA-R1 reactor were determined at the pneumatic irradiation station. To obtain these values, the “bare triple monitor” method was used with 198Au –97Zr – 95Zr. To evaluate its reproducibility, the temporal variation of these parameters was analyzed, with validation carried out through irradiation of reference materials of geological origin G-S-N (granite) and biological INCT-MPH-2 (mix of herbs). The results obtained for f and α show that such values ​​are reproducible and compatible with each other, according to the normal Gaussian distribution for up to 1 standard deviation of confidence. The results obtained for the elements detected in the samples agree with the recommended values, with relative errors (bias) less than 10%, except in the case of Mn in G-S-N (16.3%). These results indicate that it is possible to routinely use this method for LAN-IPEN researchers to analyze geological and biological samples.
k0 -INAA, neutron activation method, neutron flux.
Copyright (c) 2026 João Pedro Oliveira Flores, Renato Semmler, Marina F. Koskinas, Denise Simões Moreira, Ione Makiko Yamazaki, Paulo Sérgio Cardoso da Silva, Vera Akiko Maihara https://creativecommons.org/licenses/by/4.0
Application of Optically Stimulated Luminescence Dosimeters in the Evaluation of the Dose Map Software in Interventional Radiology
Interventional radiology is widely employed; however, the complexity and duration of certain procedures may result in significant radiation exposure to patients. This study presents a comparison between a commercial computational dose mapping method used in interventional radiology, Dose Map, and optically stimulated luminescence dosimetry using a matrix built with these dosimeters. The dosimetric material was obtained from a roll of Landauer Luxel® tape and calibrated on a GE® Innova 4100 IQ angiography system, using an ionization chamber as a reference. The calibration yielded a linear relationship between the readout signal and the air kerma. Experiments were conducted using homogeneous poly(methyl methacrylate) phantoms, as well as clinical monitoring of patients. The maximum deviation between kerma values measured by the dosimeters and those estimated by Dose Map was 14%. The comparison among the dosimeter matrix, radiochromic film, and Dose Map demonstrated good geometric agreement in both phantom studies and patient monitoring. These results confirm the applicability of Dose Map for real-time dose monitoring, contributing to improved patient safety in interventional radiology.
Copyright (c) 2026 Eduardo Souza Santos, Denise Yanikian Nersissian, Elisabeth Mateus Yoshimura https://creativecommons.org/licenses/by/4.0
Evaluation of Public Exposure to Gamma Radiation in Cotonou, Southern Benin
The objective of this study is to assess public exposure to natural background gamma radiation in Cotonou, southern Benin, in West Africa. This is a cross-sectional study with both descriptive and analytical aims, conducted from July to December 2024. The methodology involved continuous, georeferenced measurement of the ambient gamma dose rate at a height of one meter (1 m) above ground level using a spectrometer. The study sites included city streets and selected markets, including Dantokpa, an open-air market, and eight indoor markets. A total of 341,991 data points were recorded along the streets and 16,202 were recorded within the markets. The ambient gamma dose equivalent rate along the streets ranged from 4.67 to 136.84 nSv·h– 1, with an average of 25.11 ± 12.72 nSv·h– 1. The highest average rate was observed in District 5, which hosts a cement manufacturing plant. The average dose rates were 23.71 ± 12.90 nSv·h– 1 at the Dantokpa market and 69.72 ± 21.96 nSv·h– 1 in the indoor markets. In the latter, the dose rates were higher than those recorded in their respective districts. The estimated external annual effective doses were 0.04 ± 0.02 mSv for streets, 0.10 ± 0.06 mSv for Dantokpa, and 0.30 ± 0.09 mSv for indoor markets. These values remain below the worldwide average of 0.87 mSv, as recognized by the United Nations Scientific Committee on the Effects of Atomic Radiation for public exposure to natural radiation of terrestrial and cosmic origin. Overall, ambient gamma radiation exposure in Cotonou is low, though higher in enclosed market environments. These values may serve as baseline references for future studies in Cotonou and other African cities.
Copyright (c) 2025 Dr Gilles David Houndetoungan, Dr Olatoundé Herbert Fachinan, Dr Mahougnon Boniface Zinsou, Dr Sonia Mahussi Gwladys Adjadohoun, Dr Gibril Abogbo, Dr Bonaventure Awede, Dr Martial Zoungrana, Dr Kuassi Marcellin Amoussou-Guenou https://creativecommons.org/licenses/by/4.0
ApplyApplying Deep Learning in gamma-spectroscopy for radionuclide identificationng Deep-learning in gamma-spectroscopy for radionuclide identification
This study presents the results of using a Deep Convolutional Neural Network model on gamma spectrum classification for radioactive waste management. The approach uses a modified version of the VGG-19 architecture, originally developed for image recognition with 1000 mutually exclusive classes. The modified VGG-19 architecture uses a gamma spectrum as input and classifies, on a nonexclusive basis, ten classes representing the ten most common radionuclides at IPEN's Radioactive Waste Management Department (Am-241, Ba-133, Cd-109, Co-57, Co-60, Cs-137, Eu-152, Mn-54, Na-22, Pb-210). Gamma spectra were generated using Monte Carlo simulations created with PENELOPE/PenEasy, simulating an HPGe detector with sources inside a steel drum filled with paper, representing the common content of the drums managed at IPEN's Radioactive Waste Management Department. The data set was augmented by mixing these simulated spectra into new spectra containing up to four radionuclides. Several distances from the detector to the drum (41 cm, 46 cm, 51 cm, and 56 cm) were used to create a representative data set. The data from 56 cm (originally 150 spectra after the argumentation process, 375 spectra) was used for validation. After 250 training epochs, the model achieved consistent performance in the training set, demonstrating the efficiency of the method.
