Pub Date : 2024-01-10DOI: 10.15392/2319-0612.2024.2329
Maysa Costa Castro, N. F. Silva, Linda Viola Ehlin Caldas
Computed tomography (CT) is a diagnostic exam responsible for the highest dose values received by the patients during the procedure. Over the years, this kind of equipment has been improved to ensure that the patients do not receive unnecessary doses. For this reason it is important to keep a quality control program for the CT equipment. To perform the dosimetry in CT beams, the instrument used is usually a pencil type ionization chamber with a sensitive volume length of 10 cm. However, this kind of detector is available with different sensitive volume lengths. The aim of this study was to compare the response of two homemade pencil type ionization chambers with sensitive volume lengths of 10 cm and 30 cm in the laboratories of Instituto de Pesquisas Energéticas e Nucleares (IPEN, Brazil) and National Physical Laboratory (NPL, UK). The characterization tests were performed, and the results obtained are within the international recommended limits. The only difference observed in the response of the two chambers in both laboratories is the fact that the ionization current obtained in all the tests at the IPEN is higher than at the NPL, because of the beam characteristics.
{"title":"Interlaboratory comparison of two homemade pencil type ionization chambers","authors":"Maysa Costa Castro, N. F. Silva, Linda Viola Ehlin Caldas","doi":"10.15392/2319-0612.2024.2329","DOIUrl":"https://doi.org/10.15392/2319-0612.2024.2329","url":null,"abstract":"Computed tomography (CT) is a diagnostic exam responsible for the highest dose values received by the patients during the procedure. Over the years, this kind of equipment has been improved to ensure that the patients do not receive unnecessary doses. For this reason it is important to keep a quality control program for the CT equipment. To perform the dosimetry in CT beams, the instrument used is usually a pencil type ionization chamber with a sensitive volume length of 10 cm. However, this kind of detector is available with different sensitive volume lengths. The aim of this study was to compare the response of two homemade pencil type ionization chambers with sensitive volume lengths of 10 cm and 30 cm in the laboratories of Instituto de Pesquisas Energéticas e Nucleares (IPEN, Brazil) and National Physical Laboratory (NPL, UK). The characterization tests were performed, and the results obtained are within the international recommended limits. The only difference observed in the response of the two chambers in both laboratories is the fact that the ionization current obtained in all the tests at the IPEN is higher than at the NPL, because of the beam characteristics.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2024-01-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139534279","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 : 2023-12-22DOI: 10.15392/2319-0612.2023.2348
Masoud Jabbari, S. Pandesha
Novel therapeutic strategy in radionuclide therapy use cell-penetrating monoclonal antibodies to carry Auger-emitting radionuclides into the cells. Estimation of dose in normal and tumor cells are important to investigate the efficacy and toxicity of treatment. Monte Carlo simulation is the most suitable method for estimation of absorbed dose at microscopic level. It is therefore useful to carry out Monte Carlo simulation of Auger emitting radionuclides in order to assess the sensitivity of the results with respect to transport approximations generally used in Monte Carlo codes. There are several Auger emitting radionuclides with potential clinical applications, however, based on their half-life 111In is the most suitable for Auger therapeutic purposes and was considered in the present investigation. Geant4 Monte Carlo simulation was performed and specific absorbed dose fraction (or S-values) for 111In were calculated by using different physics model (Standard, Livermore, Penelope and Geant4-DNA) and compared with Medical Internal Radiation Dosimetry (MIRD) S-values. Source was distributed in the cytoplasm (Cy), surface (Cs) and nucleus (N). Average of relative differences (RD) (%) were calculated for self and cross absorbed dose. RD(%) for self-absorption (NßN) were 4.4, 2.36, 6.21 and 1.1 for Standard, Penelope, Livermore and Geant4-DNA respectively. For cross-absorption these values were higher (e.g. for NßCy 15.4, 18.36, 19.21 and 24.8 for Standard, Penelope, Livermore and Geant4-DNA respectively). Cutoff energy considered for electrons and gamma photons affect the results in dose estimation for Auger electrons in Monte Carlo simulation.
