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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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.
International Radiation Protection Association (IRPA)
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.
The Meeting on Nuclear Applications (ENAN)
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
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
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.
International Joint Conference Radio (RADIO)
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)
National Week of Nuclear and Energy Engineering and Radiation Sciences (SENCIR)
Copyright (c) 2025 Karine L. Carvalho, Wallace V. Nunes, Ary M. de Azevedo, Paulo C. R. Silveira https://creativecommons.org/licenses/by/4.0
Calibration Of The Short Irradiation Facility For k0 - NAA Implementation At The IEA-R1 Reactor
The short irradiation facility of the IEA-R1 nuclear research reactor at IPEN, São Paulo, Brazil, has been used for short irradiation of samples for the purpose of determining the concentration of elements of these samples through the use of the instrumental neutron activation analysis technique. With the aim of implementing the k0-NAA method at the Neutron Activation Analysis Laboratory (LAN), the reactor parameters a and f were obtained using the bare triple method. In this method, a set of three neutron flux monitors were irradiated without Cd-cover. The efficiency curve of the gamma-ray spectrometer used was determined by measuring calibrated radioactive sources at the commonly used counting geometries. The results for the parameters a and f were respectively 0.0384±0.0016 and 35.67±0.26. This value of f shows that the neutrons in the irradiation position are well thermalized.The variation of these parameters was studied with time and the reproducibility was verified.
The Meeting on Nuclear Applications (ENAN) 2019
Copyright (c) 2021 Brazilian Journal of Radiation Sciences https://creativecommons.org/licenses/by/4.0
Fabrication and Dosimetric Evaluation of a 3D-Printed Multichannel Cylindrical Applicator Prototype for HDR Gynecological Brachytherapy
High dose-rate (HDR) brachytherapy is widely used in the treatment of gynecological cancers, but the availability of multichannel applicators remains limited in many radiotherapy centers. 3D printing has emerged as a viable alternative for manufacturing customized devices, allowing for optimized dose distribution and reduced exposure to organs at risk. This study aimed to develop and evaluate a 3D-printed multichannel cylindrical applicator for gynecological brachytherapy. The printing material was selected based on its physical properties, followed by an analysis of Hounsfield Units (HU) for different infill percentages and printing patterns. The applicator was printed using polylactic acid (PLA), and different physical and imaging tests were performed. The dose distributions obtained with the 3D-printed multichannel applicator and a single-channel were compared, with focus on target coverage and organ-at-risk exposure. Dosimetric evaluation was performed using Gafchromic® EBT4 film. The results show that the multichannel applicator enabled better dose conformity, reducing rectal exposure compared to the single-channel applicator while maintaining target coverage. Gamma analysis confirmed the accuracy of the calculated dose distribution. 3D printing seems to be a viable alternative to produce customized applicators, potentially expanding therapeutic options in gynecological brachytherapy, however, future studies should investigate the biocompatibility of the material and the clinical feasibility of the applicator.
Copyright (c) 2025 Patrícia Vieira Guimarães, Saulo Santos Fortes, Delano Valdivino Santos Batista, Rechele Grazziotin Reisner https://creativecommons.org/licenses/by/4.0
The Brazilian panorama for the calibration of Y-90 microspheres
The combination therapy approaches are gaining popularity, particularly the radiopharmaceutical therapy with external radiotherapy, immunotherapy or both. Radioembolization using Yttrium-90 Microspheres, SIR-Spheres and TheraSphere, has been used clinically in the treatment of locally advanced and unresectable Hepatic Carcinomas. According to the literature, the standardization of microspheres is not yet well established. In view of the practice of 90Y in therapies in Brazil, it is essential to develop solid standards for its measurement, in order to verify the absorbed radiation dose and its administration to the patient. This paper proposes a study of the existing standardization infrastructure for 90Y microspheres through a literature review and analysis of the measuring instruments available at the National Laboratory for Ionizing Radiation Metrology, a general analysis was made of the spectrometry and calibration methods available in Brazil, specifically at LNMRI, evaluating those suitable for use in the standardization of Yttrium microspheres. The results showed that in the period between 2000 and 2024 90Y was widely cited in treatment by radioembolization with microspheres, qualitative and quantitative evaluation of the activity quantity in PET/CT scans and its metrological characterization involving proficiency tests, study of impurities, standardization by primary and secondary methods
Y-90 microspheres, Radioembolization, Standardization.