Copyright (c) 2025 André Gomes Lamas Otero, Ademar José Potiens Júnior, Julio Takehiro Marumo https://creativecommons.org/licenses/by/4.0
Analysis of TG-43 dosimetric parameters for an Ir-192 HDR brachytherapy source using with the Geant4 toolkit
This study evaluated the dosimetric parameters of the Buchler G089 192Ir high-dose-rate brachytherapy source using the TG-43 formalism and Monte Carlo simulations with the Geant4 toolkit. The radial dose function and the anisotropy function were obtained for this source. For the radial dose function, a small discrepancy could be observed for larger radii. The dose rate constant (Λ) was also calculated in this study (1.114 cGy·h⁻¹·U⁻¹) showing a maximum relative difference of 0.45% when compared with reference values (1.119 and 1.115 cGy·h⁻¹·U⁻¹). The absorbed doses were obtained by positioning the source in the lowest voxel of the ICRP male phantom prostate and benchmarked against previous studies. For comparison criteria, the Amersham 6711-Oncoseed 125I source was also modeled and inserted in the same position of the prostate. Additionally, the dose enhancement effect due to the presence of gold nanoparticles (GNPs) was analyzed for the ¹⁹²Ir source, considering a homogeneous concentration of 30 mg·g⁻¹ in a tumor region simulated in the peripheral zone of the prostate. An approximately 18.5% increase in the absorbed dose was observed in this region, in agreement with results from previous studies.
Copyright (c) 2025 Alice Albuquerque, Dr. Luiz Antônio Ribeiro da Rosa, Dr. Denison S. Santos https://creativecommons.org/licenses/by/4.0
Development of a semi-analytical nodal methodology for one-dimensional eigenvalue problems based on multigroup neutron transport theory using the discrete ordinate formulation
A semi-analytical nodal methodology is described in this paper for obtaining the numerical solution of eigenvalue problems based on neutron transport theory, in slab geometry, with isotropic scattering, using the discrete ordinates and multigroup energy formulation. This new approach applies a quadratic polynomial approximation only to the fission term in the transport equation, which justifies the method being classified as semi-analytical. The numerical solution is obtained through two interconnected iterative processes: the outer iterative process, which uses the power method to obtain successive estimates for the fission source and the effective multiplication factor (<!-- [if gte msEquation 12]><m:oMath><m:sSub><m:sSubPr><m:ctrlPr></m:ctrlPr></m:sSubPr><m:e><m:r>k</m:r></m:e><m:sub><m:r>eff</m:r></m:sub></m:sSub></m:oMath><![endif]--> <span style="font-size: 11.0pt; line-height: 107%; font-family: 'Calibri',sans-serif; mso-ascii-theme-font: minor-latin; mso-fareast-font-family: 'Times New Roman'; mso-fareast-theme-font: minor-fareast; mso-hansi-theme-font: minor-latin; mso-bidi-font-family: 'Times New Roman'; mso-bidi-theme-font: minor-bidi; position: relative; top: 4.0pt; mso-text-raise: -4.0pt; mso-ansi-language: PT-BR; mso-fareast-language: PT-BR; mso-bidi-language: AR-SA;"> ), and the internal iterative process, which aims to obtain successive estimates of the angular neutron fluxes emerging from the homogeneous regions throughout the spatial domain. Once the eigenvalues are calculated, for each outer power iteration, the angular fluxes of neutrons emerging at the node faces and in the sweeping direction of the internal iterative process are estimated. These are incoming fluxes at the faces of adjacent nodes, which ensures the continuity of the numerical solution. Computational algorithms were implemented in MATLAB. Numerical results for a typical benchmark problem considering an ADS, c.f., Accelerator-Driven Subcritical Reactor, type model are provided to illustrate the accuracy of the converged numerical solutions in coarse-mesh calculations. Although the method is not free from spatial truncation error, the results for the benchmark problem were considered satisfactory with one node per region, and refining the spatial domain did not result in a high computational cost in terms of response time, with results approaching those of analytical solutions.
Meeting on Nuclear Reactor Physics and Thermal Hydraulics (ENFIR)
National Week of Nuclear and Energy Engineering and Radiation Sciences (SENCIR)
Neutron transport equation, Multigroup energy formulation, Nodal methodology
Copyright (c) 2025 Natália Rocha Pinheiro, Francisco Bruno Souza Oliveira, Hermes Alves Filho https://creativecommons.org/licenses/by/4.0
Practical leak detection and leak rate measurement applied to a hot cell for radiopharmaceuticals preparations in a GMP compliant Laboratory
Hot cells are containment systems used in radiopharmaceutical production, designed to ensure radiation protection and product quality. Leak tightness testing is a mandatory requirement under CNEN NN 6.13 standard, as it directly impacts worker safety, environmental protection, and product integrity. This study aimed to perform a practical pressure change leak test in a hot cell used for radiopharmaceutical preparations, in accordance with applicable technical standards. The pressure change method was applied using pressures between 1.6 and 2.5 higher the working pressure for a testing time of 15 minutes. The method proved practical, requiring no highly specialized equipment, although its sensitivity to temperature highlights the importance of high-precision thermometer. Results showed that while the method is suitable for ISO 10648-2:1994 Class 2 compliance, it may not be adequate for Class 1 due to the risk of mathematically inaccurate results under temperature variations. Multiple rounds of leak detection and repair were required to achieve the required containment level. Overall, the DC, RIC, CIC, and Solid Waste chambers met Class 2 leak tightness requirements, being suitable for use in radiopharmacy facilities.
