Pub Date : 2023-07-25DOI: 10.15392/2319-0612.2023.2272
Fernando Barcellos Razuck, A. A. D. Silva, Danielle Monegalha Rodrigues, Gisele Valente Cavalcante, M. E. D. Acar, Pamela Rodrigues Perrotta, Paulo Fernandes de Jesus, M. Wasserman
The Institute of Radiation Protection and Dosimetry (IRD) is a research and development institution, linked to the Brazilian Nuclear Energy Commission (CNEN), with a tradition of training human resources in the areas of radiation protection, dosimetry, medical physics and metrology of ionizing radiation. Despite this relevance, the IRD has suffered loss of its intellectual capital, mainly due to retirements and lack of replacement of qualified personnel. Thus, it is extremely important to preserve the technical-scientific knowledge related to its activities. A methodology that can help in this process is knowledge management (KM), in view of its potential to generate benefits in public and private organizations. Therefore, this work aims to carry out an experience report of the process of implementing KM at IRD, which used as a theoretical reference the models applied by the International Atomic Energy Agency (IAEA). Initial results include the creation of the working group on KM, the diagnosis of critical knowledge and maturity, the Knowledge Management Assistance Visit (KMAV) by IAEA and the production of papers. In addition, the support of the IRD's top management should be highlighted, which has made it possible to carry out activities related to the implementation and effectiveness of KM. Thus, it is intended to expand KM activities in the IRD, such as the execution of projects and the offer of training in the area.
{"title":"The implementation process of knowledge management at the Institute of Radiation Protection and Dosimetry: actions and perspectives","authors":"Fernando Barcellos Razuck, A. A. D. Silva, Danielle Monegalha Rodrigues, Gisele Valente Cavalcante, M. E. D. Acar, Pamela Rodrigues Perrotta, Paulo Fernandes de Jesus, M. Wasserman","doi":"10.15392/2319-0612.2023.2272","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2272","url":null,"abstract":"The Institute of Radiation Protection and Dosimetry (IRD) is a research and development institution, linked to the Brazilian Nuclear Energy Commission (CNEN), with a tradition of training human resources in the areas of radiation protection, dosimetry, medical physics and metrology of ionizing radiation. Despite this relevance, the IRD has suffered loss of its intellectual capital, mainly due to retirements and lack of replacement of qualified personnel. Thus, it is extremely important to preserve the technical-scientific knowledge related to its activities. A methodology that can help in this process is knowledge management (KM), in view of its potential to generate benefits in public and private organizations. Therefore, this work aims to carry out an experience report of the process of implementing KM at IRD, which used as a theoretical reference the models applied by the International Atomic Energy Agency (IAEA). Initial results include the creation of the working group on KM, the diagnosis of critical knowledge and maturity, the Knowledge Management Assistance Visit (KMAV) by IAEA and the production of papers. In addition, the support of the IRD's top management should be highlighted, which has made it possible to carry out activities related to the implementation and effectiveness of KM. Thus, it is intended to expand KM activities in the IRD, such as the execution of projects and the offer of training in the area.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72836538","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-24DOI: 10.15392/2319-0612.2023.2254
Arthur Dantas Mangussi, T. Pianoschi, Bernardo Cecchetto, V. Botelho
Objective: AQMI - “Assessment of the quality of mammographic images” was developed to support the quality control (QC) of digital mammographic images. Materials and Methods: The software was implemented in the Python programming language via the Streamlit library, which involved content structuring and environmental planning. The experimental data that were selected from a public domain repository [19]. From the selected database, relevant information that was present in the DICOM file was studied to perform the image quality test. Then, from searching the literature, indicators that measure image quality were found, such as the signal-to-noise ratio, the contrast-to-noise ratio, figure of merit and image histogram. Results: AQMI assists in analyzing the image quality test established in IN 92 by the Agência Nacional de Vigilância Sanitária [8]. It also has quality addition indicators, trend graphs, and the image assessment history. Conclusion: For the functionalities of this work, the developed software is a promising tool for use in clinical practice, since it consists of a free, friendly, and easy-to-use interface.
