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Sample records for cnen

  1. Northeast project/CNEN

    International Nuclear Information System (INIS)

    Alves, R.N.; Ribeiro, G.F.; Lima, J.O.V.; Dornelles, G.H.; Laborne, J.J.; Sakamoto, L.H.; Lemos Junior, O.F.

    1987-10-01

    The subprojects from the Northeast/CNEN project, that aims to disseminate the benefits of nuclear energy are described. Those subprojects are the following: food conservation, energy, health, hydric resources, mineral and agriculture, all of them have as goal to improve the socio-economical conditions of the northeast population in Brazil. (E.G.) [pt

  2. CNEN resolution phohibits radioactive lightning rods

    International Nuclear Information System (INIS)

    1989-01-01

    After 15 years of irrestricted use in Brazil, the radioactive lightning rods were phohibited by Brazilian CNEN since the publication of a new law (Resolution number 4 of april 19,1989) published on may 9, 1989. All the existing ones will be removed at the time of their programed maintenance. (A.C.A.S.) [pt

  3. Chapter 9: Questions from CNEN specific exams

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2018-04-01

    The following are real questions from CNEN specific exams for obtaining the certification of RSO for gamma irradiators. These are questions that require essay answers, that are interpretative ones and therefore that may accept more than one interpretation, therefore more than one answer. For this reason, suggestions of answers will be presented in the second part of this chapter.

  4. Chapter 9: Questions from CNEN specific exams

    International Nuclear Information System (INIS)

    2018-01-01

    The following are real questions from CNEN specific exams for obtaining the certification of RSO for gamma irradiators. These are questions that require essay answers, that are interpretative ones and therefore that may accept more than one interpretation, therefore more than one answer. For this reason, suggestions of answers will be presented in the second part of this chapter

  5. Management report 2007 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2007-01-01

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous

  6. Management report 2007 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2007 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous.

  7. Implementation of the CNEN's safeguards laboratory

    International Nuclear Information System (INIS)

    Almeida, S.G. de

    1986-01-01

    The International Safeguards Agreements between Brazil and others countries has been concluded with the participation of the International Atomic Energy Agency (AIEA), and involve the Physical Protection and Control of Nuclear Material activities, which set up the National Safeguards System. The Safeguards Laboratory was constructed to the implementation and maintenance of this National Safeguards System, under responsability of CNEN's Safeguards Division, in order to carry out measurements of nuclear materials under safeguards. Technical requirements applied to the construction, setting up and operation of the laboratory are showed. The first results refer to the implementation of safeguards methods and techniques, as well as its participation within international scientific and technical co-operation programs in the safeguards area, through of them we wait its credencement by the AIEA as Regional Safeguards Laboratory for every countries of the Latin America. (Author) [pt

  8. Management report 2003 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2004-03-01

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2003, involving the government programs in the areas of nuclear safety, medicine application, technological development, administration and miscellaneous

  9. Management report 2003 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2003 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2003, involving the government programs in the areas of nuclear safety, medicine application, technological development, administration and miscellaneous.

  10. CNEN experience on bellows for sodium system

    International Nuclear Information System (INIS)

    Gai, A.; Casalini, P.

    1980-01-01

    In Italy work on the breeder reactors is being carried out in three main areas: The PEC reactor; Construction of the components for the Creys-Malville plant, the testing in support of this, and work on the SPX reactor; Standardized industrial supplies. With regard to the PEC reactor, design work for the system and a part of the components is being conducted mainly in Italy by CNEN and NIRA, with the experimental testing in support being conducted in Italy and abroad. With regard to the Creys-Malville plant and the SPX reactor programs, activities for the supply of the components and testing in support of them are being conducted within a tight framework of agreements between the research organizations and Italian and French industries. Finally, the standardized industrial supplies are developing autonomously, without any major research and development involvement. The differences in methodologies, procedures and organizations involved in the three above mentioned work areas and the relative limitation of activities conducted in the breeder reactor area in Italy have made the carrying out of a systematic, organic program for the use of sodium bellows impossible. In particular, until today no sodium testing program has been carried out on this component in Italy

  11. CNEN experience on bellows for sodium system

    Energy Technology Data Exchange (ETDEWEB)

    Gai, A; Casalini, P

    1980-02-01

    In Italy work on the breeder reactors is being carried out in three main areas: The PEC reactor; Construction of the components for the Creys-Malville plant, the testing in support of this, and work on the SPX reactor; Standardized industrial supplies. With regard to the PEC reactor, design work for the system and a part of the components is being conducted mainly in Italy by CNEN and NIRA, with the experimental testing in support being conducted in Italy and abroad. With regard to the Creys-Malville plant and the SPX reactor programs, activities for the supply of the components and testing in support of them are being conducted within a tight framework of agreements between the research organizations and Italian and French industries. Finally, the standardized industrial supplies are developing autonomously, without any major research and development involvement. The differences in methodologies, procedures and organizations involved in the three above mentioned work areas and the relative limitation of activities conducted in the breeder reactor area in Italy have made the carrying out of a systematic, organic program for the use of sodium bellows impossible. In particular, until today no sodium testing program has been carried out on this component in Italy.

  12. Management report 2004 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2005-03-01

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

  13. Management report 2006 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2007-03-01

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

  14. Radiotoxicological analysis at IPEN-CNEN/SP-Brazil

    International Nuclear Information System (INIS)

    Duarte, C.L.; Gaburo, J.; Bellintani, S.A.

    1987-01-01

    The methodology of control of internal contamination of handlers of radioactive materials is briefly described. The aim of IPEN-CNEN/SP-Brazil is the evaluation of occupational exposure of compounds of uranium, tritium, iodine-131, lead and fluorine among other ones. (M.A.C.) [pt

  15. Management report 2005 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    2006-03-01

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

  16. Management report 2004 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2004 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  17. Management report 2005 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2005 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  18. Management report 2006 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2006 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  19. Safeguard system of IPEN-CNEN/Sao Paulo - Brazil

    International Nuclear Information System (INIS)

    Araujo, Jose Adroaldo de; Enokihara, Cyro Teiti; Nakamura, Aparecida Tiyo O.

    1999-01-01

    The history, requirements, organization, and operation of the State System of Accounting and Control from the institute for Energetic and Nuclear Research (IPEN-CNEN/SP) are described. The implementation system at the institution take into consideration the national and international safeguards requirements. It has started by the nuclear material (U, Pu and Th) physical inventory taking, including their provenance and transformation. The earlier computerized accounting system used for control has been replaced by a new one developed by the National Authority (CNEN/SESAL). The optimized system has more flexibility, giving a more effective answer to any occurred change on Material Balance Area. The actual system make use of an effective methodology. (author)

  20. CNEN, IAEA and ISO normative requirements for measurement management

    International Nuclear Information System (INIS)

    Kibrit, Eduardo

    2009-01-01

    International standard ISO 10012:2003 establishes requirements for measurement management systems, including requirements for measurement processes and measuring equipment. ISO 9001:2008 presents requirements for quality management systems, including requirements for the control of monitoring and measuring equipment. ISO 17025:2005 presents general requirements for the competence of testing and calibration laboratories. In the nuclear field the requirements for measurement management are established by standards published by the International Atomic Energy Agency (IAEA), and in Brazil, by the National Nuclear Energy Commission (CNEN). The present paper presents and discusses the normative requirements for measurement management, considering requirements established by National Nuclear Energy Commission (CNEN), International Atomic Energy Agency (IAEA), and International Organisation for Standardisation (ISO). (author)

  1. Review of CNEN activities in the field of sodium fires

    Energy Technology Data Exchange (ETDEWEB)

    Gerosa, A [CNEN/CSN Casaccia, Rome (Italy)

    1979-03-01

    The problems related to sodium fires have received increased attention at CNEN in recent years. Sodium fires have been reported in several countries with a rate that is. relatively high if compared to the number of plants in operation. The consequences of fires have been usually quite limited but it appears that more adequate precautions could often be applied to minimize risk of more serious consequences. Many alternatives exist for fire prevention and for fire extinction, but the fact that many alternatives have not been sufficiently tested make choices rather difficult. CNEN has been facing the problem of sodium fire prevention and extinction in relation to: design of PEC reactor; design of experimental loops in its own centres (Casaccia and Brasimone); safe operation of the same loops and analysis of accidents and potential accident situations; design of facilities for sodium fire experiments; operation of sodium fire facilities; operation of sodium disposal facilities. It is worth mentioning that sodium is also utilized by italian concerns, where it is processed mostly as an intermediate product in the manufacture of tetraethyl lead. A recent accident in a TEL production plant in Italy (Trento in July 1978) has recently once more raised the question if provisions for sodium fire extinction were adequate. Small scale fires for training purposes have been performed by several experimenters at CNEN since 1965. A more systematic approach, initiated in 1973 at Brasimone Centre, has been interrupted after 1976 when studies for the construction of a larger experimental facility (SUPERSATANA) have been abandoned. In 1976 it was proposed a CNEN participation to the French Program ESMERALDA. An accord to run the ESMERALDA Project as a French-Italian common program has recently been taken. Experimental results are presented in this paper.