{"title":"Monte Carlo investigation of S-values for 111In radionuclide therapy","authors":"Masoud Jabbari, S. Pandesha","doi":"10.15392/2319-0612.2023.2348","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2348","url":null,"abstract":"Novel therapeutic strategy in radionuclide therapy use cell-penetrating monoclonal antibodies to carry Auger-emitting radionuclides into the cells. Estimation of dose in normal and tumor cells are important to investigate the efficacy and toxicity of treatment. Monte Carlo simulation is the most suitable method for estimation of absorbed dose at microscopic level. It is therefore useful to carry out Monte Carlo simulation of Auger emitting radionuclides in order to assess the sensitivity of the results with respect to transport approximations generally used in Monte Carlo codes. There are several Auger emitting radionuclides with potential clinical applications, however, based on their half-life 111In is the most suitable for Auger therapeutic purposes and was considered in the present investigation. Geant4 Monte Carlo simulation was performed and specific absorbed dose fraction (or S-values) for 111In were calculated by using different physics model (Standard, Livermore, Penelope and Geant4-DNA) and compared with Medical Internal Radiation Dosimetry (MIRD) S-values. Source was distributed in the cytoplasm (Cy), surface (Cs) and nucleus (N). Average of relative differences (RD) (%) were calculated for self and cross absorbed dose. RD(%) for self-absorption (NßN) were 4.4, 2.36, 6.21 and 1.1 for Standard, Penelope, Livermore and Geant4-DNA respectively. For cross-absorption these values were higher (e.g. for NßCy 15.4, 18.36, 19.21 and 24.8 for Standard, Penelope, Livermore and Geant4-DNA respectively). Cutoff energy considered for electrons and gamma photons affect the results in dose estimation for Auger electrons in Monte Carlo simulation.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-12-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138945518","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 : 2023-12-20DOI: 10.15392/2319-0612.2023.2389
Alexandre Soares Leal, João Gabriel Oliveira Marques, Amir Zacarias Mesquita, Daniel Almeida Magalhães Campolina, Denise Das Merces Camarano, Jefferson Jose Vilela
The IPR-R1 Triga nuclear research reactor of the Nuclear Technology Development Center (CDTN) is one of the oldest reactors in operation in the world. It is a compact and inherently safe reactor that operates at a continuous power level of 100 kW with a solid homogeneous General Atomic (GA) fuel element of zirconium hydride moderator homogeneously combined with 20% enriched uranium. The reactor core is at the bottom of a tank under approximately 6.0 meters of shielding water. The long operation time of the reactor, 63 years, and the contact of the water with the core, can induce corrosive processes in the IPR-R1 reactor and affect its safe operation. To keep the water quality according to the chemical-physical recommended standards, a quality management program, as recommended by the International Atomic Energy Agency (IAEA), was implemented. The water quality management program is a guideline of good practices applied to nuclear reactors, targeting to keep their water coolants at specified physical-chemical standard. The main aim of the present work is to introduce IPR-R1 Triga’s water chemistry program results from the second half of 2022 till the first half of 2023, when the installation returned to its regular activities after the Covid-19 pandemic. The physical-chemical parameters evaluated (e.g.: pH, alpha and beta radiation, electrical conductivity and gamma emitters) shows that the IPR-R1 reactor operates within recommended safety standards.