目的:为支持数字化乳房x线影像的质量控制(QC)，开发AQMI -“乳房x线影像质量评估”。材料和方法:软件采用Python编程语言，通过Streamlit库实现，涉及内容构建和环境规划。实验数据选自公共领域存储库[19]。从选定的数据库中，研究DICOM文件中存在的相关信息，以执行图像质量测试。然后，通过文献检索，找到衡量图像质量的指标，如信噪比、对比噪比、优值和图像直方图。结果:AQMI协助分析了Agência national de vigilicia Sanitária在1992年建立的图像质量测试[8]。它还具有质量添加指标，趋势图和图像评估历史。结论:就本工作的功能而言，所开发的软件具有免费、友好和易于使用的界面，是一种有希望用于临床实践的工具。
{"title":"AQMI: Software for assessing the quality of mammographic images","authors":"Arthur Dantas Mangussi, T. Pianoschi, Bernardo Cecchetto, V. Botelho","doi":"10.15392/2319-0612.2023.2254","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2254","url":null,"abstract":"Objective: AQMI - “Assessment of the quality of mammographic images” was developed to support the quality control (QC) of digital mammographic images. Materials and Methods: The software was implemented in the Python programming language via the Streamlit library, which involved content structuring and environmental planning. The experimental data that were selected from a public domain repository [19]. From the selected database, relevant information that was present in the DICOM file was studied to perform the image quality test. Then, from searching the literature, indicators that measure image quality were found, such as the signal-to-noise ratio, the contrast-to-noise ratio, figure of merit and image histogram. Results: AQMI assists in analyzing the image quality test established in IN 92 by the Agência Nacional de Vigilância Sanitária [8]. It also has quality addition indicators, trend graphs, and the image assessment history. Conclusion: For the functionalities of this work, the developed software is a promising tool for use in clinical practice, since it consists of a free, friendly, and easy-to-use interface.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87806288","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-21DOI: 10.15392/2319-0612.2023.2194
Ângela Moreira Marques dos Santos, R. Sebastião, A. Z. Mesquita, T. Alonso, A. Mantuano, T. Fonseca
Conventional Fricke is an aqueous ferrous sulfate solution that has been widely studied in the field of chemical dosimetry. The feasibility of its use has become attractive for high dose measurements that are of clinical interest in the field of radiotherapy and for industrial purposes, in the irradiation of blood bags and the sterilization of surgical material. The derivation of the absorbed dose of Fricke depends on the radiation-induced oxidation of iron (II) ions (Fe2+) present in the aqueous solution to iron (III) ions (Fe3+), which occurs after exposure to ionising radiation. In this paper, it is proposed to evaluate the dose response of the Fricke dosimeter using two different analytical techniques, ultraviolet-visible spectrophotometry (UV-Vis) and nuclear magnetic resonance spectroscopy (NMR). Twelve groups of samples were analysed in triplicate, irradiated with doses between 0 and 800 Gy, using a cobalt-60 source (60Co). The dose rate of Fricke dosimeters was evaluated against the practical values obtained. The different methods allowed an analytical correlation of the species of oxidised iron (Fe3+) using a linearity curve as a function of the applied radiation dose.