  2. Review of CNEN activities in the field of sodium fires

    International Nuclear Information System (INIS)

    Gerosa, A.

    1979-01-01

    The problems related to sodium fires have received increased attention at CNEN in recent years. Sodium fires have been reported in several countries with a rate that is. relatively high if compared to the number of plants in operation. The consequences of fires have been usually quite limited but it appears that more adequate precautions could often be applied to minimize risk of more serious consequences. Many alternatives exist for fire prevention and for fire extinction, but the fact that many alternatives have not been sufficiently tested make choices rather difficult. CNEN has been facing the problem of sodium fire prevention and extinction in relation to: design of PEC reactor; design of experimental loops in its own centres (Casaccia and Brasimone); safe operation of the same loops and analysis of accidents and potential accident situations; design of facilities for sodium fire experiments; operation of sodium fire facilities; operation of sodium disposal facilities. It is worth mentioning that sodium is also utilized by italian concerns, where it is processed mostly as an intermediate product in the manufacture of tetraethyl lead. A recent accident in a TEL production plant in Italy (Trento in July 1978) has recently once more raised the question if provisions for sodium fire extinction were adequate. Small scale fires for training purposes have been performed by several experimenters at CNEN since 1965. A more systematic approach, initiated in 1973 at Brasimone Centre, has been interrupted after 1976 when studies for the construction of a larger experimental facility (SUPERSATANA) have been abandoned. In 1976 it was proposed a CNEN participation to the French Program ESMERALDA. An accord to run the ESMERALDA Project as a French-Italian common program has recently been taken. Experimental results are presented in this paper

  3. Metrology in CNEN NN 3.05/13 standard

    International Nuclear Information System (INIS)

    Mello, Marina Santiago de

    2014-01-01

    The nuclear medicine exams are widely used tools in health services for a reliable clinical and functional diagnosis of a disease. In Brazil, the National Nuclear Energy Commission, through the norm CNEN-NN 3:05/13, provides for the requirements of safety and radiological protection in nuclear medicine services. The objective of this review article was to emphasize the importance of metrology in compliance with this norm. We observed that metrology plays a vital role as it ensures the quality, accuracy, reproducibility and consistency of the measurements in the field of nuclear medicine. (author)

  4. Electron beam accelerator facilities at IPEN-CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    Somessari, Samir L.; Silveira, Carlos G. da; Paes, Helio; Somessari, Elizabeth S.R. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], E-mail: somessar@ipen.br

    2007-07-01

    Electron beam processing is a manufacturing technique, which applies a focused beam of high-energy electrons produced by an electron accelerator to promote chemical changes within a product. At IPEN-CNEN/SP there are two electron beam accelerators Type Dynamitron{sup R} (manufactured by RDI- Radiation Dynamics Inc.) Job 188 and Job 307 models. The technical specifications for the Job 188 energy 1.5 MeV, beam current 25 mA, scan 1.20 m, beam power 37.5 kW and for the Job 307 energy 1.5 MeV, beam current 65 mA, Scan 1.20 m, beam power 97.5 kW. Some applications of the electron beam accelerator for radiation processing are wire and cable insulation crosslinking, rubber vulcanization, sterilization and disinfection of medical products, food preservation, heat shrinkable products, polymer degradation, aseptic packaging, semiconductors and pollution control. For irradiating these materials at IPEN-CNEN/SP, there are some equipment such as, underbeam capstan with speed control from 10 to 700 m/min; a track; a system to roll up and unroll wires and electric cables, polyethylene blankets and other systems to improve the quality of the products. (author)

  5. External dosimetry by Thermoluminescent Dosimetry Laboratory - IPEN/CNEN - Brazil

    International Nuclear Information System (INIS)

    Manzoli, Jose Eduardo; Carvalho, Ricardo Nunes

    2001-01-01

    The Thermoluminescence Dosimetry Laboratory, LDT - IPEN/CNEN - Brazil, executes around six thousand TLD readings monthly. It is responsible for the dose evaluation and registration and for all the manufacture process of preparation and sending the dosemeters which are used by IPEN itself, hospitals, industries, town halls, universities, etc. Although prepared to read many kinds of materials, actually the LDT reads only CaSO 4 :Dy detector chips. Chips, heating molds, plastic packaging and almost every material or instrument are made right here at IPEN. The readings are performed in a Bicron Harshaw TLD model 5500, but an old model 2000-AB is ready to be used if necessary. In this work it is presented some features of this important service realized to the IPEN workers and to the community. (author)

  6. Isochronous variable energy cyclotron of IPEN-CNEN/SP (Brazil)

    International Nuclear Information System (INIS)

    Lucki, G.; Zanchetta, A.A.; Gouveia, S.; Klein, H.

    1984-01-01

    The cyclotron CV-28 installed at the Radiation Damage Division of IPEN-CNEN/SP is a multi-particle radiation source where protons, deuterons, 3 He ions and alpha particles can be accelerated with variable energy up to 24, 14, 36 and 28 MeV, respectively. The cyclotron is a versatile machine that can be applied in research and development of : radioisotope production - materials science - nuclear physics - activation analysis and others. First internal beam with 24 MeV protons has been obtained in April 23, 1981. First irradiation of Cu sample, at the external beam (beam current 1.5 μA), with 28 MeV alpha particles was performed in December 29, 1983. Main characteristics of the cyclotron are given together with a description of peripheral systems and experimental capability. Presently the accelerator is being optimized for cpontinuous running. (Author) [pt

  7. Industrial radioprotection - interpretations of the standard CNEN-NE-3.01

    International Nuclear Information System (INIS)

    Dagnino, R.; Zaniolo, C.

    1989-01-01

    The safety standard established by Comissao Nacional de Energia Nuclear - Brazilian CNEN, to rule the activities related to radioprotection, embodies various professionals activities. In this article a specific analysis about the application of the standard to industry is presented. (author)

  8. Regulatory guides for qualifying the calculation methodology of Furnas by CNEN

    International Nuclear Information System (INIS)

    1987-10-01

    Regulatory guides are presented which will be used for qualifying the calculation methodology of FURNAS by CNEN, in the areas of Neutronics, Thermohydraulics, Accident Analysis and Fuel Rod Performance, as applied to Angra 1 NPP. (Author) [pt

  9. Performance of the CNEN MHD Blow-Down Loop Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bertolini, E.; Brown, R.; Gasparotto, M.; Gay, P.; Toschi, R. [Laboratorio Conversione Diretta, CNEN, Frascati (Italy)

    1968-11-15

    The CNEN facility has been designed, manufactured and used for alkali-seeded noble gas MHD energy conversion research, as the major experimental effort during the first five-year CNEN Research Programme on MHD. The main specifications and the general arrangement with information on preliminary commissioning tests of some components were given at the Salzburg Symposium. Since then the facility has been successfully commissioned and from March 1967 has been working on MHD experiments. Efforts were made to reduce any adverse effects on the experimental MHD results that were due to inherent limitations of an experimental apparatus (particularly under open-circuit conditions). Great emphasis was placed on problems of caesium vaporization and the mixing with helium, the purity level of the mixture, measurements and the control system. The insulation of the plasma from ground was carefully treated, increasing the ratio between insulator resistance and typical plasma resistance as much as possible. Fluidynamic tests at room and high temperatures have shown that stability in the gas parameters (temperature, pressure and mass flow) can be maintained within few per cent for tens of seconds after a transient, giving a behaviour similar to a continuously running system. The high- temperature, alumina pebble-bed heater has successfully operated, bringing the helium-caesium mixtures up to 2000 Degree-Sign K and up to 4 atm abs pressure, and undergoing seven thermal cycles, for a total of more than 2000 hours operation at top temperature. Preheated generator ducts using alumina as insulator and tantalum for electrodes performed satisfactorily, very much attention having been given in the design to reduction of thermal shocks and to obviating possible paths for caesium leakage and short-circuiting of electrode leads. The pulsed liquid nitrogen precooled magnet has been run for about 50 pulses at high field ( Asymptotically-Equal-To 4.5 tesla) with an operating time of about 10

  10. The IPEN/CNEN-SP PSD neutron diffractometer

    International Nuclear Information System (INIS)

    Parente, Carlos Benedicto Ramos; Mazzocchi, Vera Lucia; Mascarenhas, Yvonne Primerano

    2004-01-01

    Full text: A new IPEN-CNEN/SP neutron powder diffractometer is under construction at the 4 MW thermal IEA-R1m research reactor. It is an upgrading of the old IPEN-CNEN/SP multipurpose neutron diffractometer. The main modifications introduced in the old instrument are: installation of a position sensitive detector (PSD) and a bent perfect single crystal monochromator (a focusing Si monochromator). The PSD is formed by eleven linear detector elements, clamped together at each end to form a rigid plane. The PSD is installed in a detector shielding which is supported by two arms fixed in a large rotary table. This table provides the instrument with the 2θ angular movement. A smaller rotary table, placed underneath and concentric with the larger one, provides the ω(θ) movement. Both tables are driven by a computer controlled geared mechanism. The computer also makes the data acquisition. A rotating-oscillating collimator, placed at the entrance to the detector shielding, eliminates parasitic scattering from furnace or cryorefrigerator heat shields in the vicinity of the sample. The collimator also makes the PSD less sensitive to ambient background. The PSD spans an angular range of 20 deg of a diffraction pattern, resulting in a quite good resolution for the instrument. An extended powder diffraction pattern can be obtained by moving the detector and collecting the data in 20 deg segments. With a take-off angle of 84 deg, the monochromator can be positioned to produce 4 different wavelengths, namely 1.111, 1.399, 1.667 and 2.191 A. Other parts constructed for the new instrument are: a in-pile collimator, a monochromatic beam collimator and a neutron shield, large enough to accommodate the monochromator, a beam shutter and the monochromatic beam collimator. In comparison to the former instrument, the new diffractometer will have better resolution and will be ca. 600 times faster in data acquisition. At the present time, the new instrument is in the final steps of