Copyright (c) 2026 Rodrigo da Silveira Santos, Carlos Leonel Zapparoli, Joel Mendes dos Santos, Gabriela Franco da Rosa Caetano, Marcelo de Gusmão Paraíso Cavalcanti, Delvonei Alves de Andrade https://creativecommons.org/licenses/by/4.0
Electronic Brachytherapy: A Calibration Protocol in Terms of Absorbed Dose to Water"
New radiotherapy techniques have been innovative in recent decades with the aim of maximizing the dose to tumor tissue and reducing the dose to healthy tissue. One of the modalities that has gained prominence, using low-energy beams, is intraoperative radiotherapy (IORT), as it is a method based on high radiation doses (10–20 Gy) administered to the tumor bed immediately after surgical excision. IORT can be achieved through treatment with low-energy X-ray beams with some devices available on the market. However, such devices provide little dosimetric information and lack a calibration protocol. According to the recently updated recommendations of the TRS 398 standard (2024), for the use of low-energy beams, the ideal is to use a parallel plate ionization chamber calibrated in terms of absorbed dose in water. Based on TRS 398, this work established a calibration protocol for parallel plate dosimeters in terms of absorbed dose in water at the Center for Ionizing Radiation Metrology (CEMRI) of the Institute for Energy and Nuclear Research (IPEN).
intraoperative radiotherapy, radiation metrology, dosimeter calibration
Copyright (c) 2026 Fábio Dias, Orlando Rodrigues Jr, Maria da Penha Albuquerque Potiens https://creativecommons.org/licenses/by/4.0
Comparative Study of Thermal Neutron Flux from Gold Foil Activation.
This study presents a comparative analysis between Monte Carlo simulations (MCNP-5) and experimental measurements of thermal neutron fluence using gold foil activation at the TNF2 irradiation facility of the Neutron Metrology Laboratory (LNMRI/IRD). The MCNP-5 model was constructed to replicate the irradiator geometry and source configuration. Gold foils, both bare and cadmium-covered, were irradiated and analyzed via gamma spectrometry to determine the induced activity of 198Au. The results of the calculated nuclear reaction rates were compared to the measured activities through C/E (Calculated/Experimental) analysis. The findings show consistent agreement within experimental uncertainty, supporting the accuracy of the MCNP model and reinforcing the role of TNF2 in the national and international metrological infrastructure for neutron dosimetry. Future developments will include improvements in flux mapping and personal dosimetry applications.
The activation of gold foil through thermal neutron bombardment
Copyright (c) 2026 Watila Lins Silva, Max Ramos, Regio Santos Gomes, Achiles Astuto, Walsan Wagner Pereira https://creativecommons.org/licenses/by/4.0
Pathological Studies in Uteruses by X-ray Microtomography
X-ray computed microtomography (microCT) is an advanced technique for evaluating materials that uses the principle of X-ray attenuation to form high-resolution two- and three-dimensional images. This technique allows detailed visualization of the microstructures of biological samples through the digital combination of hundreds of cross-sections. As a non-destructive technique, microCT requires minimal sample preparation and does not cause damage to the analyzed material. This work aims to use microCT to obtain high-resolution images of the ex-vivo uterus, demonstrating the possibility of visualizing microstructures, detailing tissues and contributing to the anatomical and pathological study of these organs. The research also highlights the relevance and usefulness of microCT as a modern and effective technique for the non-destructive analysis of biological samples, emphasizing its potential in several areas of science and medicine. In addition, it seeks to validate microCT as an essential tool for medical research, providing a deeper understanding of the internal structures of organs and their possible pathologies.
Copyright (c) 2026 Larissa M. Gonçalves, Olga M. O. Araujo, Alessandra S. Machado, Pedro Castro, Ricardo T. Lopes https://creativecommons.org/licenses/by/4.0
Development of Spheroid in Co-Culture of Prostate Tumor with Human Fibroblast, using the Hanging Drop Technique with Plate Inversion for Analysis of GammaCell220 Irradiation in Co-60
The development of tumor spheroids in co-culture with human fibroblasts represents an innovative approach to modeling the prostate cancer microenvironment and assessing radiation effects. In this study, we employed the "hanging drop" technique in conjunction with plate inversion to generate three-dimensional spheroids composed of prostate tumor cells (LNCAP cell line) co-cultivated with human fibroblasts. This approach aims to create a more representative in vivo-like tumor environment, facilitating a detailed analysis of the interactions between tumor cells and fibroblasts in 3D conditions. The formed spheroids were exposed to gamma radiation using a GammaCell 220 irradiator with Co-60, with the goal of investigating the effects of radiation on both fibroblastic and tumor cells. Gamma radiation is known to induce cell death, and this study examines how such damage impacts cellular morphology within the spheroid microenvironment.
Copyright (c) 2026 Thais Monteiro, Alex Alves Rodrigues, Giovana Dias da Silva, Esther Carolina dos Santos, Patricia Lima Falcão, Suleyna Ribeiro Prudente, Mayelle Maria Paz, Daniel Perez Vieira https://creativecommons.org/licenses/by/4.0
Retrospective study of radiation exposures during interventional cardiology procedures performed at the University Cardiovascular Center of Uruguay
The number of interventional cardiology procedures has increased rapidly during the last decades. Fluoroscopic X-ray procedures, such as coronary angiography and percutaneous transluminal coronary angioplasty, are considered the largest source of medical occupational exposure, either for patients or operators, causing deleterious health effects. In this respect, several modifications in classical interventional cardiology procedures as well as the incorporation of radiation protection protocols for reducing radiation exposure have been developed. To adequately know the success in the application of these changes, the reference values of radiation exposure for different interventional cardiology procedures should be established. For this purpose, a retrospective, cross-sectional and descriptive study was carried out at the University Cardiovascular Center from the Faculty of Medicine (University of the Republic) of Uruguay between 2018 and 2020, with the aim to know the frequency of procedures performed as well as the average of delivered radiation dose, the fluoroscopy time and the Kerma-rea product for every interventional procedure. Urgent angioplasty procedure was the most frequent interventional procedure performed, producing the highest exposure level of occupational radiation workers and patients. It was established for the first time in Uruguay reference levels for the three most frequent interventional cardiology procedures using the third quartile of radiation exposure parameters employed (Total dose delivered, Kerma-area product and fluoroscopy time). Reference values obtained were in agreement with the ones found at international level.