{"title":"Dose response assessment of conventional Fricke: a relationship between UV-Visible and nuclear magnetic resonance techniques","authors":"Ângela Moreira Marques dos Santos, R. Sebastião, A. Z. Mesquita, T. Alonso, A. Mantuano, T. Fonseca","doi":"10.15392/2319-0612.2023.2194","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2194","url":null,"abstract":"Conventional Fricke is an aqueous ferrous sulfate solution that has been widely studied in the field of chemical dosimetry. The feasibility of its use has become attractive for high dose measurements that are of clinical interest in the field of radiotherapy and for industrial purposes, in the irradiation of blood bags and the sterilization of surgical material. The derivation of the absorbed dose of Fricke depends on the radiation-induced oxidation of iron (II) ions (Fe2+) present in the aqueous solution to iron (III) ions (Fe3+), which occurs after exposure to ionising radiation. In this paper, it is proposed to evaluate the dose response of the Fricke dosimeter using two different analytical techniques, ultraviolet-visible spectrophotometry (UV-Vis) and nuclear magnetic resonance spectroscopy (NMR). Twelve groups of samples were analysed in triplicate, irradiated with doses between 0 and 800 Gy, using a cobalt-60 source (60Co). The dose rate of Fricke dosimeters was evaluated against the practical values obtained. The different methods allowed an analytical correlation of the species of oxidised iron (Fe3+) using a linearity curve as a function of the applied radiation dose.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82633780","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-20DOI: 10.15392/2319-0612.2023.2193
Nalber Miranda Leite, C. D. O. Lira, A. Rodríguez
Wax deposition along the extensive oilfield pipelines is a problem that affects the flow assurance. To solve it, one must monitor the wax formation in its initial stage. In this light, nuclear techniques are an effective alternative solution, as they can detect characteristics of materials or substances in an indirect and non-invasive manner. The present work shows a computational model using the MCNP6 (Monte Carlo N-Particle 6) code and the gamma radiation transmission profiling technique to detect different wax thickness. This fact is directly related to the attenuation of the gamma radiation beam when crossing the wax thicknesses.
{"title":"Computational analysis for wax detection in deepwater pipelines using nuclear techniques","authors":"Nalber Miranda Leite, C. D. O. Lira, A. Rodríguez","doi":"10.15392/2319-0612.2023.2193","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2193","url":null,"abstract":"Wax deposition along the extensive oilfield pipelines is a problem that affects the flow assurance. To solve it, one must monitor the wax formation in its initial stage. In this light, nuclear techniques are an effective alternative solution, as they can detect characteristics of materials or substances in an indirect and non-invasive manner. The present work shows a computational model using the MCNP6 (Monte Carlo N-Particle 6) code and the gamma radiation transmission profiling technique to detect different wax thickness. This fact is directly related to the attenuation of the gamma radiation beam when crossing the wax thicknesses.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76345551","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-19DOI: 10.15392/2319-0612.2023.2212
E. W. Martins, M. Potiens
The activimeter calibration has the purpose of ensure greater reliability in measurement results, hence the activimeters used are commonly installed in controlled areas and, in some cases, with difficult access. The activimeter “in situ” calibration methodology presented in this work allows its execution only with the displacement of the radioactive samples and not of the activimeter itself, which simplifies the procedure of nuclear medicine services and at radiopharmaceuticals production centers, without affecting the quality and accuracy of measurements. After the application of the methodology by qualified technicians, the obtained results of the tested activimeters showed its importance since the calibration factors can present correction of up to 5% for 111In and greater than 5% for 123I.