{"title":"Water quality management program for IPR-R1 TRIGA® research reactor","authors":"Alexandre Soares Leal, João Gabriel Oliveira Marques, Amir Zacarias Mesquita, Daniel Almeida Magalhães Campolina, Denise Das Merces Camarano, Jefferson Jose Vilela","doi":"10.15392/2319-0612.2023.2389","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2389","url":null,"abstract":"The IPR-R1 Triga nuclear research reactor of the Nuclear Technology Development Center (CDTN) is one of the oldest reactors in operation in the world. It is a compact and inherently safe reactor that operates at a continuous power level of 100 kW with a solid homogeneous General Atomic (GA) fuel element of zirconium hydride moderator homogeneously combined with 20% enriched uranium. The reactor core is at the bottom of a tank under approximately 6.0 meters of shielding water. The long operation time of the reactor, 63 years, and the contact of the water with the core, can induce corrosive processes in the IPR-R1 reactor and affect its safe operation. To keep the water quality according to the chemical-physical recommended standards, a quality management program, as recommended by the International Atomic Energy Agency (IAEA), was implemented. The water quality management program is a guideline of good practices applied to nuclear reactors, targeting to keep their water coolants at specified physical-chemical standard. The main aim of the present work is to introduce IPR-R1 Triga’s water chemistry program results from the second half of 2022 till the first half of 2023, when the installation returned to its regular activities after the Covid-19 pandemic. The physical-chemical parameters evaluated (e.g.: pH, alpha and beta radiation, electrical conductivity and gamma emitters) shows that the IPR-R1 reactor operates within recommended safety standards.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-12-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138956419","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 : 2023-12-19DOI: 10.15392/2319-0612.2023.2317
J. Gomes, M. Mattar Neto, M. C. Maturana, Patricia Oliveira
The main objective of this work is to present a methodology for the development of a Reliability Assurance Program (RAP) specific to a PWR experimental nuclear installation, through the analysis of the installation and the development of a preliminary RAP subsidized by a Reliability, Availability and Maintainability (RAM) model. The study of an evaluation was carried out in the long-term decay heat removal of the studied experimental plant, whose data were used for application of the RAP. The necessary steps for applying the developed RAP are followed, using the data from the assessment of the studied plant, resulting in a list of components of significant risk for the Program, and in the following steps of sending the list to the experts panel, ranking of SSCs by the panel and development of the final list of significant risk SSCs for using the list in the optimization of the plant. The RAP subsidized by a RAM model will be able to work with the logical relationships between each component of the plant for their effects on energy generation and with the quantitative prediction of the magnitude of each contributor to the occurrence of high-level events, and the developed methodology can be applicable throughout the experimental plant. In this way, it will be possible to implement the RAP in the plant, which will provide a structured way to meet the regulatory requirements for its licensing. Also, it will be possible to complement the plant safety analysis report, which must contain the RAP.
{"title":"Development of the Reliability Assurance Program in a Brazilian nuclear power plant subsidized by a Reliability, Availability and Maintainability Model","authors":"J. Gomes, M. Mattar Neto, M. C. Maturana, Patricia Oliveira","doi":"10.15392/2319-0612.2023.2317","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2317","url":null,"abstract":"The main objective of this work is to present a methodology for the development of a Reliability Assurance Program (RAP) specific to a PWR experimental nuclear installation, through the analysis of the installation and the development of a preliminary RAP subsidized by a Reliability, Availability and Maintainability (RAM) model. The study of an evaluation was carried out in the long-term decay heat removal of the studied experimental plant, whose data were used for application of the RAP. The necessary steps for applying the developed RAP are followed, using the data from the assessment of the studied plant, resulting in a list of components of significant risk for the Program, and in the following steps of sending the list to the experts panel, ranking of SSCs by the panel and development of the final list of significant risk SSCs for using the list in the optimization of the plant. The RAP subsidized by a RAM model will be able to work with the logical relationships between each component of the plant for their effects on energy generation and with the quantitative prediction of the magnitude of each contributor to the occurrence of high-level events, and the developed methodology can be applicable throughout the experimental plant. In this way, it will be possible to implement the RAP in the plant, which will provide a structured way to meet the regulatory requirements for its licensing. Also, it will be possible to complement the plant safety analysis report, which must contain the RAP.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-12-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138959987","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 : 2023-12-19DOI: 10.15392/2319-0612.2023.1317
T. A. S. Vieira, Felipe Reis Campanha Ribeiro, Yasmim Martins Carvalho, V. Silva, Graiciany de Paula Barros, Andre Augusto Campagnole dos Santos
In the present work, an assessment of the Neutronic Benchmark of the Molten Salt Fast Reactor (MSFR) was performed using mesh based Monte Carlo Neutron Transport (MCNT) calculations with numerical uncertainty quantification due to discretization in neutronic parameters. Calculations with Constructive Solid Geometry (CSG) models where made as a baseline for the developed mesh based models. The numerical uncertainty given by the mesh utilization is evaluated using an extended version of the Grid Convergence Index (GCI). The fuel salt reprocessing is evaluated regarding a constant reprocessing rate. The fuel salt inventory variation with time for the developed models (CSG and meshed) is presented. The differences caused by the discretization procedure are noticeable, which shows that mesh based MCNT require careful mesh sensitivity evaluation and further validation.
