Pub Date : 2023-05-23DOI: 10.15392/2319-0612.2023.2160
M. C. Tessari-Zampieri, A. Santiago, Renan N. Lopes, M. Cotrim, M. Scapin
Materiality should be used as a strategic business tool, with implications beyond social, economic, and environmental responsibility in sustainability reporting. Organizations can benefit by incorporate materiality into their existing economic processes, creating a broader approach and ensuring strategies with significant social and environmental topics. This provides stakeholder engagement; prioritizes financial resources for sustainability; develops new business; identifies climate change issues; among others. In this context, aim this study was to present a review the materiality related to radiologic protection in organizational sustainability reports. The results show that radiologic protection is considered in several topics in the organizational sustainability reports evaluated, represented from issues occupational health and safety, environmental assessment suppliers, environmental compliance, local communities, and waste management. It was concluded that, in preparing the materiality matrix, it is necessary to have the methods defined advance to grant them to be reproduced and periodically reviewed. This will allow to demonstrate the sustainability evolution and its alignment with the organizations' strategies.
{"title":"A review on the radiological protection materiality in environmental sustainability reports","authors":"M. C. Tessari-Zampieri, A. Santiago, Renan N. Lopes, M. Cotrim, M. Scapin","doi":"10.15392/2319-0612.2023.2160","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2160","url":null,"abstract":"Materiality should be used as a strategic business tool, with implications beyond social, economic, and environmental responsibility in sustainability reporting. Organizations can benefit by incorporate materiality into their existing economic processes, creating a broader approach and ensuring strategies with significant social and environmental topics. This provides stakeholder engagement; prioritizes financial resources for sustainability; develops new business; identifies climate change issues; among others. In this context, aim this study was to present a review the materiality related to radiologic protection in organizational sustainability reports. The results show that radiologic protection is considered in several topics in the organizational sustainability reports evaluated, represented from issues occupational health and safety, environmental assessment suppliers, environmental compliance, local communities, and waste management. It was concluded that, in preparing the materiality matrix, it is necessary to have the methods defined advance to grant them to be reproduced and periodically reviewed. This will allow to demonstrate the sustainability evolution and its alignment with the organizations' strategies.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80392699","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 : 2023-05-23DOI: 10.15392/2319-0612.2023.2151
Ary Machado de Azevedo, D. O. Cardoso, M. P. Medeiros, S. Gavazza, R. K. Morales
In the present work, the transmission factors of γ-rays are determined in bi-layered shields composed of lead and steel, through a methodology composed of three distinct parts. The buildup calculation was performed using the methodology published by Broder in 1962 [1]. A computational simulation was used through a spherical model, a total of three concentric spheres were simulated, with the source in the center of the spheres. The first sphere represents the lead shield and its radius is represented by the thickness of this material. The second sphere represents the steel shield and its radius is the sum of the thicknesses of the shielding. The third sphere is the vacuum that will determine the number of photons that will pass. To verify if the analytical methodology can be used to calculate the transmission factor of the proposed shield, laboratory experiments were performed with the BGO (Bismuth Germanate) detector. Measurements were only made with the thickness of steel, and with 15 different thicknesses of lead, ranging from 0.11 cm to 2.01 cm, while keeping the steel thickness. Three different thicknesses of steel were used: 0.65 cm, 0.85 cm and 1.40 cm. The work is relevant in the field of radiological and nuclear defense, considering the application of this shield in military vehicles, and the efficiency of the proposed analytical methodology was demonstrated.
