ADELIA SAHYUN
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Resumo IPEN-doc 28004 Real time tracking of mobile radioactive sources2021 - SAHYUN, ADELIA; PEREZ, CLARICE A.It is vital that mobile radioactive sources remain under safe and secure control, at all times and the operator is notified in real time of their unauthorised removal from a fixed location, store or vehicle. This paper describes a system that constanily monitors mobile radioactive sources and provides a means to detect their location should unauthorised removal occur. Thousands of radiographic exposure devices are transported in the public domain every day and there are examples where the vehicle carrying a device has been stolen, not for the device itself but for the vehicle, which often leads to the device being discarded. Abandoning the device can lead to high risks of exposure for those who have secondary contact for example children or those attracted by its perceived intrinsic value. A lack of knowledge of the dangers of radiation has led some people in the past attempting and sometimes succeeding to open a device and remove the source. With other factors involved such as location, country and the intentions of those in possession of the device, it is therefore important that the device is located quickly, enabling recovery actions to begin as soon as possible. In addition, this paper encourages that such monitoring systems are more widely promoted in all countries and that an international code of practice is developed to assist when sources are transported internationally.Resumo IPEN-doc 28003 ALARA in focus2021 - PEREZ, CLARICE de F.A.; SAHYUN, A.By the 1950s the world had already realized the need to protect the people from the harmful effects of ionizing radiation. In 1955 ICRP established an incipient dose limitation system that has since been refined over the years. The development of the fundamental philosophy was completed in the ICRP Publication 26, in 1977, where the three principles of the dose limitation system were established and identified separately. The principles are known as: (a) justification, (b) optimization or (ALARA) As Low As Reasonably Achievable, and (c) dose limitation. The philosophy contained in Publication 26 was adopted by the IAEA in its Safety Series publication No. 9, 1982 edition, and in Brazil by the National Nuclear Energy Commission in 1988, with the publication of the regulations CNEN-NE3.01. The three principles remain valid and in the current editions of both documents. This paper describes the development of the ALARA concept from its origin to the present day, to provide an insight and understanding of its meaning and importance for the new generations of Radiation Protection Supervisors and other professionals who work directly and indirectly in areas that involve the use of ionizing radiation.Artigo IPEN-doc 27036 Study on the protection planning actions and response to nuclear or radiological emergency2016 - PEREZ, CLARICE F.A.; SAHYUN, ADELIA; FREITAS, KENIA A.M.Nuclear or Radiological emergencies can have as a consequence the rise of Deterministic effects, in the population involved, and/or Stochastic effects due to their doses. In these situations, protective actions need to be done in order to keep the doses in the affected population below the levels of deterministic effects and protective actions that might reduce the risk of stochastic effects should be adopted, minimizing the doses to reasonably achievable levels. This work presents a comparative study between the publication of IAEA Safety Series 109 and the document of the International Atomic Energy Agency GSG-2 "Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency" regarding the effective dose value system to be used as a basis to trigger protection actions in the Planning and Response to Nuclear or Radiological Emergencies that can reduce the risk of stochastic effects.Resumo IPEN-doc 27064 The evaluation of the real alpha value in Brazil and its projection until the year 20502016 - SAHYUN, ADELIA; GHOBRIL, CARLOS N.; PEREZ, CLARICE F.; SORDI, GIAN M.The real evolution of the alpha value in Brazil has been performed three times in 1993 and 2000 making use of the procedure advised by ICRP and in 2004 making use of the procedure recommended by the IAEA. In both, the first two papers were made various projections for the coming years until 2025. Because of the great social and economic crisis in which the country (Brazil) is going, we decided to reassess the alpha value of our country and compare it with the projections of the two previous papers. Therefor e, we decided to make a dollar correction from that time to the current dollar, comparing the purchasing power from that time to the current. This procedure has shown us the great gap of value in use and that the actual value should be two to three times h igher. By GDP per capita, we could calculate the alpha value updated to various countries including the European Union and compare them with the official value currently in use. In conclusion, we believe that all countries that adopt an alpha value should upgrade it to the present day.Artigo IPEN-doc 27060 Some suggestions to adequate the IAEA Safety Standards Series No. 49 according to the General Safety Requirements Part 3 from IAEA2016 - SAHYUN, ADELIA; GHOBRIL, CARLOS N.; PEREZ, CLARICE F.; SORDI, GIAN M.At that time of publication SSR49 two exposure situations were considered, namely: practices and interventions, with Naturally Occuring Radioactive Material (NORM) being considered as intervention exposures but acknowledging that some natural sources can have exposures resulting from practices. In the Ba sic Safety Standards (BSS) the exposure situations have been categorised as planned, emergency and existing. These three situations necessitate an update of SSR No.49 since NORM fits in the existing situation, i.e one in which the doses already exist and should be reduced. To reduce the doses will create radioactive waste that must be either treated or stored. This scenario raises a problem of defining the dividing line between existing and planned situations. The point of transistion from one situation to the other needs to be clarified in order to establish the necessary controls for an existing situation whilst providing the necessary controls needed for the planned situation. For the latter planned situation several questions arise as to whether certain requirements can be exempted and under what circumstances. This paper will examine what the authors consider most important in more detail with some suggestions made for further consideration.Artigo IPEN-doc 23038 The evaluation of the real alpha value in Brazil and its projection until the year 20502017 - PEREZ, CLARICE F.; GHOBRIL, CARLOS N.; SORDI, GIAN M.; SAHYUN, ADELIAWhen a cost–benefit analysis is applied to the optimization of practices involving radiation protection, the alpha value is used to determine the amount of money required to be invested in a practice to minimize radiation doses to acceptable levels. The alpha value is often linked to the gross domestic product (GDP) per capita, so the monetary reference value of person-Sievert can often be different in each country. Evaluation of the alpha value in Brazil was performed in 1993 and 2000 making use of the procedure advised by ICRP to produce projections up to 2015 and subsequently in 2004 by using the procedure recommended by the IAEA. This paper, in response to the social and economic situation in Brazil, calculates the alpha value and compares it with the projections of the 1993 and 2000 papers and includes a dollar correction to take account of the differences in the purchasing power from that time. This procedure illustrates the significant gap of value in use and that the actual value should be two to three times higher. By GDP per capita, the authors could calculate the alpha value updated to various countries including the European Union and compare them with the official value currently in use. In conclusion, it is believed that all countries that adopt an alpha value should upgrade it to the present day.Resumo IPEN-doc 06163 Background radiation doses at IPEN-CNEN/SP1997 - SANCHES, M.P.; SAHYUN, A.; SORDI, G.M.A.A.; RODRIGUES, D.L.Resumo IPEN-doc 06164 Distribution of radioactive material for Nuclear Medicine use in Brazil1997 - SAHYUN, A.; SORDI, G.M.A.A.; RODRIGUES, D.L.; SANCHES, M.P.Resumo IPEN-doc 06229 Criteria according to the National Commission of Nuclear Energy - CNEN, for the managing of radioactive waste in nuclear medicine1997 - SAHYUN, A.; SORDI, G.M.A.A.; SANCHES, M.P.; RODRIGUES, D.L.Resumo IPEN-doc 04657 Risk evaluation in consequence of abnormal situation with iodine-1311996 - GABURO, J.C.G.; SORDI, G.M.A.A.; SANCHES, M.P.; SAHYUN, A.