{"title":"Investigation of discretization uncertainty in Monte Carlo neutron transport simulations of the Molten Salt Fast Reactor (MSFR)","authors":"T. A. S. Vieira, Felipe Reis Campanha Ribeiro, Yasmim Martins Carvalho, V. Silva, Graiciany de Paula Barros, Andre Augusto Campagnole dos Santos","doi":"10.15392/2319-0612.2023.1317","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.1317","url":null,"abstract":"In the present work, an assessment of the Neutronic Benchmark of the Molten Salt Fast Reactor (MSFR) was performed using mesh based Monte Carlo Neutron Transport (MCNT) calculations with numerical uncertainty quantification due to discretization in neutronic parameters. Calculations with Constructive Solid Geometry (CSG) models where made as a baseline for the developed mesh based models. The numerical uncertainty given by the mesh utilization is evaluated using an extended version of the Grid Convergence Index (GCI). The fuel salt reprocessing is evaluated regarding a constant reprocessing rate. The fuel salt inventory variation with time for the developed models (CSG and meshed) is presented. The differences caused by the discretization procedure are noticeable, which shows that mesh based MCNT require careful mesh sensitivity evaluation and further validation.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-12-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138959908","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 : 2023-12-14DOI: 10.15392/2319-0612.2023.2261
Soledad Banega, Cintia Bertoncini, Mercedes Pascuccio, Alba Güerci
Introduction: the search for substances that modulate the adverse effects of radiotherapy is key to optimizing the efficacy of these treatments and improving the patient's quality of life. We consider the evaluation of green tea (Camellia Sinensis) opportune for its antioxidant and anti-inflammatory properties, while its composition in polyphenols would make it possible to reduce radiosensitivity and improve cell recovery. Thus, our objective was to assess the efficacy of this infusion in the management of mucositis developed during radiant treatment of patients with head and neck cancer. Materials and Methods: a prospective and controlled clinical trial was carried out on a population of 20 patients, under treatment with intensity modulated radiation (IMRT). The result of the intervention with green tea rinses (4 times/day) or compliance with the usual protocol, was assessed by detailed recording of radiotoxicity, using the RTOG scale. Statistical analysis was performed using the T-Test: Student's t-Mann-Whitney U. Results: all the patients who adhered to and exhaustively complied with the protocol with the infusion, although they did not significantly recover the state of the oral cavity, demonstrated better control of the radio-induced acute effects (xerostomia and mucositis). Conclusion: although our results are preliminary, they allow us to suggest that from the intervention with green tea, the acute radiation-induced effects could be modulated. We believe intervention with this substance is opportune, given its easy administration, availability, cost, and lack of toxicity in a wide range of doses.