Copyright (c) 2025 Thamyra Cybelle Vieira dos Santos, Ms Dayana Azeredo da Conceição, Dr José Ubiratan Delgado https://creativecommons.org/licenses/by/4.0
Automated dose-effect calibration curve for X-rays using the cytokinesis-block micronucleus assay
This article shows the development of a dose–effect calibration curve for X-ray exposures ranging from 0 to 4 Gy using the cytokinesis-block micronucleus assay and automated analysis—the first effort of its kind reported in Latin America. This work establishes a regional benchmark for high-throughput methodologies in cytogenetic biodosimetry, highlighting their potential to improve operational efficiency and reduce response times in radiological emergencies. Methods: Blood samples from six healthy donors were irradiated with X-rays at seven dose levels (0–4 Gy) using a calibrated 6 MV linear accelerator. Two blind samples (1.5 and 3 Gy) were included for validation. The CBMN assay was performed following IAEA protocols, DAPI-stained slides were analyzed using a AxioImager.Z2 automated microscope integrated with MetaSystems Metafer4 and the MNScoreX classifier software. A negative binomial regression model (NB1) was used for model fitting, accounting for overdispersion in micronucleus (MN) frequency. Results: Automated scoring of binucleated lymphocytes showed a dose-dependent increase in MN frequency. The fitted model followed a linear–quadratic relationship: Y = 0.0545 + 0.0448·D + 0.0145·D², with all coefficients statistically significant (p < 0.001). Dose estimates for blinded samples (1.5 and 3 Gy) matched the true doses within 95% confidence intervals, with all z-scores < |3|. Conclusions: The resulting linear–quadratic dose–response curve enabled accurate estimation of blinded sample doses, with all z-scores falling within acceptable fitness-for-purpose thresholds. These results underscore the value of combining automated microscopy with robust statistical modeling to achieve reliable dose assessment, particularly in high-throughput settings and radiological emergency scenarios.
Copyright (c) 2025 Fabio Andrés Chaves-Campos, Fernando Ortíz-Morales, Anthony Cordero-Ramírez, Julián Alonso Gómez-Castro, Jorge Ernesto González-Mesa https://creativecommons.org/licenses/by/4.0
The EDXRF Analysis to Monitor Iron Deficiency Anemia
Iron Deficiency Anemia is a significant global issue, particularly affecting pregnant women and young children. Traditional methods of diagnosing iron-deficiency anemia generally require extensive and costly laboratory procedures. This study explores the feasibility of using portable Energy Dispersive X-ray Fluorescence (EDXRF) technology for assessing iron concentration in whole blood samples from donors diagnosed with iron deficiency anemia. The results indicated a marked decrease in iron levels in the blood samples from patients with anemia compared to the control group. The EDXRF technique demonstrated several advantages, including simplicity in sample collection, rapid measurement time, and low cost. This method is particularly promising for use in situations where biological material is limited, such as in pediatric practices for newborns. The study concludes that portable EDXRF technology is an effective and efficient tool for diagnosing iron deficiency anemia, potentially improving diagnostic accessibility and outcomes.
Copyright (c) 2025 Maria Paula de Oliveira Goes, Cibele Bugno Zamboni, Maria Gabriela Miquelino Benedito, Maria Regina Andrade Azevedo https://creativecommons.org/licenses/by/4.0
Determination of the total retention capacity of 99Mo in anionic extracting agent
The Nuclear Metrology Laboratory (LMN) at IPEN-CNEN/SP is developing a research project aimed at studying analytical techniques for determining radioactive impurities, emitting alpha and beta particles. This project started with the determination of impurities present in 99Mo, which is used to obtain the radiopharmaceutical 99mTc by means of radiochemical separation in the 99Mo/99mTc generator. The study of the anionic extracting agent Strata X-A widely used in quality analysis, was realized by means a breakthrough curve in order to validate its total exchange capacity for Mo. The breaking point was determined at (2.75 +/- 0.14) mL, showing that just one 0.5 g Strata X-A cartridge is sufficient to retain 1.0 mL of a (Na2MoO4+ 99Mo) solution in concentration of 2.42 g L- 1.