{"title":"Activimeter “in situ” calibration methodology to 111In and 123I","authors":"E. W. Martins, M. Potiens","doi":"10.15392/2319-0612.2023.2212","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2212","url":null,"abstract":"The activimeter calibration has the purpose of ensure greater reliability in measurement results, hence the activimeters used are commonly installed in controlled areas and, in some cases, with difficult access. The activimeter “in situ” calibration methodology presented in this work allows its execution only with the displacement of the radioactive samples and not of the activimeter itself, which simplifies the procedure of nuclear medicine services and at radiopharmaceuticals production centers, without affecting the quality and accuracy of measurements. After the application of the methodology by qualified technicians, the obtained results of the tested activimeters showed its importance since the calibration factors can present correction of up to 5% for 111In and greater than 5% for 123I.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89621616","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-14DOI: 10.15392/2319-0612.2023.2220
Larissa Cristina Silva dos Santos, J. W. Vieira, F. Lima, A. C. H. Oliveira
Due to its vast number of occurrences, cancer has caused an economic impact on the public and supplementary health care sectors. It is estimated that more than 50% of patients diagnosed with malignant neoplasms need radiotherapy at some stage of their treatment, most of them treated with photon and/or electron beams. Due to the build-up effect (increase in dose in the matter from deposition on the surface to a point of maximum dose) caused by the interaction of photon beams with the irradiated tissue, bolus is often used in routine radiotherapy sectors to superficialize the point of maximum dose in the treatment region. The human body has complex surfaces that are often treatment regions in radiotherapy, but commercial bolus with a standard shape and length do not adapt perfectly to these surfaces. When this happens, air gaps may appear in the region, causing differences between the dose defined in radiotherapy planning and the dose delivered during treatment. In order to eliminate these air gaps and possible dose distribution errors, two methodologies for individualized bolus construction were proposed. In both cases, computed tomography images of the Alderson Rando male anthropomorphic phantom were used as a reference of the anatomy of a human body. From these images, one bolus model was constructed in the 3D modeling software 3ds Max by creating a polygonal mesh, while the other bolus model was constructed in the image computing software 3D Slicer, using segmentation tools. The software Creality Slicer 1.2.3. prepared the files for 3D printing. The prints of the files were made on polylactic acid filament on the Tevo Tarantula Pro printer. The bolus construction methodology using the software 3ds Max showed better results, as a greater contact area between the bolus and the phantom was observed when testing the fit of the printed bolus to the physical phantom. The 3D files of the virtual bolus will be available for future computer simulations. The printed bolus could be used in dosimetry with linear accelerators.
{"title":"3D modeling of bolus for producing by prototyping and use in radiation therapy","authors":"Larissa Cristina Silva dos Santos, J. W. Vieira, F. Lima, A. C. H. Oliveira","doi":"10.15392/2319-0612.2023.2220","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2220","url":null,"abstract":"Due to its vast number of occurrences, cancer has caused an economic impact on the public and supplementary health care sectors. It is estimated that more than 50% of patients diagnosed with malignant neoplasms need radiotherapy at some stage of their treatment, most of them treated with photon and/or electron beams. Due to the build-up effect (increase in dose in the matter from deposition on the surface to a point of maximum dose) caused by the interaction of photon beams with the irradiated tissue, bolus is often used in routine radiotherapy sectors to superficialize the point of maximum dose in the treatment region. The human body has complex surfaces that are often treatment regions in radiotherapy, but commercial bolus with a standard shape and length do not adapt perfectly to these surfaces. When this happens, air gaps may appear in the region, causing differences between the dose defined in radiotherapy planning and the dose delivered during treatment. In order to eliminate these air gaps and possible dose distribution errors, two methodologies for individualized bolus construction were proposed. In both cases, computed tomography images of the Alderson Rando male anthropomorphic phantom were used as a reference of the anatomy of a human body. From these images, one bolus model was constructed in the 3D modeling software 3ds Max by creating a polygonal mesh, while the other bolus model was constructed in the image computing software 3D Slicer, using segmentation tools. The software Creality Slicer 1.2.3. prepared the files for 3D printing. The prints of the files were made on polylactic acid filament on the Tevo Tarantula Pro printer. The bolus construction methodology using the software 3ds Max showed better results, as a greater contact area between the bolus and the phantom was observed when testing the fit of the printed bolus to the physical phantom. The 3D files of the virtual bolus will be available for future computer simulations. The printed bolus could be used in dosimetry with linear accelerators.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74005515","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-12DOI: 10.15392/2319-0612.2023.2221
William Henrique Silva Profeta, Otto Haubrich, Jonnathan Toshio Ogihara, Gabriel Garro Gomes Fontes, Itamar Arnaldo Tororó Pereira, Ari Machado de Azevedo, J. Soares, Edson Ramos de Andrade, D. O. Cardoso
The objective of this paper was the radiometric survey at the Materials Engineering Laboratory of the Military Institute of Engineering, in Rio de Janeiro, Brazil. Properties of materials are analyzed in this laboratory using X-rays machines. For the development of that work, two scintillator detectors were used with their associated electronics. Detector “A” has NaI(Tl) as scintillator material and detector “B” has CeBr3. In addition to verifying whether the measured dose rate is in accordance with that provided by the CNEN standard, a comparison was made between the efficiencies of these radiation detection equipment.