导语：寻找能调节放疗不良反应的物质是优化放疗疗效和改善患者生活质量的关键。绿茶（山茶）具有抗氧化和消炎的特性，其多酚成分可降低放射敏感性并改善细胞恢复，因此我们认为对绿茶进行评估正合适。因此，我们的目标是评估这种输液在治疗头颈部癌症患者放射治疗期间出现的粘膜炎方面的疗效。材料和方法：我们对 20 名接受调强放射治疗（IMRT）的患者进行了前瞻性对照临床试验。使用绿茶漱口液（每天 4 次）进行干预的结果或遵守常规方案的情况，通过使用 RTOG 量表详细记录放射毒性来评估。统计分析采用 T 检验：结果：所有坚持并严格遵守输液方案的患者，虽然口腔状况没有明显恢复，但放射引起的急性效应（口腔干燥症和粘膜炎）得到了较好的控制。结论：虽然我们的研究结果还只是初步的，但我们可以认为，通过使用绿茶进行干预，可以调节辐射引起的急性效应。我们认为，使用绿茶进行干预是一个很好的时机，因为绿茶服用方便、容易获得、成本低，而且在各种剂量下都没有毒性。
{"title":"Modulation of radiant oncological therapy through the intervention with substances of vegetable origin","authors":"Soledad Banega, Cintia Bertoncini, Mercedes Pascuccio, Alba Güerci","doi":"10.15392/2319-0612.2023.2261","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2261","url":null,"abstract":"Introduction: the search for substances that modulate the adverse effects of radiotherapy is key to optimizing the efficacy of these treatments and improving the patient's quality of life. We consider the evaluation of green tea (Camellia Sinensis) opportune for its antioxidant and anti-inflammatory properties, while its composition in polyphenols would make it possible to reduce radiosensitivity and improve cell recovery. Thus, our objective was to assess the efficacy of this infusion in the management of mucositis developed during radiant treatment of patients with head and neck cancer. Materials and Methods: a prospective and controlled clinical trial was carried out on a population of 20 patients, under treatment with intensity modulated radiation (IMRT). The result of the intervention with green tea rinses (4 times/day) or compliance with the usual protocol, was assessed by detailed recording of radiotoxicity, using the RTOG scale. Statistical analysis was performed using the T-Test: Student's t-Mann-Whitney U. Results: all the patients who adhered to and exhaustively complied with the protocol with the infusion, although they did not significantly recover the state of the oral cavity, demonstrated better control of the radio-induced acute effects (xerostomia and mucositis). Conclusion: although our results are preliminary, they allow us to suggest that from the intervention with green tea, the acute radiation-induced effects could be modulated. We believe intervention with this substance is opportune, given its easy administration, availability, cost, and lack of toxicity in a wide range of doses.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-12-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138971958","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 : 2023-12-13DOI: 10.15392/2319-0612.2023.2310
Daniel Mol Machado, Antonio Carlos de Abreu Mól, André Cotelli Santo, Mônica de Assis, Celso Marcelo Lapa, J. Suita
The preparations of radiopharmaceuticals must follow the parameters of quality, efficacy, and safety (pharmaceutical and nuclear), complying with all the requirements established in good manufacturing practices, guaranteed by the physical structure, layout, safety, and radiological protection, which are also fundamental for the correct flow to be followed for excellence in the functioning of the service. One of the main problems is related to the flow of radiopharmaceuticals, which implies exposure to ionizing radiation, which in turn poses serious biological risks to the human body. simple erythema (redness) to the acute radiation syndrome, which can even be lethal. Factors like this corroborate the need for training that simulate real situations, however, situations like this are limited, due to the risk to which a non-specialized professional can be exposed if radioprotection standards are not obeyed. The present work aims to propose and evaluate the use of virtual reality (VR) technology for training and qualification of professionals in a radiopharmacy. The applied methodology was divided into four stages, initially the rules and regulations regarding the Nuclear Medicine Service published by ANVISA, CNEN and international recommendations by the IAEA were analyzed in detail, in the second stage visits were carried out in public and private hospitals in the Rio de Janeiro that present the nuclear medicine service, in the third stage the virtual environment (simulator) was built, and the fourth stage proposed strategies to carry out training, considering a new technique for teaching. The use of virtual reality, through a simulator, allowed the creation of a graphical environment with a realistic appearance, in which the user can navigate in this environment and manipulate the virtual world. Therefore, it is expected that this tool can help in the planning and training of radiopharmacy professionals.