Copyright (c) 2025 Ione Makiko Yamazaki, Denise Simoes Moreira, Mauro da Silva Dias, José Antonio Seneda, Marina Fallone Koskinas https://creativecommons.org/licenses/by/4.0
Monte Carlo simulation of a 6 MV Varian Trilogy clinical linear accelerator using Geant4 for small-field dosimetry analysis
In recent decades, radiotherapy has advanced significantly due to the emergence of advanced clinical linear accelerators, enabling safer and faster treatments with reduced side effects. In this study, we present a Monte Carlo simulation of a 6 MV Varian Trilogy clinical linear accelerator using the Geant4 toolkit to analyze dosimetric parameters, with a focus on small photon fields. The simulation models phase-space files generated at key beam-modification stages. Validation was performed by comparing simulated depth dose curves (PDD) and dose profiles with experimental measurements for the 6 MV photon beam, employing the gamma index (3%/3 mm criteria) to quantify the degree of agreement in the PDDs. The results agreed within a 2% difference, with over 95% of points passing the gamma analysis for a 10 x 10 cm² field. The developed framework allows for the calculation of correction factors for small-field dosimetry, addressing challenges such as lateral electronic disequilibrium in high-energy 6 MV beams, and comparing them with established values in the literature. These capabilities are particularly important for measurements of small fields used in advanced radiotherapy techniques, including Stereotactic Radiosurgery (SRS) and Stereotactic Body Radiotherapy (SBRT), where high precision in dose deposition is essential. Overall, this work establishes a robust and flexible Geant4-based platform for simulating clinical linear accelerators, contributing to the development of more accurate dosimetric protocols for high-energy photon therapy in small fields. Preliminary observations suggest notable output factor discrepancies in small photon fields (<3x3 cm2), indicating the potential need for detector-specific correction factors. Ongoing analysis aims to confirm these trends.
Copyright (c) 2025 Andre Luiz de Carvalho Ribeiro, Alex Cristóvão Holanda de Oliveira, Leonardo Peres da Silva, Eduardo De Paiva https://creativecommons.org/licenses/by/4.0
Evaluation of Nuclear Material Balance by Statistical Analysis of the Material Unaccounted For (MUF)
Evaluating the nuclear material balance is an essential tool that can be used to assess the validity of the operator’s declarations of existing quantities of nuclear material from a facility, with an effect on safeguards agreements, where applicable. In summary, evaluating the nuclear material balance and associated safeguards activities enables the national regulatory authority to identify variations that may indicate deviations. A specific strategy used to detect potential deviations from assessing the material balance is known as "diversion into MUF", where MUF refers to the parameter Material Unaccounted For. It represents the difference between the book inventory and the ending physical inventory at the end of the material balance period. This evaluation is conducted through statistical analysis of the standard deviation of the MUF (σMUF) parameter, using an anonymous Brazilian facility as a case study. The ultimate goal is to implement this analysis within Brazil's control and accounting system, known as e-Gamma. This will enable the system to automatically perform such analyses for all facilities nationwide during each accounting period. This statistical study can be a powerful predictor of diversion, utilizing the σMUF parameter as a valuable resource. It is possible to suggest implementing this evaluation in control and accounting systems to increase efficiency in identifying and resolving discrepancies and anomalies, which is of fundamental importance in improving the reliability of a control system within the national scenario. Considering the international scenario, a country that increases its capacity to verify the accounting of nuclear material under its custody will tend to occupy a position of autonomy among its peers.