{"title":"Radiometric survey in microscopy laboratory","authors":"William Henrique Silva Profeta, Otto Haubrich, Jonnathan Toshio Ogihara, Gabriel Garro Gomes Fontes, Itamar Arnaldo Tororó Pereira, Ari Machado de Azevedo, J. Soares, Edson Ramos de Andrade, D. O. Cardoso","doi":"10.15392/2319-0612.2023.2221","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2221","url":null,"abstract":"The objective of this paper was the radiometric survey at the Materials Engineering Laboratory of the Military Institute of Engineering, in Rio de Janeiro, Brazil. Properties of materials are analyzed in this laboratory using X-rays machines. For the development of that work, two scintillator detectors were used with their associated electronics. Detector “A” has NaI(Tl) as scintillator material and detector “B” has CeBr3. In addition to verifying whether the measured dose rate is in accordance with that provided by the CNEN standard, a comparison was made between the efficiencies of these radiation detection equipment.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80022953","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-11DOI: 10.15392/2319-0612.2023.2250
Augusto Elizandro de Aguiar, R. G. Cabral, C. L. Oliveira, S. O. Vellozo
Mathematical tools for calculating radiation shielding usually have difficult notations that could only be solved by computational methods. The Albedo’s method applied for calculation of shielding proves to be an excellent substitute in determining the incident beam fractions that are reflected, absorbed and transmitted, avoiding the use of the transport equation and diffusion approximation that are extremely important in nuclear reactor designs and irradiation calculations. Based on the simple following of the radiation current path, the method can be characterized as a graphical and analytical solution. This work explores the Albedo’s Method applied to 4-slab shielding with incidence of gamma radiation to an energy group compared to ANISN, computational method consecrated in the area of nuclear calculations.
{"title":"Albedo method applied for gamma radiation shielding","authors":"Augusto Elizandro de Aguiar, R. G. Cabral, C. L. Oliveira, S. O. Vellozo","doi":"10.15392/2319-0612.2023.2250","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2250","url":null,"abstract":"Mathematical tools for calculating radiation shielding usually have difficult notations that could only be solved by computational methods. The Albedo’s method applied for calculation of shielding proves to be an excellent substitute in determining the incident beam fractions that are reflected, absorbed and transmitted, avoiding the use of the transport equation and diffusion approximation that are extremely important in nuclear reactor designs and irradiation calculations. Based on the simple following of the radiation current path, the method can be characterized as a graphical and analytical solution. This work explores the Albedo’s Method applied to 4-slab shielding with incidence of gamma radiation to an energy group compared to ANISN, computational method consecrated in the area of nuclear calculations.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88420568","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-10DOI: 10.15392/2319-0612.2023.2207
Cibele Bugno Zamboni, Dalton Nogueira da Silva Giovanni, Mateus Ramos de Almeida, Alberto Sabino Todo, Fabio Sabará Dias, Orlando Rodrigues Junior
In this investigation, the elements Ca and S were evaluated in a single nail clipping using compact and portable X-ray spectrometer model X-123 SDD with Ag target. Experimental conditions for current, voltage and excitation time were investigated. These analyses can be useful for a variety of applications, including nutritional and medical diagnosis, such as, the evaluation of bone dysfunctions by measurement of Ca (bone decalcification) and S for nutrition evaluations (collagen production). This analysis offers some benefits comparatively to blood and serum analyses, such as, non-invasive collection, fast analyses (minutes) and low cost. In addition, nail clippings are simple to obtain, easy to store, and easy to transport. This pilot study show a positive expectation for clinical application using in-vitro nail test.