{"title":"Determination of steel and lead bi-laminated shielding for military vehicles","authors":"Ary Machado de Azevedo, D. O. Cardoso, M. P. Medeiros, S. Gavazza, R. K. Morales","doi":"10.15392/2319-0612.2023.2151","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2151","url":null,"abstract":"In the present work, the transmission factors of γ-rays are determined in bi-layered shields composed of lead and steel, through a methodology composed of three distinct parts. The buildup calculation was performed using the methodology published by Broder in 1962 [1]. A computational simulation was used through a spherical model, a total of three concentric spheres were simulated, with the source in the center of the spheres. The first sphere represents the lead shield and its radius is represented by the thickness of this material. The second sphere represents the steel shield and its radius is the sum of the thicknesses of the shielding. The third sphere is the vacuum that will determine the number of photons that will pass. To verify if the analytical methodology can be used to calculate the transmission factor of the proposed shield, laboratory experiments were performed with the BGO (Bismuth Germanate) detector. Measurements were only made with the thickness of steel, and with 15 different thicknesses of lead, ranging from 0.11 cm to 2.01 cm, while keeping the steel thickness. Three different thicknesses of steel were used: 0.65 cm, 0.85 cm and 1.40 cm. The work is relevant in the field of radiological and nuclear defense, considering the application of this shield in military vehicles, and the efficiency of the proposed analytical methodology was demonstrated.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83243944","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 : 2023-05-22DOI: 10.15392/2319-0612.2023.2136
M. Clavery, Fernando Barcellos Razuck
Nuclear Medicine (NM) is a medical specialty that, through non-invasive methods, uses radioactive materials for diagnostic and therapeutic purposes. According to Standard NN 3.05 of the Brazilian National Nuclear Energy Commission (CNEN), a Nuclear Medicine System (NMS) must be composed of, at least, a Holder, a Nuclear Physician, a Radiation Protection Supervisor and higher and mid-level professionals, duly qualified for the performance of their duties, which may be exercised, in this case, by a radiology technician. Thus, in 2009, the National Council of Radiology Technicians (CONTER) granted a period of 5 (five) years for radiology technicians who work in the NM and Radiotherapy specialties to specialize in their areas of expertise, a period that was extended for another 5 (five) years. In this sense, this paper aims to carry out a survey of the Technical Specialization courses in NM offered in Brazil, considering that almost 10 years have passed since the CONTER Resolution No. 17, of 2014, verifying aspects such as structure and workload, based on the requirements of the Ministry of Education (MEC), in order to suggest a core curriculum for courses in NM. It was found that, with the legal requirement of this training, these courses began to be offered, but in a reduced number and only in some regions of Brazil, despite the existence of courses in the distance modality. It is understood, therefore, that an expansion of courses in the area is necessary, in view of the relevance of the service for NM.
{"title":"Technical specialization in Nuclear Medicine: an analysis of courses in Brazil and a proposal for a basic curriculum","authors":"M. Clavery, Fernando Barcellos Razuck","doi":"10.15392/2319-0612.2023.2136","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2136","url":null,"abstract":"Nuclear Medicine (NM) is a medical specialty that, through non-invasive methods, uses radioactive materials for diagnostic and therapeutic purposes. According to Standard NN 3.05 of the Brazilian National Nuclear Energy Commission (CNEN), a Nuclear Medicine System (NMS) must be composed of, at least, a Holder, a Nuclear Physician, a Radiation Protection Supervisor and higher and mid-level professionals, duly qualified for the performance of their duties, which may be exercised, in this case, by a radiology technician. Thus, in 2009, the National Council of Radiology Technicians (CONTER) granted a period of 5 (five) years for radiology technicians who work in the NM and Radiotherapy specialties to specialize in their areas of expertise, a period that was extended for another 5 (five) years. In this sense, this paper aims to carry out a survey of the Technical Specialization courses in NM offered in Brazil, considering that almost 10 years have passed since the CONTER Resolution No. 17, of 2014, verifying aspects such as structure and workload, based on the requirements of the Ministry of Education (MEC), in order to suggest a core curriculum for courses in NM. It was found that, with the legal requirement of this training, these courses began to be offered, but in a reduced number and only in some regions of Brazil, despite the existence of courses in the distance modality. It is understood, therefore, that an expansion of courses in the area is necessary, in view of the relevance of the service for NM.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91149357","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 : 2023-05-22DOI: 10.15392/2319-0612.2023.2144
M. Scapin, M. C. Tessari-Zampieri, S. Guilhen, M. Cotrim
This study aims to develop reliable analytical methodology that is, cost-effective, and requires minimal sample quantity to quantify uranium content in nuclear waste and others. The Energy Dispersive X-ray Fluorescence Spectrometry (EDXRF) technique was used, and a rigorous comparison was made between the fundamental parameters (FP) method and the empirical (EMP) method. Statistical evaluation of results demonstrated that the FP method showed a satisfactory level of confidence for precision and limit of quantification.