International Radiation Protection Association (IRPA)
percutaneous transluminal coronary angioplasty
Copyright (c) 2026 Rafael Mila, Fredy Hernandez, Jaime J. Cordon, Ariel Duran, Wilner Martínez-López https://creativecommons.org/licenses/by/4.0
Analysis of the principles of green chemistry in the radioiodination of metaiodobenzylguanidine compared to the principles already adopted for radiological protection
Environmental concerns have increasingly highlighted the importance of applying methodologies that prioritize safer waste treatments, the use of less toxic reagents, and milder synthesis conditions. In this context, radioiodinated metaiodobenzylguanidine (MIBG) stands out as a key radiopharmaceutical used in diagnostic scintigraphy and therapy of neural crest-derived tumors, such as pheochromocytoma and neuroblastoma, as well as in assessing sympathetic neuronal integrity after cardiac events. Halogenation reactions that avoid toxic reagents and hazardous conditions are essential for producing safe pharmaceutical compounds. Radioiodination, a specific type of halogenation, plays a critical role in the synthesis of radiopharmaceuticals—radioactive compounds formulated for diagnosing and treating human diseases. A major challenge in the production of radioiodinated MIBG is aligning the process with the principles of green chemistry, emphasizing the use of harmless substances and minimizing their quantities, while also meeting stringent nuclear, radiological protection, and pharmaceutical regulations. However, green chemistry considerations are often neglected in this process. This study quantitatively assesses the application of green chemistry principles to existing radioiodination methods for MIBG. The degree of compliance with each principle was expressed as a percentage. Additionally, a qualitative analysis was conducted to explore the alignment between green chemistry and radiological protection principles. Green chemistry is guided by twelve principles: Prevention, Atom Economy, Less Hazardous Chemical Syntheses, Designing Safer Chemicals, Safer Solvents and Auxiliaries, Energy Efficiency, Renewable Feedstocks, Reducing Derivatives, Catalysis, Design for Degradation, Real-Time Analysis for Pollution Prevention, and Inherently Safer Chemistry for Accident Prevention. This work examines how each principle applies to MIBG radioiodination, with some aspects also discussed in the broader context of radiopharmaceutical production. While radioiodinated MIBG complies fully with pharmaceutical requirements in its final medicinal formulation, its production currently incorporates about 68% of the green chemistry principles. As radiopharmaceutical production moves forward, greater attention should be given to eco-friendly practices. Investing time and resources into adopting green principles for MIBG radioiodination is a logical next step. This radiopharmaceutical holds well-established clinical importance, and future advances in its production should embrace sustainable, environmentally conscious methodologies.
International Joint Conference Radio (RADIO)
Copyright (c) 2026 Antonio Pedro Junior, Eliene Bezerra Simão da Silva, Francisco José de Oliveira Ferreira, Rogerio Chaffin Nunes, Karine Rocha Ramos da Silva, Larissa Cunha Pinheiro, Fellipe Souza da Silva, Luciano Moreira Lima, Adriana Marques, Cintia Andrade Custódio, Luciana Carvalheira https://creativecommons.org/licenses/by/4.0
Study for the Development of a Biosensor Aimed at the Interaction-Response of Chemical War Agents and Ionizing Radiation
It has long been known that the nuclear sector is a potential branch capable of solving major obstacles relevant to modern society with regard to energy demands. The technology in this sphere is associated with various possibilities, including areas that require multidisciplinary expertise for their respective advancements, such as medical sciences, security and defense, national autonomy and sovereignty, energy generation, food technology, among others. With the development of nanostructured technologies, highly sensitive, accessible, and easy to handle, it is possible to introduce new alternatives to reduce the “gap” between these possibilities within the sector, making the nuclear area more visible to new researchers due to the potential for new research to be developed. With the prospect of innovation for the sector and with increasing technological input, a special look at instrumental and measurement issues is necessary, since it is also necessary to ensure the quality of nuclear technology for the development of any system focused on this theme. This research presents a combination of different areas, highlighting the multidisciplinarity of construction, aiming to obtain the necessary support for the creation of a device capable of interacting with systems that represent chemical and radiological-nuclear threats. As it is a biosensor, it presents a biological interface sensitive to chemical warfare agents (organophosphates), neurotoxins and undergoes a process analogous to radiolysis, it is the means by which it is possible to associate electronics to the system, being capable of transducing information from one form of energy to another, making it possible to quantify and obtain relevant and proportional information about the exposure of this system created. For the in silico study carried out, the energy fluctuations for both the chemical simulations and the MCNP simulations were guiding the verification process, since the lower the energy value, the stronger the chemical interaction between ligands and enzymes.