{"title":"X- ray experimental set-up for in-vitro nail test","authors":"Cibele Bugno Zamboni, Dalton Nogueira da Silva Giovanni, Mateus Ramos de Almeida, Alberto Sabino Todo, Fabio Sabará Dias, Orlando Rodrigues Junior","doi":"10.15392/2319-0612.2023.2207","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2207","url":null,"abstract":"In this investigation, the elements Ca and S were evaluated in a single nail clipping using compact and portable X-ray spectrometer model X-123 SDD with Ag target. Experimental conditions for current, voltage and excitation time were investigated. These analyses can be useful for a variety of applications, including nutritional and medical diagnosis, such as, the evaluation of bone dysfunctions by measurement of Ca (bone decalcification) and S for nutrition evaluations (collagen production). This analysis offers some benefits comparatively to blood and serum analyses, such as, non-invasive collection, fast analyses (minutes) and low cost. In addition, nail clippings are simple to obtain, easy to store, and easy to transport. This pilot study show a positive expectation for clinical application using in-vitro nail test.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85449449","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-07-07DOI: 10.15392/2319-0612.2023.2148
Fernando Barcellos Razuck, Raul A. C. dos Santos, Paulo Escarani
In a world where information has a high speed of propagation and is present in the most diverse media, it is essential to follow the news in order to keep the population informed about the actions taken, the real risks and the consequences of an alleged nuclear accident. Effective public communication is understood to encourage the implementation of appropriate protective actions by people at risk and reassure individuals who are not directly at risk, reducing rumors and fears. Thus, the Strategic Communication Planning (SCP) acquires high relevance in a context of panic control, disseminating the correct procedures that will directly contribute to the coordination of the nuclear emergency. In this sense, this work aims to present the steps of a SCP in the case of a nuclear emergency at the Almirante Álvaro Alberto Nuclear Power Plant. In this case, the SCP is divided into the Risk Management and Accident Management phases, being prepared in order to unite the legislation in force in the country with international agreements, technical standards and civil defense doctrines. It is understood that the SCP makes it possible to efficiently build communication channels with the public, as well as to provide authorities with strategies to disseminate information, creating performance indices to evaluate these strategies in relation to the stakeholders in the communication process, because only with a Implemented SCP will make it possible to create a continuous improvement in the information feedback processes with an increase in the quality of communications
{"title":"The Strategic Communication Planning in an emergency at the Almirante Álvaro Alberto Nuclear Power Plant (CNAAA)","authors":"Fernando Barcellos Razuck, Raul A. C. dos Santos, Paulo Escarani","doi":"10.15392/2319-0612.2023.2148","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2148","url":null,"abstract":"In a world where information has a high speed of propagation and is present in the most diverse media, it is essential to follow the news in order to keep the population informed about the actions taken, the real risks and the consequences of an alleged nuclear accident. Effective public communication is understood to encourage the implementation of appropriate protective actions by people at risk and reassure individuals who are not directly at risk, reducing rumors and fears. Thus, the Strategic Communication Planning (SCP) acquires high relevance in a context of panic control, disseminating the correct procedures that will directly contribute to the coordination of the nuclear emergency. In this sense, this work aims to present the steps of a SCP in the case of a nuclear emergency at the Almirante Álvaro Alberto Nuclear Power Plant. In this case, the SCP is divided into the Risk Management and Accident Management phases, being prepared in order to unite the legislation in force in the country with international agreements, technical standards and civil defense doctrines. It is understood that the SCP makes it possible to efficiently build communication channels with the public, as well as to provide authorities with strategies to disseminate information, creating performance indices to evaluate these strategies in relation to the stakeholders in the communication process, because only with a Implemented SCP will make it possible to create a continuous improvement in the information feedback processes with an increase in the quality of communications","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73024933","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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