  11. Anions environmental monitoring control at CNEN-IPEN/SP-Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Villa, Sabrina M.; Marques, Joyce R.; Monteiro, Lucilena R.; Cotrim, Marycel E.B.; Pires, Maria Aparecida F., E-mail: lrmonteiro@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The Nuclear and Energy Research Institute IPEN-CNEN/SP, to comply with guidelines and basic procedures to be observed by its installation regarding environmental control actions, related with conventional effluent release started in 2007 the Environmental Monitoring Program for stable chemical compounds (PMA-Q). This program includes, besides others parameters, ionic species such as Fluoride, Chloride, Nitrite-N, Nitrate-N and Sulfate, measured by Ion Chromatography. Among these compounds, Fluoride and Chloride are regulated in effluent discharges by CONAMA's Resolution 430/2011 and the Sao Paulo State Decree 8468/76. Fluoride, Chloride, Nitrite-N, Nitrate-N in groundwater are regulated by CONAMA's Resolution 396/2008. Considering the legal requirements, every year this program is revised and improvement actions are planned and implemented. The present paper will discuss these improvements to determine the individual performance of the laboratory related to those tests performed by ion chromatography. The adequacy actions performed were the construction of control charts (internal quality control) and the interlaboratory proficiency tests regular participation (external quality control). With these quality control actions it was possible to monitor continuously the laboratory performance, to identify and resolve analytical problems and also interlaboratory differences, to add value to the essay quality control and to provide additional confidence to the institutional program PMA-Q. The recent change in legislation by CONAMA Resolution 430/2011 and the requirements of Resolution CONAMA 396/2008 improvement requirements are also discussed in this work. (author)

  12. Neutron tomography at IPEN-CNEN/SP: images and applications

    Energy Technology Data Exchange (ETDEWEB)

    Pugliesi, Reynaldo; Pereira, Marco Antonio Stanojev; Andrade, Marcos Leandro Garcia, E-mail: pugliesi@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2016-07-01

    Full text: The neutron tomography is a non destructive testing technique used to inspect the internal structure of a sample by means of tridimensional digital images. Because of the neutron-matter interaction characteristics this technique can be used to inspect hydrogen-rich substances like ceramics, oil, grease, water, rubber, blood and others, even wrapped by thick metal layers. In this way, the information provided by neutrons are complementary to the ones provided by X-rays. The Brazilian Institute for Nuclear Technology IPEN-CNEN/SP has an equipment for neutron tomography which since Nov/2011 is operational and installed at the IEA-R1 Nuclear Research Reactor. This equipment is able to provide high quality tomographs and some important results obtained for Proton Exchange Membranes (PEM) cell, for an archaeological sample and for pottery, will be presented. Furthermore, details of its construction and its versatility, in the sense that by means of small adjustments is possible to obtain images by other neutron imaging techniques, will be also presented. Is very important enhance that the high quality of the obtained images is due to the excellence of the IEA-R1 reactor which is able to furnish neutron beams with adequate intensity for such purpose. (author)

  13. Anions environmental monitoring control at CNEN-IPEN/SP-Brazil

    International Nuclear Information System (INIS)

    Villa, Sabrina M.; Marques, Joyce R.; Monteiro, Lucilena R.; Cotrim, Marycel E.B.; Pires, Maria Aparecida F.

    2013-01-01

    The Nuclear and Energy Research Institute IPEN-CNEN/SP, to comply with guidelines and basic procedures to be observed by its installation regarding environmental control actions, related with conventional effluent release started in 2007 the Environmental Monitoring Program for stable chemical compounds (PMA-Q). This program includes, besides others parameters, ionic species such as Fluoride, Chloride, Nitrite-N, Nitrate-N and Sulfate, measured by Ion Chromatography. Among these compounds, Fluoride and Chloride are regulated in effluent discharges by CONAMA's Resolution 430/2011 and the Sao Paulo State Decree 8468/76. Fluoride, Chloride, Nitrite-N, Nitrate-N in groundwater are regulated by CONAMA's Resolution 396/2008. Considering the legal requirements, every year this program is revised and improvement actions are planned and implemented. The present paper will discuss these improvements to determine the individual performance of the laboratory related to those tests performed by ion chromatography. The adequacy actions performed were the construction of control charts (internal quality control) and the interlaboratory proficiency tests regular participation (external quality control). With these quality control actions it was possible to monitor continuously the laboratory performance, to identify and resolve analytical problems and also interlaboratory differences, to add value to the essay quality control and to provide additional confidence to the institutional program PMA-Q. The recent change in legislation by CONAMA Resolution 430/2011 and the requirements of Resolution CONAMA 396/2008 improvement requirements are also discussed in this work. (author)

  14. Radiological accident with Iodine-131 in the Radioisotope Division at IPEN-CNEN/SP (Brazil)

    International Nuclear Information System (INIS)

    Sanches, Matias Puga; Rodrigues, Demerval Leonidas

    1997-01-01

    The accident occurred in the first week of May 1995, in the Radioisotope Division-TPI, involving two tubes containing a total volume of 3 ml, aqueous solution of N Al 1 31, with 370 MBq and 1480 MBq activity is reported. Part of installation and six workers involved in the distribution process were contaminated with 131 I, but there were no contamination outside the building. The workers were decontaminated and the received radiation doses were evaluated by the Radiotoxicological Laboratory of IPEN-CNEN/SP together with IRD-CNEN/RJ. The building involved was closed and the activities stopped until the complete decontamination by the Radioprotection experts of IPEN-CNEN/SP. (author)

  15. Performance of IPEN/CNEN-SP Neutron Activation Analysis Laboratory for microelement determinations in proficiency testing

    International Nuclear Information System (INIS)

    Armelin, Maria Jose A.; Saiki, Mitiko; Souza, Gilberto B. de; Nogueira, Ana Rita A.

    2009-01-01

    The performance of Neutron Activation Laboratory, IPEN - CNEN/SP, was evaluated for the Ca, Fe, K, Mn, Na and Zn determinations in animal feed samples for ruminants through a proficiency test (PT) program. This PT program is organized by EMBRAPA Cattle Southeast to evaluate laboratories that analyze animal feed samples. Considering the fractions of satisfactory z-scores (%) of evaluated analytes to determine the laboratories performance, the general performance indicator obtained by IPEN - CNEN/SP ranged from 90 to 95% of the satisfactory results during the period of participation in the evaluation, four years. (author)

  16. CNEN-NN 6.04 standard adaptation in Brazil for industrial radiographic work in occupied areas or public roads

    International Nuclear Information System (INIS)

    Teixeira, P.B.; Aquino, J.O. de; Souza, L.A. de

    1996-01-01

    The industrial radiographic work that uses mobile equipment in Brazil must be in compliance with the National Commission of Nuclear Energy (CNEN) Regulation CNEN-NN 6.04. It states that every works that employs radiographic equipment in occupied areas or public roads requires a specific radiation protection procedure. This procedure must be approved by the CNEN at least fifteen days before starting the job. It is not always possible to the users to get their licensing work at time, because the industrial radiography jobs need immediate actions. Furthermore, the CNEN-NN 6.04 Regulation does not specify what type of information the procedures should involve, so that some important information had been often missed, causing a delaying in the licensing procedures. The corrective and preventive actions taken by the CNEN to optimize this kind of jobs and to overcome bureaucratic difficulties are described. A standard radiation protection procedure is also presented. (authors). 2 refs., 2 tabs

  17. Reduction of doses in the environment of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Rodrigues, D.L.; Sanches, M.P.; Sordi, G.M.A.A.

    1997-01-01

    According Brazilian legislation, individual dose levels at IPEN-CNEN/SP entitle staff to receive 10% of their base salary as additional health allowance, 20 holidays per semester, and special retirement after 25 years of work. The present work presents estimates of cost due to health allowances and recommends reduction of individual dose levels for staff including non-radiological personnel

  18. Utilization of basic directives radioprotection norm in industrial radiography services CNEN-3.01

    International Nuclear Information System (INIS)

    Dagnino, R.

    1989-01-01

    The characteristics of the introduction of the standart CNEN - 3.01 - Diretrizes Basicas de Radioprotecao in industrial radiography field, mainly referred to service companies are presented. Some suggestions are proposed in order that the accomplishment of these principles does not stop the works which use this inspection technique. (author)

  19. Implantation of licensing norm for industrial radiography installations - Norm CNEN-NE-604 Rev.1

    International Nuclear Information System (INIS)

    Heilbron Filho, P.F.L.; Oliveira, S.M.V. de.