{"title":"The Use of Virtual Reality as an Aid Tool in the Implementation of a Radiopharmacy Center in a Nuclear Medicine Service","authors":"Daniel Mol Machado, Antonio Carlos de Abreu Mól, André Cotelli Santo, Mônica de Assis, Celso Marcelo Lapa, J. Suita","doi":"10.15392/2319-0612.2023.2310","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2310","url":null,"abstract":"The preparations of radiopharmaceuticals must follow the parameters of quality, efficacy, and safety (pharmaceutical and nuclear), complying with all the requirements established in good manufacturing practices, guaranteed by the physical structure, layout, safety, and radiological protection, which are also fundamental for the correct flow to be followed for excellence in the functioning of the service. One of the main problems is related to the flow of radiopharmaceuticals, which implies exposure to ionizing radiation, which in turn poses serious biological risks to the human body. simple erythema (redness) to the acute radiation syndrome, which can even be lethal. Factors like this corroborate the need for training that simulate real situations, however, situations like this are limited, due to the risk to which a non-specialized professional can be exposed if radioprotection standards are not obeyed. The present work aims to propose and evaluate the use of virtual reality (VR) technology for training and qualification of professionals in a radiopharmacy. The applied methodology was divided into four stages, initially the rules and regulations regarding the Nuclear Medicine Service published by ANVISA, CNEN and international recommendations by the IAEA were analyzed in detail, in the second stage visits were carried out in public and private hospitals in the Rio de Janeiro that present the nuclear medicine service, in the third stage the virtual environment (simulator) was built, and the fourth stage proposed strategies to carry out training, considering a new technique for teaching. The use of virtual reality, through a simulator, allowed the creation of a graphical environment with a realistic appearance, in which the user can navigate in this environment and manipulate the virtual world. Therefore, it is expected that this tool can help in the planning and training of radiopharmacy professionals.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-12-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139005601","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 : 2023-12-05DOI: 10.15392/2319-0612.2023.2173
Elydio Soares, Talita Santos, Filipe Mazzaro, Fernando Almeida, Bruno Mendes, Ricardo Gomes, Telma Fonseca
Brazil is the world's largest supplier of niobium to industry, accounting for 98% of world production, with Minas Gerais supplying 80% of total production. The mineral exploration industry generates millions of tons of waste annually. In several mining industries, waste is considered a burden for companies. Based on the radiation protection exemptions for the disposal of mining waste, the study analyses the use of waste as a raw material for the construction industry. The minimum dose rate found for gamma radiation in the waste was 0.24 µSv/h and a maximum dose of 0.33 µSv/h, which corresponds to an annual dose above the population exposure limit. The radio concentrations from gamma spectrometric analyses with the Ge(HP) detector for the two samples are a maximum of 240 Bq/kg for Ra-226 and a maximum of 840 Bq/kg for Ra-228. Despite the dose values determined for gamma radiation, CNEN Resolution 179 of 2014 considers materials with natural radioactive concentrations of radium 226 and 228 of up to 1000 Bq/kg suitable for use in the cement industry. Nevertheless, further analysis must be carried out. Since the tailings contain a concentration of Ra-226 and the radio is a source of radon gas, new analyses need to be carried out targeting the exhalation of radon.