Copyright (c) 2025 João Nilton da Conceição Bandeira, Fabiane Modenese Garbim, Joyce Sobreiro Francisco Diz De Almeida, Álvaro José Boareto Mendes, Fernando Manuel Araújo Moreira https://creativecommons.org/licenses/by/4.0
Evaluation of the antioxidant, cytotoxic and radioprotective potencial of the lectin WSMoL from Moringa oleífera Lam. seeds
WSMoL (water-soluble lectin from the seeds of Moringa oleifera Lam.) is widely known for its biological properties, especially for its inflammatory, immunomodulatory and antitumor activity and is a promising candidate for a radioprotector of natural origin. Aim of the study: This study aimed to evaluate the antioxidant and cytotoxic potential and the radioprotective effect of WSMoL in human lymphocyte culture (PBMC). The concentrations analyzed were 850, 425, 212.5, 106.25 and 53.12µg/mL. Materials and methods: Antioxidant activity was tested using the DPPH and ABTS assays. Cell viability and cytotoxicity were assessed using the MTT assay on PBMC lymphocytes. Radioprotection was verified by the Alkaline Comet and Micronucleus with Blockage of Cell Cytokinesis assays after exposure to Cobalt-60 gamma radiation. Results: In the DPPH test, WSMoL was unable to capture the radical. In the ABTS test, the inhibition index (I%) was ≤10% and the IC50 was 71.42 g/L. The MTT test showed that the lectin was not cytotoxic and cell viability was over 79%, with a maximum (≤125%) at a concentration of 53.12 µg/mL. In the Alkaline Comet test, the Damage Index (DI) observed was high at concentrations of 850 and 53.12 µg/mL (≥170 ± 30). The Damage Frequency (y) observed through the Micronucleus assay was 0.260 for the two concentrations analyzed, similar to the y of the irradiated control group. Conclusion: WSMoL did not show significant antioxidant activity in the DPPH and ABTS tests. The lectin did not show a cytotoxic profile, and its use at a concentration of 53.12µg/mL is recommended. WSMoL showed no radioprotective capacity after exposure to gamma radiation at a dose of 2.5Gy.
Copyright (c) 2025 Osana Diniz Ferreira, Andreza Lima Lourenço da Silva, Karine Lafaiete De Carvalho, Thaynara Maria Arantes, Vinícius Henrique Teixeira Morais, Dewson Rocha Dewson Rocha Pereira, Thiago Henrique Napoleão, Mércia Liane de Oliveira, Ana Maria Mendonça de Albuquerque Melo https://creativecommons.org/licenses/by/4.0
Tissue Reactions (Deterministic Effects) in Diagnostic and Interventional Radiology: An Integrative Review of Recent Literature
Ninety-eight percent of the global average individual dose delivered by artificial sources of ionizing radiation results from their use in medical applications, especially for diagnostic and interventional purposes. Although the benefits of radiation in medicine are widely recognized, exposure to this agent can cause harmful effects on the health of exposed individuals. Radiation applications for diagnostic purposes are generally associated with low doses, but interventional procedures may involve much higher doses. In the 2000s and 2010s, several publications described tissue reactions in patients and professionals exposed during interventional radiological procedures. This work aimed to review the literature on the most recent reports (last decade) on the occurrence of tissue reactions after diagnostic or interventional radiological procedures. The PubMed search tool was used to search and select publications on the topic. Although 826 articles were initially selected, only 5 presented relevant content for this review. The low number of articles in the final selection may be a result of the methodology we used or an actual reduction in the number of individuals presenting these effects in more recent years, due to the growing concerns about radiological protection in these practices. Among the articles analyzed, there were reports of skin lesions, as well as thinning or hair loss in patients exposed to doses (cumulative air kerma at the reference point) above 3.5 Gy. However, these reactions are rare and do not appear in most patients, even among those who received higher doses. An increased frequency of lens opacities (cataracts) has also been reported in occupationally exposed professionals. An adequate assessment of the occurrence of these effects is essential to try to understand their causes and minimize the frequency or consequences of their occurrence. Carrying out research like this can help with this task.
Copyright (c) 2025 Laisa Neves, Lucía Canevaro Lucía Viviana Canevaro, Ana Dovales Ana Cristina Murta Dovales https://creativecommons.org/licenses/by/4.0
Evaluations of the possible mutagenic and genotoxic effects of 2-ACBs: by-products generated from irradiated foods
This study investigates the potential mutagenic and genotoxic effects of 2-Alkylcyclobutanones (2-ACBs), by-products formed in irradiated foods. 2-ACBs are compounds derived from the irradiation of fat-containing foods, with recognized genotoxic potential. The research focused on the compounds 2-dodecylcyclobutanone (2-dDCB) and 2-tetradecylcyclobutanone (2-tDCB), evaluating their mutagenicity through the micronucleus assay in hepatic cell lines (HepG2, BRL3A, and HTC) and genotoxicity through the Ames test using five bacterial strains (TA-98, TA-100, TA-1535, TA-1537, and WP2uvrA). Results from the Ames test indicated that 2-dDCB and 2-tDCB did not significantly increase mutagenic reversion rates, while the micronucleus assays showed no genotoxic damage in the tested cell lines. It is concluded that, at the evaluated concentrations, the compounds 2-dDCB and 2-tDCB do not exhibit mutagenic or genotoxic potential, supporting the safety of irradiated foods. However, further research is recommended to assess long-term effects and different irradiation conditions.
Copyright (c) 2025 Angélica Bueno Barbezan, Ana Carolina de Araújo Bispo, Bruno Melo Mendes, Daniel Perez Vieira, Luma Ramirez de Carvalho, Glaucia Maria Machado-Santelli, Anna Lúcia Casaas Haasis Villavicencio https://creativecommons.org/licenses/by/4.0
Human biomonitoring in residents of a NORM area using the comet assay, Pernambuco-Brazil
Geological research has found areas of uraniferous phosphorite in northeastern Brazil. This region is located along the coast of the states of Paraíba and Pernambuco, Brazil. Its distribution in Pernambuco is located in the Metropolitan Region of Recife/Região Metropolitana do Recife (RMR), covering the municipalities of Abreu e Lima and Olinda. Studies have been carried out in these municipalities, verifying the presence of Naturally Occurring Radioactive Material (NORM) in different matrices: soil, groundwater, air and fruit. Given these facts, the need arose to carry out human biomonitoring (HBM) in residents of these municipalities. Therefore, the aim of this study was to assess possible DNA damage in the residents of Olinda and Abreu e Lima by means of the comet assay using lymphocytes. The results showed high levels 3 and 4 damage to the DNA of the volunteers in the sample group who are under the influence of NORM, demonstrating a statistically significant difference in the damage index when compared to the control group. It is suggested that the genotoxic results found may be related to the NORM present in the municipality of Abreu e Lima, thus influencing the health of its residents. The research is relevant because it is a pioneer in the generation of scientific knowledge in the area of the study of uraniferous phosphorite using HBM.