    1988-04-01

    The results of audits carried out by DIN/CNEN (Department of Nuclear Installations) in firms of Rio de Janeiro and Sao Paulo, Brazil, that use industrial radiography for implantation of the norm of installation licensing, are presented. (M.C.K.) [pt

  20. Large sample neutron activation analysis: establishment at CDTN/CNEN, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Menezes, Maria Angela de B.C., E-mail: menezes@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Jacimovic, Radojko, E-mail: radojko.jacimovic@ijs.s [Jozef Stefan Institute, Ljubljana (Slovenia). Dept. of Environmental Sciences. Group for Radiochemistry and Radioecology

    2011-07-01

    In order to improve the application of the neutron activation technique at CDTN/CNEN, the large sample instrumental neutron activation analysis is being established, IAEA BRA 14798 and FAPEMIG APQ-01259-09 projects. This procedure, LS-INAA, usually requires special facilities for the activation as well as for the detection. However, the TRIGA Mark I IPR R1, CDTN/CNEN has not been adapted for the irradiation and the usual gamma spectrometry has being carried out. To start the establishment of the LS-INAA, a 5g sample - IAEA/Soil 7 reference material was analyzed by k{sub 0}-standardized method. This paper is about the detector efficiency over the volume source using KayWin v2.23 and ANGLE V3.0 software. (author)

  1. The CNEN, Flamanville 3 and the English project of Hinkley Point

    International Nuclear Information System (INIS)

    Reber, Laurent

    2014-01-01

    The CNEN is the National Centre of Nuclear Equipment. It's an engineering unit of EDF. After a brief presentation of this department which is one of the six engineering departments of EDF, the CNEN manager presents the Flamanville EPR, its design characteristics and objectives (notably in terms of safety and availability). He comments the status of the construction, gives some explanations to the difficulties faced during this construction. He outlines the greater importance given to safety with respect to reactors of previous generations. Then, he addresses the British Hinkley Point project, its context, the requirements expressed by the British nuclear safety authority. As studies must be performed in the host country, the British nuclear engineering organisation is indicated. The content of the contract between EDF and the British is summarized

  2. Pretreatment procedures applied to samples to be analysed by neutron activation analysis at CDTN/CNEN

    International Nuclear Information System (INIS)

    Francisco, Dovenir; Menezes, Maria Angela de Barros Correia

    2009-01-01

    The neutron activation technique - using several methods - has been applied in 80% of the analytical demand of Division for Reactor and Analytical Techniques at CDTN/CNEN, Belo Horizonte, Minas Gerais. This scenario emphasizes the responsibility of the Laboratory to provide and assure the quality of the measurements. The first step to assure the results quality is the preparation of the samples. Therefore, this paper describes the experimental procedures adopted at CDTN/CNEN in order to uniform conditions of analysis and to avoid contaminations by elements present everywhere. Some of the procedures are based on methods described in the literature; others are based on many years of experience preparing samples from many kinds of matrices. The procedures described are related to geological material - soil, sediment, rock, gems, clay, archaeological ceramics and ore - biological materials - hair, fish, plants, food - water, etc. Analytical results in sediment samples are shown as n example pointing out the efficiency of the experimental procedure. (author)

  3. k0IAEA software validation at CDTN/CNEN, Brazil, using certified reference materials

    International Nuclear Information System (INIS)

    Menezes, M.A.B.C.; Jacimovic, R.

    2007-01-01

    The IAEA distributed the k 0I AEA software package program to several laboratories. The Laboratory for Neutron Activation Analysis, at CDTN/CNEN (Centro de Desenvolvimento da Tecnologia Nuclear/Comissao Nacional de Energia Nuclear), Belo Horizonte, Brazil, acquired the k 0I AEA software package during the Workshop on Nuclear Data for Activation Analysis, 2005, held at the Abdus Salam International Centre for Theoretical Physics, Trieste, Italy. This paper is about the validation procedure carried out at the local laboratory aiming at the validation of the k 0I AEA software package. After the software was set up according to the guidelines, the procedure followed at CDTN/CNEN to validate the k 0I AEA software was to analyse several reference materials. The overall results pointed out that the k 0I AEA software is working properly. (author)

  4. Control system and nuclear materials inventory at IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Araujo, Jose Adroaldo de; Enokihara, Cyro Teiti

    2002-01-01

    The history, requirements, organization, and operation of the State System of Accounting and Control from the Institute for Energetic and Nuclear Research (IPEN-CNEN/SP) are described. The implementation system at the institution take into consideration the national and international safeguards requirements. It has started by the nuclear material (U, Pu and Th) physical inventory taking, including their provenance and transformation. The earlier computerized accounting system used for control has been replaced by a new one developed by the National Authority (CNEN/CSG). The optimized system has more flexibility, giving a more effective answer to any occurred change on Material Balance Area. The present system make use of an effective methodology. (author)

  5. The insulin radioimmunoassay kit prepared by IPEN-CNEN/SP - Brazil

    International Nuclear Information System (INIS)

    Mesquita, C.H. de; Silva, C.P.G. da; Hamada, M.M.

    1985-11-01

    The specification and methodological aspects of the insulin radioimmunoassay kit produced by IPEN-CNEN/SP - Brazil are described. The limitations taking care and the following quality control parameters or procedures are discussed: specific radioactivity, comparison between two insulin - 125 I purification procedures, affinity constant 'K' of the antigen - antibody reaction, minimal detectable dose (MDD), kinetics degradation of the radioinsulin, radioassay imprecision profile, radioassay performance temperature dependence and normal values histogram. (Author) [pt

  6. Replacing nuclear staff: The proactively work at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Pupak, M.O.; Rogero, J.R.

    2004-01-01

    The purpose of this paper was to bring the actual situation of Nuclear Education and Training in Brazil. Accordingly, this paper overviewed the situation of the educational matter on Latin America, especially in Brazil, in terms of efficiency and effectiveness of its superior education system. Mainly this paper pointed out for the replacing of nuclear staff and the proactive work of the Energy and Nuclear Research Institute (IPEN) of the Brazilian Nuclear Energy Commission (CNEN). (author)

  7. Replacing nuclear staff: The proactive work at IPEN/CNEN-SP-Brazil

    International Nuclear Information System (INIS)

    Pupak, M.O.; Rogero, J.R.

    2005-01-01

    The purpose of this paper was to bring out the actual situation of Nuclear Education and Training in Brazil. Accordingly, this paper overviews the situation of educational matters in Latin America, especially in Brazil, in terms of efficiency and effectiveness of its superior education system. Mainly, this paper points out the replacing of nuclear staff and the proactive work of the Energy and Nuclear Research Institute (IPEN) of the Brazilian Nuclear Energy Commission (CNEN). (author)

  8. Implementation of the automated potentiometric titration method for total U at the CNEN Safeguard Laboratory, Brazil

    International Nuclear Information System (INIS)

    Cristiano, Barbara F.G.; Delgado, Jose U.; Araujo, Radier M.S. de; Silva, Jose W.S. da; Barros, Pedro D. de

    2009-01-01

    Brazilian nuclear facilities, in accordance with the regulation CNEN-NN-2.02, must have available measurement systems which allow to determine their nuclear material inventories. For the evaluation and the follow up the performance of the involved laboratories in those measurement systems, the accomplishment of interlaboratory comparison programmes becomes fundamental. Therefore, the implementation of the potentiometric titration viewing the characterization of uranium samples, represents an reference element for the Brazilian programs

  9. SUS in nuclear medicine in Brazil: analysis and comparison of data provided by Datasus and CNEN.

    Science.gov (United States)

    Pozzo, Lorena; Coura Filho, George; Osso Júnior, João Alberto; Squair, Peterson Lima

    2014-01-01

    To investigate the outpatient access to nuclear medicine procedures by means of the Brazilian Unified Health System (SUS), analyzing the correspondence between data provided by this system and those from Comissão Nacional de Energia Nuclear (CNEN) (National Commission of Nuclear Energy). Data provided by Datasus regarding number of scintillation chambers, outpatient procedures performed from 2008 to 2012, administrative responsibility for such procedures, type of service providers and outsourced services were retrieved and evaluated. Also, such data were compared with those from institutions certified by CNEN. The present study demonstrated that the system still lacks maturity in terms of correct data input, particularly regarding equipment available. It was possible to list the most common procedures and check the growth of the specialty along the study period. Private centers are responsible for most of the procedures covered and reimbursed by SUS. However, many healthcare facilities are not certified by CNEN. Datasus provides relevant data for analysis as done in the present study, although some issues still require attention. The present study has quantitatively depicted the Brazilian reality regarding access to nuclear medicine procedures offered by/for SUS.

  10. Nuclear Information Center: 25 years of CNEN in the support of science and technology

    International Nuclear Information System (INIS)

    Sayao, Luiz Fernando; Monteiro de Barros, Anna Christina T.