{"title":"X-ray fluorescence spectrometry: An alternative technique for analysis of waste","authors":"M. Scapin, M. C. Tessari-Zampieri, S. Guilhen, M. Cotrim","doi":"10.15392/2319-0612.2023.2144","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2144","url":null,"abstract":"This study aims to develop reliable analytical methodology that is, cost-effective, and requires minimal sample quantity to quantify uranium content in nuclear waste and others. The Energy Dispersive X-ray Fluorescence Spectrometry (EDXRF) technique was used, and a rigorous comparison was made between the fundamental parameters (FP) method and the empirical (EMP) method. Statistical evaluation of results demonstrated that the FP method showed a satisfactory level of confidence for precision and limit of quantification.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81920211","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 : 2023-05-08DOI: 10.15392/2319-0612.2023.2166
Gisell Ruiz Boiset, Renne Rodrigues Rosinelli, G. Freire, Raissa Aline Santos Moura, Raphael Moratta, E. Yoshimura, P. Costa
In this work we obtained experimental linear attenuation coefficients of polymer-based samples at diagnostic imaging energy range (15-150 keV) for eleven formulations candidates for tissue-equivalent materials (TEMs). TEMs is any material that simulates a human body part or human tissue in its interaction with radiation. In diagnostic radiology, the maximum difference between the linear attenuation coefficient of the TEMs and the target material should be no more than 5% in the energy range of interest. A polienergetic narrow beam was obtained using a tungsten target x-ray tube and CdTe detector. The densities of the samples were determined and compared with reference materials obtaining a maximum difference of 17%. The comparisons between the linear attenuation coefficient of the formulations and the respective reference materials for which they were initially designed, has demonstrated good correspondence over a wide energy range. Energy ranges in which the developed samples simulate other human tissues in addition to those initially considered were found, taken into account the criterion that the maximum difference between the linear attenuation coefficients does not exceed 5% is met. The results emphasize the possibility of production and characterization of TEMs to be used in the construction of imaging and dosimetry phantoms.
{"title":"X-ray spectrometry applied for determination of linear attenuation coefficient of polymer-based samples as radiologically tissue-equivalent materials","authors":"Gisell Ruiz Boiset, Renne Rodrigues Rosinelli, G. Freire, Raissa Aline Santos Moura, Raphael Moratta, E. Yoshimura, P. Costa","doi":"10.15392/2319-0612.2023.2166","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2166","url":null,"abstract":"In this work we obtained experimental linear attenuation coefficients of polymer-based samples at diagnostic imaging energy range (15-150 keV) for eleven formulations candidates for tissue-equivalent materials (TEMs). TEMs is any material that simulates a human body part or human tissue in its interaction with radiation. In diagnostic radiology, the maximum difference between the linear attenuation coefficient of the TEMs and the target material should be no more than 5% in the energy range of interest. A polienergetic narrow beam was obtained using a tungsten target x-ray tube and CdTe detector. The densities of the samples were determined and compared with reference materials obtaining a maximum difference of 17%. The comparisons between the linear attenuation coefficient of the formulations and the respective reference materials for which they were initially designed, has demonstrated good correspondence over a wide energy range. Energy ranges in which the developed samples simulate other human tissues in addition to those initially considered were found, taken into account the criterion that the maximum difference between the linear attenuation coefficients does not exceed 5% is met. The results emphasize the possibility of production and characterization of TEMs to be used in the construction of imaging and dosimetry phantoms.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87980767","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 : 2023-05-08DOI: 10.15392/2319-0612.2023.2154
E. Itikawa, H. S. Videira, Uysha de Souza-Fonda, Priscila Soares Pires, R. Mondin, Ivani Bortoleti, M. Guimarães, C. Buchpiguel
PET/MRI technology has expanded the boundaries of investigation in nuclear medicine, supported by the high sensitivity of solid-state PET detectors. Nonetheless, the coil positioning might lead to an increased exposure period of the worker to the injected patient. This procedure does not occur on PET/CT and, therefore, exposure period is reduced on such scanner. The aim of our study was to evaluate the dosimetry of two occupationally exposed individuals (OEI) working at the Center of Nuclear Medicine of Hospital das Clínicas of the University of Sao Paulo. We used thermoluminescent (TLD) dosimeters in pulse, whole-body and crystalline for PET/MRI and PET/CT procedures during five months of clinical and research routine. We also monitored the time for positioning/removing the patient on both scanners. For this study, OEI1 performed 76 PET/MRI studies and 102 PET/CT studies while OEI2 performed 26 and 56 PET/MRI and PET/CT studies, respectively. We found no evidence of differences for the whole-body dose values between both scanners (p = 0.22). The average time of patient management (positioning/removing the patient) was 14.38, and 3.81 minutes for PET/MRI and PET/CT, respectively. When the normalization by the number of PET/CT studies was applied, we found no statistical difference for effective and equivalent dose values. Our study encourages future investigations on nursing staff, which is a critical population that is exposed to ionizing radiation, mainly on dynamic studies, due to the synchronized injection with the protocol starting.