Copyright (c) 2025 Larissa R. P. Xavier, Luiz Antônio Mello, José Carlos C. Amorim, Jakler Nichele, Edson Ramos 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
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)
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
Ginkgo biloba Extract: A Preliminary Study on Its Radiomitigative Potential Using the Conventional Dicentric Chromosome Assay
Radioprotectors and radiomitigators can be substances of natural or synthetic origin that, once administered to the human body, are capable of preventing, protecting against, or reducing damage caused by radiation. This study aimed to assess the radiomitigating potential of Ginkgo biloba extract by examining the frequency of dicentric chromosomes in irradiated human lymphocytes. Blood samples were obtained from a healthy volunteer. One sample was left in the laboratory as a control, and the others were irradiated in a 60Co source at a dose of 2 Gy and incubated in test concentrations of Ginkgo biloba extract (0.025 and 0.05 μg/ml) according to a standard protocol. Complete metaphases were analyzed, and the frequencies of alterations were statistically evaluated to verify the radiomitigating potential of Ginkgo biloba extract. The ANOVA and Tukey tests revealed a statistically significant difference between the groups treated and untreated with Ginkgo biloba exposed to 2 Gy of radiation (p < 0.05), indicating that both concentrations tested were able to reduce the damage. In this in vitro study, Ginkgo biloba extract was able to reduce the frequency of dicentric chromosomes in irradiated human lymphocytes, with a concentration of 0.025 μg/ml standing out.
Copyright (c) 2025 Julio Cesar Gomes da Silva, CAIO C. V. B. G, MENDES M. E., LOPES I. M. S. S., MELO A. M. M. A, LIMA F. F. https://creativecommons.org/licenses/by/4.0
Optimization of Flight Parameters for Gamma Radiation Detection and Mapping Using Drones
The application of drones in radiometric surveys has emerged as a promising solution, particularly for mapping radiation in areas that are difficult to access. This approach enables the creation of detailed distribution maps. However, the accuracy of the results is strongly influenced by the chosen flight strategy. This study explores how different flight parameters, such as speed and grid spacing, impact the quality of gamma radiation mapping, aiming to optimize the trade-off between measurement precision and operational efficiency, such as flight time and mapping coverage. To achieve this, two experimental flights were conducted using a drone equipped with a Geiger-Müller detector, with a Cs-137 source serving as a reference. The methodology involved continuous radiation measurements during flight, with data collected at predetermined points arranged in a structured grid, via GPS coordinates. This setup facilitated the development of a three-dimensional representation of the gamma dose distribution. By comparing the results of both flights, each configured with distinct operational settings, it was possible to evaluate the impact of flight parameters on the effectiveness of radiometric detection of dose rate distribution using drones. The results suggest that dose rate mapping tends to achieve higher resolution when lower flight speeds are adopted and when data collection points are more densely distributed across the surveyed area.
Copyright (c) 2025 Felipe Mamed, Alessandra Vaz, Ary Machado, Jonathan Oliveira, Leandro Silva, Paulo Barreto, Paulo Iack, Paulo Silveira, Rodrigo Curzio, Rodrigo Souza, Wallace Vallory https://creativecommons.org/licenses/by/4.0
Image quality and dose reduction in cardiac interventional procedures: application of an optimization strategy with typical dose value analysis
This study aimed to evaluate the impact of dose‑optimization strategies on radiation exposure during cardiac catheterization and angioplasty procedures. The investigation was carried out at a high‑complexity referral center using retrospective data, clinical‑protocol adjustments, and image‑quality assessments with dedicated simulators. Implemented measures included reducing the cine dose per frame and enabling post‑processing filters, resulting in reductions of up to 39 % in reference‑point kerma and 25 % in noise intensity under low‑dose conditions. In total, 714 procedures performed over five semesters were analyzed. Diagnostic reference levels (DRLs) were determined and compared with data from national and international literature. A statistically significant reduction in DAP (16.3 %) and Kₐ,r (12.8 %) was observed for catheterization procedures (p < 0.05). Although angioplasty procedures showed a similar trend, case variability limited statistical significance. The results demonstrate the effectiveness of technical interventions and continuous monitoring in lowering exposure levels, without compromising diagnostic image quality.