    1995-01-01

    The 25 years of the Nuclear Information Centre of the Brazilian Nuclear Energy Commission - CIN/CNEN, and the role played in the context of Brazilian scientific and technological development is analyzed under two points of view: as database producer and information services provider as well as generator of knowledge and technology in the field of Information Science. The pioneer role of the Centre, not only in developing software for bibliographic information handling and in building a marketing model to information services but also contributing for the growth of database usage culture in Brazil is described. Cooperation, decentralization and sharing of resources are emphasized as the main characteristics of the work developed by the CIN/CNEN staff. Finally, the international background of CIN/CNEN coordinating Latin-American Projects as well as an active member of INIS - International Nuclear Information System, IAEA and more recently as the Brazilian representative to ETDE - Energy Technology Data Exchange is shown. IEA energy database is also discussed. (author)

  11. SUS in nuclear medicine in Brazil: analysis and comparison of data provided by Datasus and CNEN*

    Science.gov (United States)

    Pozzo, Lorena; Coura Filho, George; Osso Júnior, João Alberto; Squair, Peterson Lima

    2014-01-01

    Objective To investigate the outpatient access to nuclear medicine procedures by means of the Brazilian Unified Health System (SUS), analyzing the correspondence between data provided by this system and those from Comissão Nacional de Energia Nuclear (CNEN) (National Commission of Nuclear Energy). Materials and Methods Data provided by Datasus regarding number of scintillation chambers, outpatient procedures performed from 2008 to 2012, administrative responsibility for such procedures, type of service providers and outsourced services were retrieved and evaluated. Also, such data were compared with those from institutions certified by CNEN. Results The present study demonstrated that the system still lacks maturity in terms of correct data input, particularly regarding equipment available. It was possible to list the most common procedures and check the growth of the specialty along the study period. Private centers are responsible for most of the procedures covered and reimbursed by SUS. However, many healthcare facilities are not certified by CNEN. Conclusion Datasus provides relevant data for analysis as done in the present study, although some issues still require attention. The present study has quantitatively depicted the Brazilian reality regarding access to nuclear medicine procedures offered by/for SUS. PMID:25741070

  12. Radiological accident with Iodine-131 in the Radioisotope Division at IPEN-CNEN/SP (Brazil); Acidente radiologico com iodo-131 nas instalacoes da Divisao de Radioisotopos do IPEN-CNEN/SP (Brasil)

    Energy Technology Data Exchange (ETDEWEB)

    Sanches, Matias Puga; Rodrigues, Demerval Leonidas [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-12-31

    The accident occurred in the first week of May 1995, in the Radioisotope Division-TPI, involving two tubes containing a total volume of 3 ml, aqueous solution of N Al{sup 1}31, with 370 MBq and 1480 MBq activity is reported. Part of installation and six workers involved in the distribution process were contaminated with {sup 131} I, but there were no contamination outside the building. The workers were decontaminated and the received radiation doses were evaluated by the Radiotoxicological Laboratory of IPEN-CNEN/SP together with IRD-CNEN/RJ. The building involved was closed and the activities stopped until the complete decontamination by the Radioprotection experts of IPEN-CNEN/SP. (author) 2 refs., 1 fig., 1 tab.; e-mail: msanches at net.ipen.br; dirodri at net.ipen.br

  13. Proposal for intake model for workers at IPEN-CNEN/SP who handle 131 I

    International Nuclear Information System (INIS)

    Todo, A.S.; Potiens Junior, A.J.; Gaburo, J.C.; Sanches, M.P.; Oliveira, E.M.

    1997-01-01

    The intake model for the two groups of workers at IPEN-CNEN/SP is presented. They handle iodine compounds during the processing of irradiated targets and at labeling of radiopharmaceutical compounds. The intake model for the workers are proposed from the knowledge of the activities carried out in the plant and the internal monitoring program of the workers. In this study, the intake is considered to be taken uniformly during the days of major activities carried out by the workers. In practice, the application of this model has be shown suitable, for the studied groups

  14. Nuclear occupational safety in uranium conversion facility at the IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Gaburo, J.; Silva, T. de M. da; Sordi, G.-M.A.A.

    1988-10-01

    After a brief description of the operations involved in the Uranium Process Conversion at the IPEN-CNEN/SP it is shown the principal radioactive sources exposure, the health physics procedures implemented and finally are discussed the doses received by the workers. The health physics measurements includ air sampling, internal contamination control by bioassay analysis and workplace monitoring for external radiation. The air monitoring results show in some points that the radiation levels are very near of the 3/10 of the DAC, but the permanence of the workers are very short. This fact is confirmed by the results of the bioassay analysis performed on the workers. (author) [pt

  15. Eurex Euratom-CNEN agreement tenth annual report for the year 1974

    International Nuclear Information System (INIS)

    Calleri, G.; Dworschak, H.; Rolandi, G.

    1977-01-01

    This report covers the tenth year of activity in connection with the Eurex project since the signing of Euratom-CNEN Agreement no.001-64-11 RC-II for the construction, operation use for industrial research purposes of the Eurex plant. The report summarizes the contents of three four-monthly reports published during 1974 and presents a summary statement of expenditure. The report contains the following parts: management of the reprocessing division; planning and construction of the plant (modification); cold tests; laboratory and pilot-scale experiments prior to start-up of the plant; industrial operation of the plant

  16. Designing a water calorimeter as primary standard of gamma rays at IPEN/CNEN

    International Nuclear Information System (INIS)

    Cintra, Felipe B. de; Caldas, Linda V.E.

    2013-01-01

    This work aims to describe the present stage and the next steps of the development of a water calorimeter of the Calibration Laboratory of IPEN/CNEN. This calorimeter will be used as a primary standard of gamma ray sources at the laboratory. Between the design and the construction step it will be shown how this model was chosen and how it is modeled virtually with computer simulation. The two main codes used, MCNP and Fluent, to characterize the prototype before its construction are presented. (author)

  17. The implementation and application of the WASP-III at CNEN/Brazil

    International Nuclear Information System (INIS)

    Sakamoto, L.H.; Lima, J.O.V.; Silva, R.C.O. da.

    1983-09-01

    The main dificulties faced in the implementation of the WASP-III on the Honeywell Bull DPS 6/64 computer at CNEN, are discribed. After the implementation, tests making use of input data provided by International Atomic Energy Agency - IAEA were performed and comparative results from accomplishment peiods of time are presented with the basic characteristics of the computer employed and the modifications carried out to adapt the programm. The WASP-III was applied to middle-sized electric system based upon the Brazilian North/Northeast System. (Author) [pt

  18. 123 I production using CV-28 cyclotron from IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Mestnik, S.A.C.; Mengatti, J.; Nieto, W.; Yanagawa, S.I.; Sumiya, L.C.A.; Silva, C.P.G.; Osso Junior, J.A.

    1992-01-01

    The main conditions for iodine 123 production by 124 Te (p,2 n) 123 I reaction were presented, using the cyclotron CV-28 at IPEN-CNEN/SP, with protons of E max = 24 MeV. Two types of targets (Te O 2 and Te O 2 + 2% Al 2 O 3 ) and the influence of Al 2 O 3 in iodine release were studied. After the selection, the 124 Te O 2 (96,2%) target, was melted in platinum support and irradiated with proton current until 12 mu A. The separation of 123 I was made by dry distillation, using induction furnace and O 2 atmosphere. (C.G.C.)

  19. Performance of the Radioprotection Engineering Group in the new structure of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Sahyun, A.; Sordi, G.M.A.A.

    1992-01-01

    A comparison between the old and now CNEN (Brazilian Nuclear Energy Commission) organizational structure was performed. The new structure lead to a new IPEN (Nuclear and Energetics Research Institute) organization and also to gave use to a Radioprotection Engineering Area, The principal modification raised a second block already in accomplishment. The main aim of the Radioprotection Engineering Area is to turn personnel team interested, concerned, dexterous, dynamic and competitive on their activities besides to provide it of a continuously improvement and updating about technical activities in radiation protection. From these results an evaluation of possible drawbacks and ways to overcome them will be performed. (author)

  20. Control and reception of out of use radioactive sources at the CDTN/CNEN, Minas Gerais, Brazil; Controle e recebimento de fontes radioativas fora de uso no CDTN/CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Reis, Luiz C.A.; Guzella, Marcia F.R.; Seles, Sandro R.N.; Cuccia, Valeria, E-mail: reislca@cdtn.b, E-mail: mfrg@cdtn.b, E-mail: seless@cdtn.b, E-mail: vc@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-10-26

    For reception of the received sources and for accomplish with CNEN regulations and IAEA recommendations, the CDTN have implanted a system for receiving those sources and all the procedures for effective control and recovering of information. The CDTN posses a source deposit, a data bank for the inventory and also a Laboratory for Treatment of Sealed Sources

  1. Act No. 1240 of 15 December 1971. Regulations concerning the restructuring of the National Nuclear Energy Commission (CNEN)

    International Nuclear Information System (INIS)

    1972-01-01

    This Act which annuls the preceding Act of 1960 with the exception of Sections 12 to 16, confirms the CNEN's responsibilities. As opposed to the previous Act this Act contains provisions concerning the National Institute for Nuclear Physics (INFN). (NEA) [fr

  2. Control and reception of out of use radioactive sources at the CDTN/CNEN, Minas Gerais, Brazil

    International Nuclear Information System (INIS)

    Reis, Luiz C.A.; Guzella, Marcia F.R.; Seles, Sandro R.N.; Cuccia, Valeria

    2011-01-01

    For reception of the received sources and for accomplish with CNEN regulations and IAEA recommendations, the CDTN have implanted a system for receiving those sources and all the procedures for effective control and recovering of information. The CDTN posses a source deposit, a data bank for the inventory and also a Laboratory for Treatment of Sealed Sources

  3. A database system for the control of radioactive effluents generated by the IPEN-CNEN/SP installations

    International Nuclear Information System (INIS)

    Maduar, M.F.