{"title":"Impact on dosimetry of occupationally exposed individuals on the patient management for PET/MRI studies: a comparison study with dosimetry on PET/CT","authors":"E. Itikawa, H. S. Videira, Uysha de Souza-Fonda, Priscila Soares Pires, R. Mondin, Ivani Bortoleti, M. Guimarães, C. Buchpiguel","doi":"10.15392/2319-0612.2023.2154","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2154","url":null,"abstract":"PET/MRI technology has expanded the boundaries of investigation in nuclear medicine, supported by the high sensitivity of solid-state PET detectors. Nonetheless, the coil positioning might lead to an increased exposure period of the worker to the injected patient. This procedure does not occur on PET/CT and, therefore, exposure period is reduced on such scanner. The aim of our study was to evaluate the dosimetry of two occupationally exposed individuals (OEI) working at the Center of Nuclear Medicine of Hospital das Clínicas of the University of Sao Paulo. We used thermoluminescent (TLD) dosimeters in pulse, whole-body and crystalline for PET/MRI and PET/CT procedures during five months of clinical and research routine. We also monitored the time for positioning/removing the patient on both scanners. For this study, OEI1 performed 76 PET/MRI studies and 102 PET/CT studies while OEI2 performed 26 and 56 PET/MRI and PET/CT studies, respectively. We found no evidence of differences for the whole-body dose values between both scanners (p = 0.22). The average time of patient management (positioning/removing the patient) was 14.38, and 3.81 minutes for PET/MRI and PET/CT, respectively. When the normalization by the number of PET/CT studies was applied, we found no statistical difference for effective and equivalent dose values. Our study encourages future investigations on nursing staff, which is a critical population that is exposed to ionizing radiation, mainly on dynamic studies, due to the synchronized injection with the protocol starting.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84832141","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 : 2023-05-03DOI: 10.15392/2319-0612.2023.2231
P. M. Barretto, E. Fonseca
This paper describes the details of the aeroradiometric operations, the radiation detection system used and discusses the results. The low-altitude survey was carried out over Goiânia a few days after information of the accident was received by the national competent authority, the Brazilian Nuclear Energy Commission (CNEN). Given the little information at the time of the accident and the urgency to respond to the local and federal authorities, an aerial radiometric survey was proposed to evaluate the extent of the contamination and dispersion of the radioactive powder. The city's entire urban area and nearby dwellings centers, plus the two creeks crossing the city were surveyed in two days. The survey found only one additional contamination point 2.8 x 10-4 C/kg/h (1.1 R/h) that had not yet been identified by ground survey crews. Furthermore, no contamination was found along the margins of the Capim Puba Creek and Meia Ponte rivers which could be contaminated due to rainwater common at that time of the year. Detection tests conducted at different altitudes over the main contamination area showed that the Cs-137 gamma radiation could be detected even at altitudes of 350m above the ground. This was much higher than the 40 m - 70 m decided for the overflights. The survey demonstrated that the contamination was restricted to a few locations in the neighborhood of the metal scrap place where the source shield was broken. These locations were under the control of CNEN radiological emergency response personnel. Such a finding was an important indicator to calm down the population and the government authorities. This allowed concentrating attention on the remediation of the known points of high gamma activity.