Copyright (c) 2025 Murilo Felisberto Morais de Assunção, Emerson Nobuyuki Itikawa, Jonas Oliveira da Silva, Guilherme Custódio Cândido Silva https://creativecommons.org/licenses/by/4.0
In vivo monitoring in radiological or nuclear emergencies: a program for intercomparison of detection efficiency in NaI(Tl) portable detectors
In vivo internal monitoring is a laboratory technique used to assess and quantify the incorporation of radionuclides in the human body. Demand for such services may increase significantly in a radiological or nuclear emergency. In addition to dedicated laboratories, researchers have proposed the calibration of portable gamma radiation detectors to carry out a rapid screening of exposed individuals and assess internal dosimetry. Several international intercomparison exercises have been conducted to evaluate the performance of detectors specifically designed for internal monitoring, including, more recently, NaI(Tl) portable detectors. However, these experimental intercomparison exercises have included the transport of radioactive sources between participating institutions. The aim of this study is to propose a simple methodology for determining a reference value for the NaI(Tl) detector efficiency at 662 keV (137Cs), supporting future exercise efforts. This work employed NaI(Tl) scintillator detectors and a torso phantom. It was possible to determine an optimized measurement geometry through simulation using the MCNPX mathematical code, especially regarding the distances, and to estimate efficiency values with defined acceptance intervals for the proposed intercomparison exercise. However, additional experiments are needed to define these intervals more precisely. Complementarily, the minimum detectable effective doses were approximately 60 µSv and 38 µSv for the NaI(Tl) 2’’×2’’ and 3’’×1.5’’ detectors, respectively.
Copyright (c) 2025 MSc. Alexandre Barbosa Soares, Dr. José Ubiratan Delgado, Dr. Alfredo Lopes Ferreira Filho, Gabriel Flintz Fraga Marques https://creativecommons.org/licenses/by/4.0
Legislation and Regulations Regarding the Use of Ionizing Radiation in Phytotherapeutics in Brazil: A Documentary Analysis
This study aimed to conduct a documentary analysis of federal legislation and regulations in Brazil regarding the irradiation of phytotherapeutic products. The research was carried out between April and June 2024 through a review of official documents, including regulations, resolutions, constitutional amendments, and decrees published between 1983 and 2018. Although the analysis revealed the existence of specific norms and resolutions related to food irradiation, no direct regulation concerning the use of ionizing radiation in phytotherapeutics was identified in Brazil. National legislation addresses the use of ionizing radiation in food, particularly for radio-sterilization, with emphasis on RDC No. 21/2001, which may be indirectly applicable to medicinal plants. Normative Instruction No. 44/2014 provides the most relevant guidelines regarding the application of ionizing radiation in pharmaceuticals. In contrast, international legislation—such as that from the FDA (USA) and FSSAI (India)—explicitly regulates the radio-sterilization of medicinal herbs and plants. The documentary analysis highlights the need for the expansion, regulation, and harmonization of Brazilian standards and protocols to ensure the safe application of ionizing radiation in phytotherapeutics.
Copyright (c) 2025 Diniz, E. C., Neto, L. S. M., Silva, M. M., Amaral, A., Magnata, S. S. L. P., Araújo, L. A,, Netto, A. M., Silva, E. B. https://creativecommons.org/licenses/by/4.0
Use of Lymphoscintigraphy Images in Nuclear Medicine to Obtain the Distribution of 99mTc Photons in Computational Exposure Models
This study aims to create a source catalog for Lower Limb Lymphoscintigraphy (LLL) examinations in Nuclear Medicine, using real lymphoscintigraphy images from adult male patients. The DIP (Digital Image Processing) software, developed by the Research Group on Computational Dosimetry and Embedded Systems (GPDC&SE), was used to adjust the anteroposterior (AP) and posteroanterior (PA) medical images to the frontal section of the anthropomorphic phantom MASH_sup (Male Adult meSH in supine position). The images were summed line by line, generating a .SGI file, which was processed by the Monte Carlo software to produce the source catalog stored in the file MSUPLC_TC99m.txt. This file contains information for each slice, including the slice number, the area of the source points, and the value of the associated cumulative distribution function (CDF). As a result, a catalog based on real clinical data was successfully generated, which enables the replacement of generic internal sources in the Computational Exposure Models of the GPDC&SE. This makes it possible to simulate LLL examinations more realistically. In the future, this methodology may be extended to female patients, different phantoms, and other scintigraphic procedures. This work represents an advancement in computational dosimetry and personalized nuclear medicine, as it enables simulations that more accurately reflect patient-specific anatomical and physiological characteristics.