    1992-01-01

    A PC-compatible database system has been developed in order to optimize the control of liquid and gaseous effluents generated by the installations of IPEN-CNEN/SP. The system implements source-term generation, optimizes the discharge control of the effluents and allows several ways for the retrieval of data concerning to the effluents. (author)

  4. Analysis of scientific and technical production of IPEN-CNEN/SP in the period of 1984 to 1988

    International Nuclear Information System (INIS)

    Sugai, M.

    1989-01-01

    An analysis of scientific and technical production of Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP in the period of 1984 to 1988 is presented. It includes articles, dissertation, thesis, books, reports and papers presented in scientific meetings or published in the Publicacao IPEN series. (C.M.)

  5. Radiological impact evaluation on the aquatic ecosystems surrounding IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Jacomino, Vanusa F.; Maduar, Marcelo F.; Bellintani, Sandra A.; Mazzilli, Barbara P.

    1996-01-01

    In order to control the discharge of radioactive materials into the aquatic system surrounding IPEN-CNEN/SP, an monitoring program has been carried out on a routine basis. All the liquid effluent generated by the IPEN facilities are released into the Pinheiros river at two different discharge points located 2 km apart. In the present paper the source term measured during the period 1985 to 1984 is presented, as well as the effective equivalent dose received by public individuals for each critical pathway. These results showed that the total activity released into the Pinheiros river is just a small fraction of the receiving capacity of the environment. The estimated annual doses during the period of study were always below 1/10 of the primary limit for the public individual as established by the International Commission of Radiological Protection, which is 1 mSv/year. (author)

  6. Incineration facility for combustible solid and liquid radioactive wastes in IPEN-CNEN - Sao Paulo

    International Nuclear Information System (INIS)

    Krutman, I.; Grosche Filho, C.E.; Chandra, U.; Suarez, A.A.

    1987-01-01

    A system for incinerating the combustible solid and liquid radioactive wastes was developed in order to achieve higher mass and volume reduction of the wastes generated at IPEN-CNEN/SP or received from other institutions. The radioactive wastes for incineration are: animal carcasses, ion-exchange resins, contaminated lubricant oils, cellulosic materials, plastics, etc. The optimization of the process was achieved by considering the following factors: selection of better construction and insulating material; dimensions; modular design of combustion chambers to increase burning capacity in future; applicability for various types of wastes; choise of gas cleaning system. The off-gas system utilizes dry treatment. The operation is designed to function with a negative pressure. (Author) [pt

  7. Implantation of radiodiagnostic reference radiations at the CDTN/CNEN for dosemeter calibration

    International Nuclear Information System (INIS)

    Baptista Neto, A.T.; Oliveira, P.M.C. de; Ferreira, F.C.B.

    2009-01-01

    A reliable dosimetry in diagnostic radiology is based on the traceability of calibrated and type-tested dosimeters in reference radiations that were established by the International Electrotechnical Commission (IEC). Metrology laboratories are expected to implement the reference radiations by reproducing the x-ray beam parameters within standard limits. This work shows the results of the implementation in the CDTN/CNEN-MG of the reference radiations for diagnostic radiology. The half value-layers and the homogeneity coefficients were determined for the primary (RQR), attenuated (RQA) and computerized tomography (RQT) x-ray beams. Results complied with the IEC limits which it means that the CDTN and the IEC reference radiations are similar and they can be used for calibration and type-testing of dosimeters to be used in diagnostic radiology. (author)

  8. Radiological impact from the transport of radiopharmaceuticals of the IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Rodrigues, Demerval Leonidas

    2009-01-01

    When a package is shipped, people who work, live or travel in the route used for transportation of radioactive materials are irradiated, as well as those who are inside vehicles that travel in the same or opposite directions. Therefore, the proposed work has as main objective to estimate the radiological impact of the transportation of radiopharmaceuticals of IPEN/CNEN-SP to some predefined destinations. The doses in individuals who are in the public streets and in vehicles that travel close to the means of transportation, along the route traveled by packages, during the transport of radiopharmaceuticals were estimated. The doses were also estimated for drivers, from both the operation of driving the vehicle, and the loading and unloading of packages, because these tasks are performed by the drivers. (author)

  9. Investigation of radiological emergencies by the IPEN-CNEN/SP during the years 2001 to 2010

    International Nuclear Information System (INIS)

    Suzuki, Fabio Fumio; Mitake, Malvina Boni

    2011-01-01

    The Brazilian National Nuclear Energy Commission maintain, in each of its unities, a technical team for investigation and initial response to radiological and nuclear emergency situations which can occur outside of its installations. At the Sao Paulo state, Brazil, that task is accomplished by the Radioprotection Management (GRP) of the Instituto de Pesquisas Energeticas e Nucleares, IPEN-CNEN/SP, Brazil. This paper shows the results obtained by the GRP, analysing which entities action the system, the nature of the event, the involved type of radiation source and the geographical distribution of occurrences in the state. During the period between 2001 and 2010, the GRP attended to 98 notifications, and the entity which the most action the system was the Fire Department. The radionuclide of most incidence was the Am-241, mainly because of radioactive lightning-arrester, followed of radionuclides used in nuclear medicine such as Mo-99/Tc-99m and I-131

  10. External beam monitoring of the Cyclone 30 cyclotron of IPEN-CNEN-SP

    International Nuclear Information System (INIS)

    Matsuda, Hylton

    2002-01-01

    Due to the increasing demand for cyclotron radioisotopes and the high cost of equipment and materials involved in the process, it becomes evident the importance of external beam monitoring of the cyclotron. In this way, the beam of the Cyclone 30 cyclotron of IPEN-CNEN/S P was characterized throughout the evaluation of its current intensity, profile (position, focus and geometry), alignment and homogeneity, by measuring currents, temperatures and pressures of irradiation systems. For this purpose, techniques and conventional devices, thermocouples and pressure sensors associated to electronic of instrumentation, and technology and flexibility of micro controllers allowed observing the beam behavior during irradiations in real time. The ion beam energy was also evaluated using activation analysis technique of monitor reactions in nat Cu. The beam monitoring systems have been contributing to prevent material damages and they have already been used in routine irradiations, bringing important advantages in the process of beam optimization of the Cyclone 30. (author)

  11. Activities of the neutron activation analysis laboratory of the radiochemistry division of IPEN - CNEN/SP

    International Nuclear Information System (INIS)

    Vasconcellos, M.B.A.

    1988-10-01

    Neutron activation analysis (NAA) is one of the relevant applications of nuclear research reactors. Due to the high neutron fluxes available in these reactors, an excellent sensitivity of analysis is attained for many elements. NAA is one of the most sensitive, precise and accurate analytical methods for trace element determination. NAA has been one of the main activities of the Radiochemistry Division of IPEN, since the beginning of the operation of the nuclear reactor IEA-R1. Most of the effort was devoted to research work, aimed to improvements in the method as well as to its applications to several kinds of matrixes (geological, biological, metallic, environmental, forensic). Besides, analytical services were also offered, to the CNEN, to industries, universities, mining companies and research institutes. In the present paper, a review is made of the research work being developed presently at the Radiochesmitry Division of IPEN. A discussion is also made of the planned expansion of the analytical services offered [pt

  12. Female Contributions in Nuclear Science: Experiences at the Brazilian Commission for Nuclear Energy (CNEN/LAPOC)

    International Nuclear Information System (INIS)

    Carrijo da Silva Dias, D.; Leandro Bonifácio, R.; Augusto da Silva Alfenas, R.