{"title":"Assessment of the use of tailings based on the legal requirements for radiation protection, from niobium mining in Minas Gerais – Brazil","authors":"Elydio Soares, Talita Santos, Filipe Mazzaro, Fernando Almeida, Bruno Mendes, Ricardo Gomes, Telma Fonseca","doi":"10.15392/2319-0612.2023.2173","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2173","url":null,"abstract":"Brazil is the world's largest supplier of niobium to industry, accounting for 98% of world production, with Minas Gerais supplying 80% of total production. The mineral exploration industry generates millions of tons of waste annually. In several mining industries, waste is considered a burden for companies. Based on the radiation protection exemptions for the disposal of mining waste, the study analyses the use of waste as a raw material for the construction industry. The minimum dose rate found for gamma radiation in the waste was 0.24 µSv/h and a maximum dose of 0.33 µSv/h, which corresponds to an annual dose above the population exposure limit. The radio concentrations from gamma spectrometric analyses with the Ge(HP) detector for the two samples are a maximum of 240 Bq/kg for Ra-226 and a maximum of 840 Bq/kg for Ra-228. Despite the dose values determined for gamma radiation, CNEN Resolution 179 of 2014 considers materials with natural radioactive concentrations of radium 226 and 228 of up to 1000 Bq/kg suitable for use in the cement industry. Nevertheless, further analysis must be carried out. Since the tailings contain a concentration of Ra-226 and the radio is a source of radon gas, new analyses need to be carried out targeting the exhalation of radon.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-12-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138601425","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 : 2023-10-31DOI: 10.15392/2319-0612.2023.2306
Rodrigo Modesto Gadelha Gontijo, Andréa Vidal Ferreira, Daniele Faria, Carlos Alberto Buchpiguel, Samuel Greggio, Gianina Venturin, Jader Costa, Juliana Silva, Marcelo Mamede
This study evaluated Image Quality (IQ) parameters and spatial resolution (SR) of Triumph® LabPET systems installed in three different Brazilian preclinical molecular imaging centers. A comprehensive evaluation of the PET scanner intrinsic parameters is important to optimize the acquired images, providing more reliable qualitative and quantitative analyses. Experiments were carried out at the centers: C1 - Molecular Imaging Laboratory of the CDTN/CNEN; C2 - Laboratory of Nuclear Medicine of HCFMUSP; C3 - Preclinical Research Center of the Brain Institute at PUC-RS. IQ phantom PET images were acquired as recommended in NEMA NU 4-2008 standard. Image reconstructions were performed in each system using the same reconstruction protocol. Data was processed using PMOD® software. The IQ parameters: (i) uniformity, (ii) spill-over ratio (SOR) and (iii) recovery coefficients (RC) were evaluated and compared. For Uniformity test, the percentage standard deviations of mean activity concentration were 7.8%; 7.3% and 6.4% for Centers 1, 2 and 3 respectively. Cold chambers RSO values in the systems 1, 2 and 3 were respectively 0.16, 0.19 and 0.21 for water; 0.26; 0.28 and 0.30 for air. The RC’s for rod diameters from 1 to 5 mm ranged from 0.08 to 0.91 for the three centers. Results revealed that the three PET systems have appropriate quality parameters for pre-clinical studies, presenting values compatible with international standards. This study was able to reveals the performance of preclinical PET system of different Brazilian imaging centers and may support the standardization of a National Quality Control Program for Small Animal PET scanners.
本研究评估了安装在巴西三个不同的临床前分子成像中心的Triumph®LabPET系统的图像质量(IQ)参数和空间分辨率(SR)。全面评估PET扫描仪的内在参数对于优化获得的图像，提供更可靠的定性和定量分析是很重要的。实验在以下中心进行:C1 - CDTN/CNEN分子成像实验室;C2 - HCFMUSP核医学实验室;C3 -临床前研究中心脑科学研究所。IQ幻影PET图像是按照NEMA NU 4-2008标准的建议获取的。在每个系统中使用相同的重建协议进行图像重建。数据处理采用PMOD®软件。对IQ参数(i)均匀性、(ii)溢出比(SOR)和(iii)恢复系数(RC)进行评价和比较。均匀性检验，平均活性浓度的百分比标准差为7.8%;1、2、3中心分别为7.3%和6.4%。系统1、系统2和系统3的冷室RSO值分别为0.16、0.19和0.21;0.26;0.28和0.30空气。杆直径从1到5毫米的RC的范围从0.08到0.91的三个中心。结果表明，这三种PET系统具有适合临床前研究的质量参数，其值与国际标准相一致。这项研究能够揭示不同巴西成像中心的临床前PET系统的性能，并可能支持小动物PET扫描仪国家质量控制计划的标准化。