本文详细介绍了航空辐射测量的操作，使用的辐射检测系统，并讨论了结果。在国家主管部门巴西核能委员会(CNEN)收到事故信息几天后，在goi上空进行了低空调查。由于事故发生时资料很少，而且迫切需要向地方和联邦当局作出反应，因此建议进行一次空中辐射测量调查，以评估污染的程度和放射性粉末的扩散。在两天内调查了整个城市地区和附近的住宅中心，以及穿过城市的两条小溪。调查发现只有一个额外的污染点2.8 x 10-4 C/kg/h (1.1 R/h)尚未被地面调查人员确定。此外，在Capim Puba Creek河和Meia Ponte河的边缘没有发现污染，这些河流可能由于每年这个时候常见的雨水而受到污染。在主要污染区的不同高度进行的探测试验表明，即使在距地面350米的高度也能探测到Cs-137伽马辐射。这远高于40米至70米的飞行高度。调查表明，污染仅限于源屏蔽被破坏的金属废料场附近的几个地点。这些地点由CNEN放射应急反应人员控制。这一发现是安抚民众和政府当局的一个重要指标。这使人们能够集中注意力对已知的高伽马活动点进行补救。
{"title":"The Cs-137 radiological accident in Goiânia, Brazil: Conditions and results of the airborne radiometric survey","authors":"P. M. Barretto, E. Fonseca","doi":"10.15392/2319-0612.2023.2231","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2231","url":null,"abstract":"This paper describes the details of the aeroradiometric operations, the radiation detection system used and discusses the results. The low-altitude survey was carried out over Goiânia a few days after information of the accident was received by the national competent authority, the Brazilian Nuclear Energy Commission (CNEN). Given the little information at the time of the accident and the urgency to respond to the local and federal authorities, an aerial radiometric survey was proposed to evaluate the extent of the contamination and dispersion of the radioactive powder. The city's entire urban area and nearby dwellings centers, plus the two creeks crossing the city were surveyed in two days. The survey found only one additional contamination point 2.8 x 10-4 C/kg/h (1.1 R/h) that had not yet been identified by ground survey crews. Furthermore, no contamination was found along the margins of the Capim Puba Creek and Meia Ponte rivers which could be contaminated due to rainwater common at that time of the year. Detection tests conducted at different altitudes over the main contamination area showed that the Cs-137 gamma radiation could be detected even at altitudes of 350m above the ground. This was much higher than the 40 m - 70 m decided for the overflights. The survey demonstrated that the contamination was restricted to a few locations in the neighborhood of the metal scrap place where the source shield was broken. These locations were under the control of CNEN radiological emergency response personnel. Such a finding was an important indicator to calm down the population and the government authorities. This allowed concentrating attention on the remediation of the known points of high gamma activity.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90325516","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 : 2023-05-02DOI: 10.15392/2319-0612.2023.2170
Mariana Alonso Natividade, T. Alonso, A. Z. Mesquita
Food irradiation consists of a physical process that subjects food to doses of ionizing radiation, which are high enough energy to eliminate or neutralize harmful microbial contaminants without changing the taste or texture of food and without leaving residues. With this irradiation process we can prevent diseases transmitted by food, such as Salmonella and Escherichia coli, prolong the shelf life of foods, control pests that harm fruits by delaying germination and ripening, and finally sterilization, which allows their storage for years without refrigeration. The use of ionizing radiation for food preservation has been studied for several decades and is regulated in the USA by the Food and Drug Administration –FDA. In 1997, the World Health Organization - WHO released the use of the technique for all types of food. In Brazil, the first studies on food irradiation were carried out by the Center for Nuclear Energy in Agriculture - Cena, in the 50's. Currently, Brazilian legislation follows the international recommendations suggested by the Food and Agriculture Organization - FAO, the International Atomic Energy Agency - IAEA and Codex Alimentarius. The scope of this work is a survey, analysis and evolution of national and international legislation related to ionizing irradiation practices in food. For the preparation of this research, bibliographical reviews were carried out, consultations in Brazilian and international legislation, Internet sites, and in the documentation of the Gamma Irradiation Laboratory of the Nuclear Technology Development Center - CDTN
{"title":"Regulation and Supervision of Food Irradiation","authors":"Mariana Alonso Natividade, T. Alonso, A. Z. Mesquita","doi":"10.15392/2319-0612.2023.2170","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2170","url":null,"abstract":"Food irradiation consists of a physical process that subjects food to doses of ionizing radiation, which are high enough energy to eliminate or neutralize harmful microbial contaminants without changing the taste or texture of food and without leaving residues. With this irradiation process we can prevent diseases transmitted by food, such as Salmonella and Escherichia coli, prolong the shelf life of foods, control pests that harm fruits by delaying germination and ripening, and finally sterilization, which allows their storage for years without refrigeration. The use of ionizing radiation for food preservation has been studied for several decades and is regulated in the USA by the Food and Drug Administration –FDA. In 1997, the World Health Organization - WHO released the use of the technique for all types of food. In Brazil, the first studies on food irradiation were carried out by the Center for Nuclear Energy in Agriculture - Cena, in the 50's. Currently, Brazilian legislation follows the international recommendations suggested by the Food and Agriculture Organization - FAO, the International Atomic Energy Agency - IAEA and Codex Alimentarius. The scope of this work is a survey, analysis and evolution of national and international legislation related to ionizing irradiation practices in food. For the preparation of this research, bibliographical reviews were carried out, consultations in Brazilian and international legislation, Internet sites, and in the documentation of the Gamma Irradiation Laboratory of the Nuclear Technology Development Center - CDTN","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84057219","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 : 2023-05-02DOI: 10.15392/2319-0612.2023.2139