Copyright (c) 2025 Jorge Alexandre Gomes Lins, José Wilson Vieira, Fernando Roberto de Andrade Lima, Whoody Alem Wanderley Araripe Farias , Victor Hugo Farias Ferreira da Silva; João Mário da Silva; Ferdinand de Jesus Lopes Filho, Jefferson Melo Gonçalves Pena, Larissa Cristina Silva dos Santos https://creativecommons.org/licenses/by/4.0
Detection of Cosmic Radiation at Low Doses: Integrative Review of Biodosimetric Methodologies with Proposition of Aerospace Evaluation Index
Galactic cosmic radiation (GCR) is the major risk in long-duration spaceflight when considering biological damage. Hence, monitoring the absorbed dose is required and biodosimetry will be considered an important tool especially in scenarios where physical dosimetry does not work. This integrative review tries to find, analyze, and compare different biodosimetric techniques capable of recording low doses of ionizing radiation (≤ 0.1 Gy) under simulation of spatial environments with respect to their operational applicability. The Aerospace Biodosimetric Performance Index is introduced to integrate the main parameters of the analysis. All results came from original articles in English available in open access published between 2019 and 2024 according to a PRISMA 2020 flowchart found in Scopus and PubMed databases and only eight studies were considered eligible for inclusion after performing a primary screening using Rayyan app. The major biodosimetric approaches recognized in the investigation are cytogenetic, molecular, and metabolic. The analysis time in the methodologies was between 2 and 70 hours, sample viability from 1 day to 2 years, and sensitivity as low as 0.05 Gy for the minimum detectable dose in some methods. The Yeast Metabolic Assay showed good applicability by combining high sensitivity with quick analysis and long viability. However, an absence of studies combining space radiation with microgravity constituted a major drawback. While many methodologies show detection capabilities at very low dose levels, few of them meet both the technical and operational requirements when considered together for prolonged space missions, hence a development challenge for hybridized yet more robust methods.
Copyright (c) 2025 Paulo Sérgio de Abreu Junior, Ricardo Felipe Soares, Thaís Soares Costa, Felipe L. Frigi, Liana Kalczuk, Priscila Correia Fernandes, Claudio Antonio Federico https://creativecommons.org/licenses/by/4.0
Understanding and enhancing nuclear safety culture in nuclear power plants through a quantitative system dynamics model
This study presents a quantitative system dynamics model developed to understand and enhance nuclear safety culture and operational performance in nuclear power plants. The model employs causal loop diagrams and stock-and-flow diagrams, created using Vensim PLE+ software, to capture and simulate the complex interactions that define safety culture dynamics. Recognizing the fundamental role of organizational culture in maintaining nuclear safety, the model incorporates key elements such as leadership, risk perception, continuous improvement, internal communication, and the commitment of management and personnel. Through an extensive literature review and expert consultations, the research integrates critical variables into the model, grounded in frameworks from the International Atomic Energy Agency (IAEA) and the World Association of Nuclear Operators (WANO). Simulating a decade of safety culture management dynamics, the model reveals the impact of management strategies, demonstrating the effectiveness of continuous improvement initiatives and proactive leadership in enhancing safety outcomes. Stress tests conducted under extreme scenarios validated the model's robustness, reaffirming its applicability in safeguarding safety culture under intensified production pressures. The findings provide actionable insights for nuclear safety professionals and decision-makers, promoting environments that support safety-focused practices. This model serves as a comprehensive tool to advance safety culture in nuclear operations, offering valuable perspectives for both theoretical discourse and practical nuclear safety management.