Copyright (c) 2025 Vinícius Henrique Teixeira Morais, Dewson Rocha Pereira, João Emanuel Firmo Pinto, Osana Diniz Ferreira, Ana Maria Mendonça de Albuquerque Melo https://creativecommons.org/licenses/by/4.0
Thermal-Hydraulic Analyzes of a Slow Loss of Flow Accident in the IEA-R1 nuclear reactor using RELAP and CFD Codes
Among the most critical accidents for the IEA-R1, there is the Loss of Flow Accident (LOFA) in which a sudden and abrupt stop of the primary pump causes the loss of flow. Traditionally, this kind of accident is analyzed by thermal-hydraulic system codes. However, they can overestimate the fluid and fuel temperature along the transient by up to 20%. Moreover, thermal-hydraulic system codes can face difficulties to capture three-dimension phenomenon, such as the natural convection. Meanwhile, Computational Fluid Dynamics (CFD) analysis has shown good results when analyzing open-pool research reactor accidents even dealing with flow inversion. This work presents a thermal-hydraulic analysis of a Slow Loss of Flow Accident (SLOFA) in the IEA-R1 using the RELAP5 code and the commercial CFD code Ansys CFX®. The objective is to combine the advantages of both approaches. The system code was used to find the transient boundary conditions for a CFD model. The CFD software solved the detailed flow pattern in a quarter of a fuel channel. The numerical results showed good agreement with the benchmark data. The peak temperatures were overestimated in only 1.8 °C in the fluid and 3 °C in the cladding.
Copyright (c) 2025 Franklin Cândido Costa, Antônio Belchior Júnior, Walmir Maximo Torres, Pedro Esnesto Umbehaun, Delvonei Alves D. Andrade https://creativecommons.org/licenses/by/4.0
Radionuclides Leaching Assessment and External Exposure on Building Materials Containing NORM Residue
Brazil’s titanium dioxide production generates approximately 30,000 tons of waste annually, known as unreacted ore waste (UOW), which is currently disposed of in industrial landfills. This residue is enriched with naturally occurring radionuclides from the uranium and thorium decay series and is classified as Naturally Occurring Radioactive Material (NORM). The reuse of NORM residues in building materials is only permissible if the activity concentrations of radionuclides in the final product do not pose any additional exposure risk to individuals. Radiation exposure from such materials may be classified as external—due to direct gamma irradiation—or internal—resulting from inhalation of radon (222Rn) and its short-lived decay products. In a previous study, the authors assessed both internal and external indoor exposure associated with incorporating up to 23% of UOW into cement and interlocking blocks. This study evaluates the feasibility of using these materials in outdoor applications, with particular emphasis on radionuclide leaching potential and external radiological exposure. Cement and interlocking blocks containing varying proportions of unreacted ore waste (0%, 3.5%, and 23%) were subjected to weathering for 60 days. The activity concentrations of 238U, 226Ra, 210Pb, 232Th, 228Ra, and 40K in the leachate were measured using gamma spectrometry and spectrophotometry. No significant increase in radionuclide concentrations were observed in the leachate from blocks containing 3.5% and 23% UOW compared to those without any residue. Gamma radiation exposure remained consistently below 0.1 mSv, and no notable changes were detected in radon concentrations in the vicinity of the experiment. The results indicate that incorporating up to 23% UOW in cement and interlocking blocks is safe and compliant with regulatory limits related to groundwater contamination and human exposure when using these materials in an open air environment.
Copyright (c) 2025 Barbara Paci Mazzilli, Fenanda Yuri Muta, Lara Vitória Santos Couto, Antonio Luis Silva Costa, Vilmar Pedreira Oliveira, André Luis Batista Cabral https://creativecommons.org/licenses/by/4.0
Assessment of Natural Radioactivity in a Residence in Belo Horizonte
Natural radioactivity comes from natural radionuclides present in rocks and soil and from cosmic rays. In addition to gamma-emitting radionuclides, radon stands out, which is a carcinogenic gas. In nature, radon occurs as radioisotopes: 222Rn (half-life time, t1/2,of 3.83 d), 219Rn (t1/2 = 3.92 s) and 220Rn (or thoron, t1/2 = 54.5 s). The World Health Organization (OMS) recommends that it be measured in homes, with the recommended limit being 100 Bq/m3 and the maximum limit being 300 Bq/m3. This work evaluates the origin of natural radiation in a residence in Belo Horizonte, Minas Gerais, Brazil, in which was observed radon concentrations above the limits established by the OMS. The detectors used were: nuclear trace detectors type CR-39, electrets (E-PERM), AlphaGUARD (AG) and the detector RS-230. The result of the 222Rn concentration measured in the electrets in the rooms of the residence varied from 14,8 Bq/m3 to 932 Bq/m3. At this highest point, the result of the average concentration of AlphaGUARD was from 4.78 kB/m3, with a maximum value of 8.5 kBq/m3. The concentration of 220Rn varied Bq/m3 Bq/m3. As this is a basement-type room, the bedroom next door was investigated, in which it is highlighted that the radon concentration of the detector CR-39 was from 445 Bq/m3, AG of 198.2 Bq/m3 with a maximum value of 350 Bq/m3, and electret of 29.6 Bq/m3. Gamma scanning with the RS-230 indicates higher counts on uncoated walls. Measurements of radon in the water showed background concentrations. It is concluded that poor ventilation of the location must be the biggest contributor to the high concentration of 222Rn, which originates mainly from the soil. The thoron concentration was higher in construction materials due to the measurement method. The instrumentation used allows a complete and comparative study between detectors in order to find the origin of natural radionuclides and subsequently suggest appropriate mitigation measures. In future studies, radon concentration in the soil and radon progeny will be measured.