{"title":"Comparative analysis of image quality parameters and spatial resolution of three Small Animal PET scanner in Brazil","authors":"Rodrigo Modesto Gadelha Gontijo, Andréa Vidal Ferreira, Daniele Faria, Carlos Alberto Buchpiguel, Samuel Greggio, Gianina Venturin, Jader Costa, Juliana Silva, Marcelo Mamede","doi":"10.15392/2319-0612.2023.2306","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2306","url":null,"abstract":"This study evaluated Image Quality (IQ) parameters and spatial resolution (SR) of Triumph® LabPET systems installed in three different Brazilian preclinical molecular imaging centers. A comprehensive evaluation of the PET scanner intrinsic parameters is important to optimize the acquired images, providing more reliable qualitative and quantitative analyses. Experiments were carried out at the centers: C1 - Molecular Imaging Laboratory of the CDTN/CNEN; C2 - Laboratory of Nuclear Medicine of HCFMUSP; C3 - Preclinical Research Center of the Brain Institute at PUC-RS. IQ phantom PET images were acquired as recommended in NEMA NU 4-2008 standard. Image reconstructions were performed in each system using the same reconstruction protocol. Data was processed using PMOD® software. The IQ parameters: (i) uniformity, (ii) spill-over ratio (SOR) and (iii) recovery coefficients (RC) were evaluated and compared. For Uniformity test, the percentage standard deviations of mean activity concentration were 7.8%; 7.3% and 6.4% for Centers 1, 2 and 3 respectively. Cold chambers RSO values in the systems 1, 2 and 3 were respectively 0.16, 0.19 and 0.21 for water; 0.26; 0.28 and 0.30 for air. The RC’s for rod diameters from 1 to 5 mm ranged from 0.08 to 0.91 for the three centers. Results revealed that the three PET systems have appropriate quality parameters for pre-clinical studies, presenting values compatible with international standards. This study was able to reveals the performance of preclinical PET system of different Brazilian imaging centers and may support the standardization of a National Quality Control Program for Small Animal PET scanners.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135808507","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 : 2023-10-31DOI: 10.15392/2319-0612.2023.2313
M. R. Gual, M. C. Maturana, Hugo Da Costa Romberg Júnior, Nathália N. Araújo
The growing demand for electricity, increasing rising fossil fuel prices and global warming in Brazil, together with the lack of access to electricity on the part of the population in certain locations in the Northern Region, such as, for example, Rondônia, Pará and Amazonas, is currently seeking for solutions. The objective of the present study is to carry out a Strengths, Weaknesses, Opportunities and Threats (SWOT) analysis of the inclusion of a project of a floating nuclear power plants (FNPP) in Brazil with a view to solving the lack of electricity in homes and in industries located in remote regions of Brazil. Study results identified several socioeconomic and environmental impacts on this regions. The study concludes that in addition to contributing to the solution of the lack of energy in remote regions, the implementation of this proposal could represent in the future a source of inflow of financial resources in the country and of international collaboration. This SWOT study will encourage investors, researchers, engineers and decision makers to open the debate about the benefit of using a FNPP in Brazil, which in addition to providing economic energy rates for the population, would be a profitable business and an international collaboration.
{"title":"SWOT analysis of a Floating Nuclear Power Plant for electricity generation in Brazil","authors":"M. R. Gual, M. C. Maturana, Hugo Da Costa Romberg Júnior, Nathália N. Araújo","doi":"10.15392/2319-0612.2023.2313","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2313","url":null,"abstract":"The growing demand for electricity, increasing rising fossil fuel prices and global warming in Brazil, together with the lack of access to electricity on the part of the population in certain locations in the Northern Region, such as, for example, Rondônia, Pará and Amazonas, is currently seeking for solutions. The objective of the present study is to carry out a Strengths, Weaknesses, Opportunities and Threats (SWOT) analysis of the inclusion of a project of a floating nuclear power plants (FNPP) in Brazil with a view to solving the lack of electricity in homes and in industries located in remote regions of Brazil. Study results identified several socioeconomic and environmental impacts on this regions. The study concludes that in addition to contributing to the solution of the lack of energy in remote regions, the implementation of this proposal could represent in the future a source of inflow of financial resources in the country and of international collaboration. This SWOT study will encourage investors, researchers, engineers and decision makers to open the debate about the benefit of using a FNPP in Brazil, which in addition to providing economic energy rates for the population, would be a profitable business and an international collaboration.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135808516","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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