causal loop diagram and stock-and-flow diagrams
Copyright (c) 2025 Santiago Gregorio Acuña, Marcelo Oscár Gim´enez, Mariela Grinberg, Ochuko Felix Orikpete, Warren Farr https://creativecommons.org/licenses/by/4.0
Reality of radiological examinations with patients with physical limitations
This article discusses the problems faced in daily hospital and clinical practice in Brazil, where there are no examination protocols or bibliographies that professionals can use as a basis for performing radiological examinations on patients with movement limitations and clinical conditions, such as paraplegia and tetraplegia. The objective of this study was to develop a booklet of adaptations of radiological positions for patients with reduced mobility. This material can improve and optimize the services provided in the area, offering greater radiological safety to both the professional and the patient during the examinations. The methodology used involved national bibliographic reviews, technical visits and hospital monitoring, as well as discussions with professionals specialized in the area of ​​radiology, in order to consolidate a more concrete and specific basis for the studied content. Based on these data, it was possible to formalize a simplified booklet, in Portuguese and English versions, accessed through specific QR Codes. The booklet includes some adaptations of radiological examination positions for patients with physical limitations or reduced mobility. The booklet contains a didactic structure for quick consultation to better guide the professional regarding the performance of the examinations. It contains a cover, a presentation, a summary, an introduction, a summary of conventional exams, the adaptation of exams, the conclusion and finally the references. The conclusion of the study emphasizes the importance of expanding research aimed at adapting radiological exams for patients with physical limitations or reduced mobility. These adaptations aim not only at the well-being of the patient, but also at the health, radiological protection and ergonomic safety of professionals, avoiding injuries during the conduct of the exam or its repetition. It is hoped that this material can provide a more humanized environment for both patients and professionals.
Adaptations of radiological exams for patients with reduced mobility
Booklet for patients with physical limitations
Adaptações de exames radiológicos para pacientes com mobilidade reduzida
Adaptations des examens radiologiques pour les patients à mobilité réduite
Adaptaciones de las exploraciones radiológicas para pacientes con movilidad reducida
Adaptations of radiological examinations for patients with reduced mobility
Copyright (c) 2025 Dra. Kátia Elisa Prus Pinho , Dra. Rita Zanlorensi Visneck Costa , Roberta Aumann, Dr. João Henrique Hamann 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
Common onion extract (Allium cepa): radioprotective or radiosensitizing?
Currently, ionizing radiation has been used on a large scale in different areas of knowledge. However, despite the existence of several radioprotection regulations for workers, patients and members of the public, these are not sufficient to completely limit the possible harmful effects of ionizing radiation. For this reason, there is currently an interest in finding radiomodifying substances with radioprotective or radiomitigating activity. It is reported that approximately half of all cancer patients will require radiotherapy. Therefore, as a means of radioprotection, the use of radioprotective compounds is essential to preserve healthy cells from radiation-induced damage. Among these agents, the literature highlights natural compounds and extracts, one of which is Allium cepa, commonly known as "onion"—a plant with medicinal potential, as well as antitumoral and antioxidant properties. However, no studies have reported the application of onion extract as an antioxidant and radioprotective agent in mammalian cells. Thus, it is necessary to confirm the antioxidant and radioprotective capabilities of A. cepa extract in human lymphocytes, particularly for planned exposures to ionizing radiation. Accordingly, the aqueous extract of A. cepa bulbs was subjected to cell viability testing (MTT assay) and antioxidant capacity evaluation (ABTS and DPPH assays). Subsequently, in the presence of the extract, the micronucleus assay was performed in lymphocytes exposed to three absorbed radiation doses (ranging from 0.5 to 4 Gy). The results demonstrated that, depending on the radiation dose and extract concentration, A. cepa extract influences the formation of micronuclei. At the dose of 0.5 Gy, no statistically significant difference was observed between irradiated groups treated or not treated with the extract. At 2 Gy, an increase in micronucleus frequency was observed in the presence of the extract, whereas at 4 Gy, the opposite effect was noted. Our findings suggest that A. cepa extract is a compound with potential applications in the field of health-related radiation exposure, exhibiting dual behavior depending on its concentration and the radiation dose. These results pave the way for further investigations, involving new extract concentrations, different absorbed radiation doses, and individual variability.