Copyright (c) 2024 Sueli da Conceição Teixeira Coelho, T.O. Santos, L. C. Takahashi, I. N. S. Ferreira, R. G. Passos https://creativecommons.org/licenses/by/4.0
Computational Analysis of Gamma-Ray and Fast Neutron Attenuation performance of some Thorium and Uranium Compounds
Evaluation of the radiation shielding effectiveness of some compounds including Fe, Th, Y, Nb, Ta, Ti, and U have been computed for energy absorption and total interaction in the photon energy range from 0.015 to 15 MeV. The effective atomic number (Zeff), of these compounds was determined via the mass attenuation (µ/ρ, cm2/g) and mass energy absorption (µ/ρ, cm2/g)en coefficients. Accordingly, the values ​​of Zeff have been computed for total photon interaction (ZIeff) and energy absorption (ZAeff) using Py-MLBUF and Phy-X/PSD codes. The effective removal cross section for fast neutrons (ΣR, cm-1) and attenuation lengths were also calculated to study the attenuation properties of fast neutrons. The results displayed showed that, Zeff of S1 (UO2) and S2 (ThSiO4) are comparatively higher than the Zeff of the remaining compounds, while S7 (Fe(UO2)2(PO4)2.8(H2O)) possesses the lowest values of Zeff. The obtained results also show that ZAeff should be used instead of ZIeff when the quantity of interest is energy dissipation. In addition, the calculated values of ΣR ​​for the tested compounds were found to be close and ranged from 0.079 cm-1 for S4 to 0.146 cm-1 for S1. Moreover, comparison of the calculated values ​​for different shielding parameters showed good agreement between the proposed methods. Finally, this study could be useful in applications of these compounds for shielding requirements from gamma-ray and fast neutron in different fields such as, nuclear fuel cycles and medical shielding in uranium-handling environments.
Copyright (c) 2025 A. M. Osman https://creativecommons.org/licenses/by/4.0
Characterization of Phosphogypsum from Cartagena and Huelva, Spain
Phosphogypsum (PG), a by-product of phosphoric acid production, is recognized as a Technologically Enhanced Naturally Occurring Radioactive Material (TENORM) due to its enrichment in uranium-series radionuclides. In Spain, particularly in Huelva and Cartagena, large PG stacks raise growing environmental concerns related to soil and groundwater contamination. This study presents a mineralogical and preliminary environmental assessment of PG samples from these regions using X-ray diffraction (XRD) and energy-dispersive X-ray fluorescence (EDXRF). Gypsum (CaSO4 · 2 H2O) was identified as the dominant crystalline phase in all samples. Variations in peak intensity and preferred orientation suggest mineralogical heterogeneity linked to source rock properties and processing conditions. Subtle peak shifts and broadening indicate co-hydration with H2O and D2O, consistent with isotopic fractionation during crystallization. EDXRF analysis also revealed the presence of heavy metals such as chromium (Cr), nickel (Ni), lead (Pb), and zinc (Zn), as well as trace elements like strontium (Sr) and barium (Ba), which may influence environmental risk. No discrete phases of uranium, thorium, or radium were detected by XRD, supporting their probable incorporation at trace levels through substitution or adsorption, a finding confirmed by EDXRF elemental analysis. This mineralogical and chemical data forms the baseline from which a further comprehensive material characterization will be drawn, integrating gamma spectrometry, ICP-MS and SEM to evaluate the chemical speciation and environmental risk of PG. Based on Web of Science data, over 300 peer-reviewed articles on PG were published globally between 2020 and 2025, with China, Morocco, and Brazil leading in scientific output. The growing research interest underscores the strategic relevance of detailed PG characterization for informing safe reuse, regulatory decisions, and circular economy applications.
Copyright (c) 2025 Carla Ricardo, Cristina Trull-Hernandis, Belen Juste, Gumersindo Verdú, Claubia Pereira, Arno Heeren https://creativecommons.org/licenses/by/4.0
Estimation of Typical Values (DRL) in Angioplasties Performed at a Radiology Service of a Hospital in Southern Brazil
Interventional radiology involves diagnostic and therapeutic interventions using X-ray-emitting equipment. Due to the high radiation doses administered to patients during these procedures, there is a significant risk of severe tissue reactions resulting from prolonged exposure. To prevent unnecessary high doses during patient exposures, the International Commission on Radiological Protection recommends the use of Diagnostic Reference Levels (DRLs) as an effective tool for optimizing procedures in diagnostic or interventional radiology services. This study aimed to estimate the DRLs (typical values) resulting from interventional radiology procedures conducted in a public hospital in southern Brazil. To achieve this, a database was developed to facilitate the collection of information regarding exposures during interventional procedures, enabling the establishment of DRLs specific to a single facility, known as typical values. Patient and procedure data were collected and tabulated by the Radiation Protection Service (SPR) of the hospital through consultation with the interventional radiology service’s logbook or, if necessary, the State Information System of Risk and Potential Benefit (SIERBP), followed by the application of exclusion criteria. After data collection, the typical doses received by adult patients undergoing these procedures were estimated through simple descriptive statistics, using the median of the data distribution and the standard deviation. The results obtained provide a better understanding of the necessary actions, whether optimization or protocol review, to ensure the radiological protection of patients. This approach has the potential to benefit not only the patients but also the entire professional team involved in the interventional radiology service.