Vagner Resende, Alex Cunha, Arandi Ginane Bezerra Junior, A. Malthez
Laser radiation can cause undesirable biological effects on living beings; although it is not ionizing, this type of radiation can cause burns to the skin and cornea, even cataracts, depending on the wavelength and intensity of the laser radiation. Due to the wide growth of laser applications in several areas, such as research and development, services, and industry, the occupational risks concerning this non-ionizing radiation have increased considerably worldwide. Several countries have normative documents and regulatory bodies or agencies that approach occupational safety and quality regarding laser application, equipment, and machines. In Brazil, there is a lacking of laser safety documents published by a national regulatory council. Therefore, large technological centers and educational institutions, such as SENAI Institute for Innovation in Laser Manufacturing and Processing Systems (ISI-Joinville) and the Federal Technological University of Paraná (UTFPR), do not have an institutional safety program for laser operations, and to adapt to the most modern international recommendations they look for international documents and models from other institutions. The main objective of this work was to develop and propose an institutional program following Brazilian regulatory documents from the Ministry of Labor and Social Security and the most modern international standard about laser safety from the American National Standards Institute (ANSI-Z 136-1: 2014). The developed safety program was applied to ISI-Joinville, but a model was adapted to be implemented at any research center and university.
{"title":"Development and Proposal of an Institutional Safety Program in the Operation of Laser Systems","authors":"Vagner Resende, Alex Cunha, Arandi Ginane Bezerra Junior, A. Malthez","doi":"10.15392/2319-0612.2023.2139","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2139","url":null,"abstract":"Laser radiation can cause undesirable biological effects on living beings; although it is not ionizing, this type of radiation can cause burns to the skin and cornea, even cataracts, depending on the wavelength and intensity of the laser radiation. Due to the wide growth of laser applications in several areas, such as research and development, services, and industry, the occupational risks concerning this non-ionizing radiation have increased considerably worldwide. Several countries have normative documents and regulatory bodies or agencies that approach occupational safety and quality regarding laser application, equipment, and machines. In Brazil, there is a lacking of laser safety documents published by a national regulatory council. Therefore, large technological centers and educational institutions, such as SENAI Institute for Innovation in Laser Manufacturing and Processing Systems (ISI-Joinville) and the Federal Technological University of Paraná (UTFPR), do not have an institutional safety program for laser operations, and to adapt to the most modern international recommendations they look for international documents and models from other institutions. The main objective of this work was to develop and propose an institutional program following Brazilian regulatory documents from the Ministry of Labor and Social Security and the most modern international standard about laser safety from the American National Standards Institute (ANSI-Z 136-1: 2014). The developed safety program was applied to ISI-Joinville, but a model was adapted to be implemented at any research center and university.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77338622","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 : 2023-04-27DOI: 10.15392/2319-0612.2023.2184
A. D. Azevedo, J. Gonçalves, A. P. Salazar, D. O. Cardoso, P. V. Gonzales, V. A. V. Ferreira, W. V. Nunes
This article addresses the development of a remotely piloted vehicle for the chemical, biological, radiological, and nuclear army defense system, able itself to perform radiometric surveys remotely favoring the process of local mapping and investigation of possible dispersions of radioactive materials in radiological and nuclear accidents and incidents. Tests were carried out to verify the efficiency of the developed prototype and it can be verified that the vehicle has a great applicability and optimizes the radiological protection process.
{"title":"Radiometric survey with Remotely Piloted Land Vehicle in Chemical, Biological, Radiological and Nuclear Defense operations","authors":"A. D. Azevedo, J. Gonçalves, A. P. Salazar, D. O. Cardoso, P. V. Gonzales, V. A. V. Ferreira, W. V. Nunes","doi":"10.15392/2319-0612.2023.2184","DOIUrl":"https://doi.org/10.15392/2319-0612.2023.2184","url":null,"abstract":"This article addresses the development of a remotely piloted vehicle for the chemical, biological, radiological, and nuclear army defense system, able itself to perform radiometric surveys remotely favoring the process of local mapping and investigation of possible dispersions of radioactive materials in radiological and nuclear accidents and incidents. Tests were carried out to verify the efficiency of the developed prototype and it can be verified that the vehicle has a great applicability and optimizes the radiological protection process.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-04-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81841173","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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