    2015-01-01

    Female professional contributions in nuclear science and technology are no longer a novelty. Names such as Marie Curie, Chen Shiung Wu and Rosalyn Yalow are evidence of the incessant, worldwide efforts of women to take part in fields largely reserved for men. Although society has witnessed high level female achievements as early as in the 1800s, female scientists and technicians still face a long journey ahead in empowering themselves into full and equal participation in these areas. Today, the Laboratory of Poços de Caldas of the Brazilian Commission for Nuclear Energy (CNEN/LAPOC) experiences a process of women empowerment at all levels of the institution. At the Technical Section, two of the seven research departments are headed by female researchers who play essential roles in the institution’s quest for excellence. Today, their work include coordination of a major environmental research project involving most researchers at LAPOC, successful participations on international intercomparisons of radiometric analysis and development of new methodologies in nuclear field applications. At the administrative level, female collaborators lead the Administration Section, improving several aspects of internal management, promoting further interaction at the workplace and strengthening cooperation among all departments. Regarding the capacitation level, the Commission has a long tradition of welcoming students and junior researchers through institutional programmes of training and collaboration in several projects. Today CNEN/LAPOC works with twenty scholarship grantees — half of which are women. Not only the Laboratory has reached equality in participation, but unarguably the female participants have demonstrated the most remarkable achievements among the group, attested by their continuous academic pursuit through Master’s and Doctoral degrees, full collaboration in scientific publishing and attendance in training programmes at international level. The purpose

  13. Improvement at the system to collect radioactive waste at IPEN-CNEN/SP-TPI Radioisotopes Division; Melhorias no sistema de coleta de rejeitos radioativos da Divisao de Producao de Radioisotopos do IPEN-CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    Nieto, Wagner; Sanches, Matias Puga [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-12-31

    This paper describes a new system used at IPEN-CNEN/SP-TPI Radioisotopes Division to collect radioactive waste. This collect system is a result from the conception and the implementation of technicians from the TPI and Mechanical Workshop Division at IPEN-CNEN/SP. A comparison between the old disposal system and the new one is presented by showing the projects characteristics and the main difficulties found in the design and implementation of the last collect system. An analysis is presented of the improvements of the new disposal collect system under several aspects, among them, under the radioprotection point of view. Furthermore, the use of this new system for the handling of radioactive waste at the TPI-Radioisotopes Division is commented. (author) 3 refs., 9 figs.; e-mail: msanches at net.ipen.br

  14. Implementation of the automated potentiometric titration method for total U at the CNEN Safeguard Laboratory, Brazil; Implementacao do metodo de titulacao potenciometrica automatizado para U total no Laboratorio de Salvaguardas da CNEN, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Cristiano, Barbara F.G.; Delgado, Jose U.; Araujo, Radier M.S. de; Silva, Jose W.S. da; Barros, Pedro D. de, E-mail: barbara@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2009-07-01

    Brazilian nuclear facilities, in accordance with the regulation CNEN-NN-2.02, must have available measurement systems which allow to determine their nuclear material inventories. For the evaluation and the follow up the performance of the involved laboratories in those measurement systems, the accomplishment of interlaboratory comparison programmes becomes fundamental. Therefore, the implementation of the potentiometric titration viewing the characterization of uranium samples, represents an reference element for the Brazilian programs

  15. Development of indigenous technology at CNEN in the fields of nuclear medicine, nuclear detectors, instrumentation, radioisotope production and application of nuclear techniques

    International Nuclear Information System (INIS)

    Mafra, O.

    1990-01-01

    The main objectives of the program developed at CNEN in the field of nuclear medicine, nuclear detectors, instrumentation, radioisotope production and application of nuclear technique are described. (E.G.) [pt

  16. Nuclear Information Center: 25 years of CNEN in the support of science and technology; Centro de Informacoes Nucleares: 25 anos de apoio da CNEN a area de ciencia e tecnologia

    Energy Technology Data Exchange (ETDEWEB)

    Sayao, Luiz Fernando; Monteiro de Barros, Anna Christina T. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Centro de Informacoes Nucleares

    1995-05-01

    The 25 years of the Nuclear Information Centre of the Brazilian Nuclear Energy Commission - CIN/CNEN, and the role played in the context of Brazilian scientific and technological development is analyzed under two points of view: as database producer and information services provider as well as generator of knowledge and technology in the field of Information Science. The pioneer role of the Centre, not only in developing software for bibliographic information handling and in building a marketing model to information services but also contributing for the growth of database usage culture in Brazil is described. Cooperation, decentralization and sharing of resources are emphasized as the main characteristics of the work developed by the CIN/CNEN staff. Finally, the international background of CIN/CNEN coordinating Latin-American Projects as well as an active member of INIS - International Nuclear Information System, IAEA and more recently as the Brazilian representative to ETDE - Energy Technology Data Exchange is shown. IEA energy database is also discussed. (author) 1 tab., 4 figs.

  17. Utilization of plastic detector for pool water radioactivity control of IEA-R1 reactor. Examination of fuel element irradiation behaviour fabricated at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Berretta, J.R.; Mesquita, C.H. de; Madi Filho, T.

    1989-01-01

    For the examination of fuel element irradiation behavior that were fabricated at IPEN/CNEN/SP Metalurgical Departament, it was provided a detection system for pool water radioactivity measurements. This system uses a plastic scintillator detector produced at IPEN/CNEN-SP Health Physics Department, with dimensions and shape apropriated for such work. The detection system shows a sensibility of 4.125x10 -2 dps/cm 3 and 20% of efficiency for 131 I radiations. (author) [pt

  18. I.R.D. annual report - 1988. Institute of Radioprotection and Dosimetry of Brazilian Nuclear Energy Commission (CNEN)

    International Nuclear Information System (INIS)

    1989-01-01

    This is the annual report of the activities developed by the Institute of Radioprotection and Dosimetry -IRD/CNEN-Brazil, in the year of 1988. It is composed by the individual reports of its several divisions, describing the main activities and personnel: DEPRO - Occupational and Radiological Protection Dept.; DEPRA - Environmental and Radiological Protection Dept.; DEMET - Metrology Dept.; DEPAT - Technical Support Dept.; DETAC - Scientific Support and Training Dept.; DEPAD -Administrative Support Dept. (J.A.M.M.)

  19. Database created with the operation of environmental monitoring program from the Nuclear Technology Development Center (CDTN) - Brazilian CNEN

    International Nuclear Information System (INIS)

    Peixoto, C.M.

    1995-01-01

    The environmental control from the Nuclear Technology Development Center (CDTN - Brazilian CNEN) is done through a Program of Environmental Monitoring-PMA, which has been in operation since 1985. To register all the analytic results of the several samples, samples, a database was created. In this work, this database structure as well as the information used in the evaluation of the results obtained from the operation of the above-mentioned PMA are presented. (author). 5 refs, 1 fig, 3 tabs

  20. Proceedings of the 2. SIPEN: Integration week from IPEN - Brazilian Institute for Energy and Nuclear Researches, CNEN/SP

    International Nuclear Information System (INIS)

    1994-01-01

    The technical-scientific activities of IPEN (Instituto de Pesquisas Energeticas e Nucleares), Brazilian CNEN, has been presented in these proceedings. It includes the following topics: management and logistics, infra-structure and support, application of nuclear techniques, fuel cycle, materials, reactor research, development of products and services, radiation protection and monitoring. Nuclear medicine and application of radiation in biological assays are studied. Environmental impacts and management of radioactive wastes are also presented

  1. Comparative study between RDC number 20 from ANVISA of 2006 and standard CNEN NN 6.10 of 2014 on radiotherapy services

    International Nuclear Information System (INIS)

    Silva, D.R.; Geraldo, J.M.; Batista, A.S.M.

    2017-01-01

    Introduction: The internal procedures of a Radiotherapy Service are performed based on resolutions and standards of the control bodies, both health and radiation use. In the health area, the control is carried out by the National Health Surveillance Agency (ANVISA), through the Resolution of the Collegiate Board of Directors (RDC) number 20 of 2006. On the other hand, because it is a service that uses high energy ionizing radiation, it must comply with the rules of the National Nuclear Energy Commission (CNEN) specifically CNEN NN 6.10 of 2014. It is therefore necessary to integrate the recommendations contained in the ANVISA and CNEN determinations, requiring interpretation and transposition effort for the internal regime of procedures of each institution. Methods: The objective of this study was to compare, discuss and interpret RDC number 20 and CNEN NN 6.10 in relation to the understanding of how the two contribute to the applicability of radioprotection and radiation therapy rules. Results: Tables are presented in constant or not in the two documents and evaluated the contributions and focus of each of them. Conclusion: It is noted that each text is reconciled with the interests of each legislator and supervisory body, that is, CNEN and ANVISA. In the control of the use of radioactive sources and emitting equipment, in the case of CNEN, and in the control of agents harmful to health, ANVISA

  2. IPR-RI TRIGA MARK I reactor and the neutron activation analysis at CDTN/CNEN

    International Nuclear Information System (INIS)

    Menezes, Maria Angela de B.C.; Kastner, Geraldo F.; Amaral, Angela M.; Souza, Wagner de; Maretti, Fausto Junior; Leal, Alexandre S.