Estimation of Diagnostic Reference Levels
Copyright (c) 2025 Fernando Rockembach Mazuim, Isadora Tomanqueves Costa, Florencia Agustina Gutierrez Perez, Cristiny Tretto Lemes Pereira Dutra, Marcos Araquem Scopel, Tiago Trindade Hahn, Catia Simone Griebler Gomes, Daiane Cristini Barbosa Souza https://creativecommons.org/licenses/by/4.0
Application of TLD Dosimeters (CaSO₄: Dy and LiF:Mg,Ti) for Environmental Assessment of H*(10) in Field Studies.
The increasing use of ionizing radiation across various sectors of society underscores the need for effective monitoring of occupationally exposed individuals (OEIs), the public, and the environment. Within this framework, environmental radiation protection programs adopt the ambient dose equivalent H*(10) as the operational quantity, as defined by the International Commission on Radiological Protection (ICRP) and recommended by the International Atomic Energy Agency (IAEA), due to its suitability for estimating the risk of external exposure under field conditions. This study assessed the ambient dose equivalent H*(10) through a field survey conducted around the perimeter of the IPEN facilities. Eight monitoring points were selected near thirteen already existing environmental sampling stations, covering approximately 60% of the area. The monitoring was structured in three stages: (i) a comparative analysis between monthly and quarterly measurements using CaSO₄:Dy thermoluminescent detectors (TLDs), which showed proportional responses; (ii) a comparison between quarterly measurements with CaSO₄:Dy and LiF:Mg,Ti TLDs, which demonstrated equivalent results; and (iii) a comparison between the quarterly CaSO₄:Dy data from this study and those obtained in the Environmental Radiological Monitoring Program of the Center for Metrology of Ionizing Radiations of IPEN (ERMP/CEMRI-IPEN), which indicated consistent and satisfactory results, confirming the reliability of using H*(10) in the applied monitoring system. Statistical and uncertainty analyses further confirmed the robustness of the environmental monitoring with thermoluminescent dosimeters. Proper detector selection remains essential to ensure accuracy, minimize variability, and enhance environmental radiation monitoring programs.
Copyright (c) 2025 Ms. Teresa Soares, Dra. Linda Caldas, V. P. Campos, L. L. Campos https://creativecommons.org/licenses/by/4.0
Preliminary Studies on the Distribution of Stable Pb and Pb-210 in the Maternal and Fetal Portions of Human Placentas
Fetal growth and survival are solely dependent on the placenta, making the characterization of toxic elements in this tissue crucial for understanding exposure during pregnancy. Stable lead (Pb) and Pb-210 are toxic elements of particular interest in this context. Stable Pb has been linked to developmental changes in children, while Pb-210, a beta-emitting radionuclide with a 22.3-year half-life, can increase cancer risk, particularly bone sarcomas, when present in excess. Placental uptake of stable Pb and Pb-210 can occur through ingestion of food and water, as well as inhalation of air, with smoking and air pollution being significant contributing factors. Recent research suggests that even low levels of environmental chemicals, especially potentially toxic elements, can significantly disrupt placental homeostasis. This preliminary study aimed at determining the concentrations of stable Pb and Pb-210 in the maternal and fetal portions of placentas from eight women who delivered at the Hospital das Clínicas, Faculdade de Medicina, University of São Paulo. Concentrations from 5.7 ± 1.2 ng g-1 to 210.3 ± 2.4 ng g-1 and from 31.5 ± 2.9 Bq kg-1 to 43.3 ± 3.1 Bq kg-1 were obtained for stable Pb and Pb-210, respectively. The results showed that both elements can cross the placental barrier and reach the fetal compartment, albeit at lower concentrations than in the maternal portion.
Copyright (c) 2025 Laíssa A. Bonifacio, Nathália V. dos Santos, Naomi Akiba, Maciel S. Luz, Rossana P. V. Francisco, Barbara P. Mazzilli https://creativecommons.org/licenses/by/4.0
Influence of Ionizing Radiation on Additive Manufacturing of ABS
This paper presents an analysis of the behavior of acrylonitrile butadiene styrene (ABS), a material widely used in 3D printing, when exposed to continuous ionizing radiation. Therefore, a detailed investigation of the changes in its mechanical properties is proposed. To this end, specimens specifically designed for each test were created and printed in two different configurations: solid and with 20% infill. The tests aimed to evaluate the material's mechanical response after irradiation, comparing irradiated and non-irradiated samples. Tensile, hardness, compression, ballistic, and density tests were performed. The irradiation stage took place at the Institute of Chemical, Biological, Radiological, and Nuclear Defense (IDQBRN), in collaboration with the Military Engineering Institute (IME). The main objective of the research is to evaluate the durability of ABS after a certain period of radiation exposure. The results demonstrate that radiation has a positive influence on the material's mechanical performance, particularly in tensile and compression tests, which showed significant improvements. Hardness, ballistic, and density tests indicated more modest but still significant increases. In summary, this study contributes to the understanding of the effects of ionizing radiation on ABS and highlights potential applications in industrial and commercial settings that require greater mechanical strength.
Brazilian Congress on Metrology of Ionizing Radiation (CBMRI)
Latin-American Congress on Solid State Dosimetry and Radiation Measurements (LASSD)
II Simpósio Internacional sobre Protección Radiologica, Cusco (SIPR)
IX Congresso de Proteção Contra Radiações da Comunidade dos Países de Língua Portuguesa (PCR-CPLP)
Copyright (c) 2025 Karine L. Carvalho, Wallace V. Nunes, Ary M. de Azevedo, Paulo C. R. Silveira https://creativecommons.org/licenses/by/4.0