Copyright (c) 2025 Dra. Raquel Cordeiro de Oliveira, Evelin Mirelle Lima Araújo, Dr. Osana Diniz Ferreira, Dra. Suy Ferreira Hwang, Dra. Ana Maria Mendonça Albuquerque de Melo, Dra. Mariana Esposito Mendes, Dr. Thiago Henrique Napoleão, Dra. Fabiana Farias de Lima https://creativecommons.org/licenses/by/4.0
Analysis of the Relationship Between Absorbed Dose and Its Effect on Plant Materials: A Literature Review
Gamma radiation has been widely explored as a physical elicitor capable of modifying plant metabolism. Its influence on the biosynthesis of secondary metabolites, which play key roles in defense, adaptation, and therapeutic action, has gained increasing interest in phytochemical and pharmacological research. This study aimed to systematically review the effects of gamma radiation on plant-derived secondary metabolites, highlighting dose-response relationships and potential biotechnological applications. A literature review was conducted using PubMed, SciELO, and BVS databases, focusing on studies published between 2019 and 2024. The search strategy included descriptors such as "gamma radiation," "secondary metabolites," and "plant materials." After applying eligibility criteria, 23 studies were selected. The studies revealed that gamma irradiation influences a wide range of secondary metabolites, including phenolics, flavonoids, terpenes, alkaloids, and saponins. Most results indicate that doses (5–100 Gy) tend to enhance the synthesis of bioactive compounds with antioxidant, antimicrobial, and anticancer properties. However, higher doses often lead to inhibitory or toxic effects. The response varied significantly across plant species and compound classes. Gamma irradiation presents great potential to optimize the production of high-value phytochemicals for therapeutic use. Nevertheless, the absence of standardized dose-response profiles and the limited understanding of molecular mechanisms highlight the need for further multidisciplinary research to ensure the safe and effective application of this technology in phytopharmaceutical development.
Copyright (c) 2025 Mario Mardone da Silva, Ewerton Clementino Diniz, Luiz da Silva Maia Neto, Liderlanio de Almeida Araújo, Simey de Souza Leão Pereira Magnata, Ademir de Jesus Amaral, Andre Maciel Netto, Edvane Borges da Silva https://creativecommons.org/licenses/by/4.0
Two-dimensional radiometric map of environmental radiation levels in a nuclear medicine service
Nuclear Medicine in Brazil has shown significant growth, with approximately 2 million procedures performed annually across 436 facilities. Ensuring that radiation exposure remains within safe limits is critical to protect patients and staff, making radiometric surveys an essential part of safety protocols. This study investigated the distribution of radiation in a nuclear medicine service in Florianópolis, Santa Catarina, using biweekly measurements collected between 2021 and 2023. A total of 2,000 samples were gathered at 40 points using a Geiger-Müller detector. The data were analyzed and mapped onto the facility’s floor plan using Paint and Excel software to generate a radiometric map. The results identified areas with elevated radiation levels and notable regional differences. The highest exposure rates were found primarily in the radiopharmacy—where radioactive materials are handled, stored, and prepared—and in radiopharmaceutical administration rooms. This radiometric map proved effective in guiding radiological protection measures and highlights the importance of continuous radiation monitoring in clinical nuclear medicine environments.
Copyright (c) 2025 Maria Eduarda Santos, Tatiane Sabriela Camozzato, Lucas Faconi Camargo https://creativecommons.org/licenses/by/4.0