    2008-01-01

    The IPR-R1 TRIGA Mark I research reactor started up in 1960. It is located at Centro de Desenvolvimento da Tecnologia Nuclear (Nuclear Technology Development Centre) / Comissao Nacional de Energia Nuclear (Brazilian Commission for Nuclear Energy), CDTN/CNEN. Join to the reactor, the Laboratory for Neutron Activation Analysis has been developing its activities since 1960. The activities of the Laboratory comprise the delayed fission neutron activation analysis, instrumental (comparative and parametric methods) and radiochemical / chemical methods. These methods are responsible for relevant percentage of CDTN's analysis demand, meeting the clients' analytical needs and researches developed by the Laboratory, by CDTN and by other institutions. Over the years the work has been linked to the goals of the country and the institutions. Nowadays several elements - Ag, Al, Au, As, Ba, Br, Ca, Cd, Ce, Cl, Co, Cr, Cs, Cu, Dy, Eu, Fe, Ga, Hf, Hg, Ho, K, La, Mg, Mn, Mo, Na, Nd, Rb, Sb, Sc, Se, Sm, Sr, Ta, Tb, Th, Ti, U, V, W, Yb, Zn and Zr - are determined in several matrices and range of concentrations. In Brazil, CDTN is the only Institute that fully masters the instrumental neutron activation analysis k0-method determining short, medium and long half-life radionuclides using its own nuclear reactor. The good performance of the reactor is pointed out in a table with experimental and certified values for Certified Reference Materials. (authors)

  3. Bromide as chemical tracer to measure the liquid effluent flow at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Silva, Douglas B.; Faustino, Mainara G.; Monteiro, Lucilena R.; Cotrim, Marycel E.B.; Pires, Maria Aparecida F.

    2013-01-01

    Due to recent changes in CONAMA Resolution 357, which occurred through the publication of Resolution 430, on May 13, 2011 that now set standards about the effluent release, IPEN-CNEN/SP initiated several actions to improve the Environmental Monitoring Program (PMA-Q) of stable chemical compounds. Besides various parameters (physical and chemical) established by CONAMA, the submission of an annual pollution inventory report became necessary. The liquid effluent flow measurement is required to implement this inventory. Thereby, this paper describes a study that uses bromide as a chemical tracer. This paper presents the results of 6 tracer releases in IPEN wastewater collection network between 2011 and 2012. Two tracer releases designs were performed: single pulse and continuous releases performed with 1 to 6 hours duration, done by using one single piston pump manufactured by DIONEX. After the release, one fraction of the effluent was collected every 15 minutes at IPEN effluent monitoring station. The tracer concentration in the effluent was analyzed by ion chromatography and flow was calculated considering the dilution in the system and pump flow set up for the release. The flow values were measured in 6 events were determined and evaluated as per Brazilian regulation requirements. Experimental designs to be implemented during 2013 monitoring were also discussed in this paper, contributing to legal compliance and to improve IPEN's Environmental Monitoring Program for stable chemical compounds (PMA-Q). (author)

  4. Design and development of a neutron tomography facility at the IPEN-CNEN/SP, Brazil

    International Nuclear Information System (INIS)

    Schoueri, Roberto Mauro

    2016-01-01

    In the work reported in this dissertation, a facility for neutron tomography was developed and installed at the irradiation channel 14 of the IEA-R1 nuclear research reactor of IPEN-CNEN/SP. Several selected objects were inspected, and the obtained images demonstrate the main characteristic of the present technique that is its capability to visualize hydrogenous rich substances. In such facility, a tomography can be obtained in 400 s with a spatial resolution of 205 μm, and the obtained images have sufficient quality to allow qualitative and quantitative analysis. These characteristics are very similar to the ones of the top facilities around the world, and the quality of the provided images are sufficient to allow qualitative and quantitative analysis of the inspected object. The implementation of the neutron tomography technique opens up the possibility of new research as it provides a new tool for inspection of objects, which provides a view of its internal structure, which is not always possible for two-dimensional imaging methods. (author)

  5. Modernization of the physical protection system of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Suzuki, F.F.

    2001-01-01

    Full text: The plans of physical protection of nuclear facilities must be reviewed and updated every two years. A general study of the physical protection system was carried out in order to review and to update the plan of physical protection of IPEN-CNEN/SP. Important alterations accomplished at the institute were considered in the study, as the installation of a cyclotron 30 MeV and the new operation conditions for the nuclear research reactor IEA-RI, that include the increase of its operation power from two to five megawatts and the establishment of the continuous operation by 72 hours weekly. The area of IPEN-CNEN/SP is 478,000 m 2 (101,850 m 2 built area of 107 constructions). The group responsible for the study investigated the performance of the physical protection system and detected some points that could be reinforced at inner and protected areas. The initial step was the evaluation, in loco, of the constructions and physical barriers of inner and protected areas. The performance of the security force personnel on the conventional procedures, as access control to the facilities, control of material flow, area monitoring and patrol, as well as its response for special situation procedures in the case of a physical protection emergency, were evaluated too. The study also focused the communication means used by the security force, as the extension phone lines that are located in each entrance area and in the huts, and the portable VHP radios that are used by the guards. In order to elaborate a programme of modernization of the physical protection system, using the results of the study as basis, an internal committee composed of specialists in physical protection, nuclear safety, operation of reactors and engineering areas was created. The programme elaborated by the committee strengthens the physical protection system by applying the defense in depth concept. At the same time, it attempts to propitiate a balanced protection to minimize the consequences for

  6. [11C] Methionine as PET radiopharmaceutical produced at CDTN/CNEN

    International Nuclear Information System (INIS)

    Silveira, Marina B.; Ferreira, Soraya Z.; Carvalho, Tiago F.; Silva, Juliana B. da

    2013-01-01

    Carbon-11 ( 11 C) is an attractive radionuclide used in positron emission tomography (PET) since carbon is a ubiquitous element in biomolecules. Positron emitter-labeled amino acids are being widely used as indicators of tumor activity due to enhanced expression of amino acid transporter systems in cancer cells. L-[Methyl-( 11 C)] Methionine or [ 11 C]Methionine is being used in neuro-oncology and, unlike 2-[ 18 F]fluoro-2-deoxy-D-glucose ( 18 FDG), gives more contrast images and improves brain tumor diagnosis. The aim of this work was to develop the synthesis and quality control of [ 11 C]Methionine at the Radiopharmaceuticals Research and Production Facility (UPPR) of CDTN/CNEN. The synthesis of [ 11 C] Methionine was performed using two Sep-Pak tC18 plus cartridges one as solid support for the 11 C-methylation of the precursor L-homocysteine thiolactone hydrochloride and another for purification. The pH, radionuclidic identity and purity, residual solvents, radiochemical and chemical purity of the final product were evaluated as described on the European Pharmacopoeia 7.0 monograph. Total synthesis time was 18 minutes, the radiochemical yield was approximately 15% (non-decay corrected) and radiochemical purity was greater than 95%. [ 11 C]Methionine was successfully synthesized at CDTN using the described procedures and complied with quality requirements. Due to the rapid growth of oncologic PET scans in last decade, 11 C labelling holds great promises in the next few years with the application of other tracers beyond 18 FDG. This pioneering work of UPPR/CDTN represents a response to the demands of a growing nuclear medicine in the country focused on achieving better diagnostic imaging. (author)

  7. Hot Chemistry Laboratory decommissioning activities at IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Camilo, Ruth L.; Lainetti, Paulo E.O.

    2009-01-01

    IPEN's fuel cycle activities were accomplished in laboratory and pilot plant scale and most facilities were built in the 70-80 years. Nevertheless, radical changes of the Brazilian nuclear policy in the beginning of 90's determined the interruption of several fuel cycle activities and facilities shutdown. Since then, IPEN has faced the problem of the pilot plants decommissioning considering that there was no experience/expertise in this field at all. In spite of this, some laboratory and pilot plant decommissioning activities have been performed in IPEN in the last years, even without previous experience and training support. One of the first decommissioning activities accomplished in IPEN involved the Hot Chemistry Laboratory. This facility was built in the beginning of the 80's with the proposal of supporting research and development in the nuclear chemistry area. It was decided to settle a new laboratory in the place where the Hot Chemistry Laboratory was installed, being necessary its total releasing from the radioactive contamination point of view. The previous work in the laboratory involved the manipulation of samples of irradiated nuclear fuel, besides plutonium-239 and uranium-233 standard solutions. There were 5 glove-boxes in the facility but only 3 were used with radioactive material. The glove-boxes contained several devices and materials, besides the radioactive compounds, such as: electric and electronic equipment, metallic and plastic pieces, chemical reagents, liquid and solid radioactive wastes, etc. The laboratory's decommissioning process was divided in 12 steps. This paper describes the procedures, problems faced and results related to the Hot Chemistry Laboratory decommissioning operations and its reintegration as a new laboratory of the Chemical and Environmental Technology Center (CQMA) - IPEN-CNEN/SP. (author)

  8. [11C] Methionine as PET radiopharmaceutical produced at CDTN/CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Silveira, Marina B.; Ferreira, Soraya Z.; Carvalho, Tiago F.; Silva, Juliana B. da, E-mail: mbs@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Unidade de Pesquisa e Producao de Radiofarmacos

    2013-07-01

    Carbon-11 ({sup 11}C) is an attractive radionuclide used in positron emission tomography (PET) since carbon is a ubiquitous element in biomolecules. Positron emitter-labeled amino acids are being widely used as indicators of tumor activity due to enhanced expression of amino acid transporter systems in cancer cells. L-[Methyl-({sup 11}C)] Methionine or [{sup 11}C]Methionine is being used in neuro-oncology and, unlike 2-[{sup 18}F]fluoro-2-deoxy-D-glucose ({sup 18}FDG), gives more contrast images and improves brain tumor diagnosis. The aim of this work was to develop the synthesis and quality control of [{sup 11}C]Methionine at the Radiopharmaceuticals Research and Production Facility (UPPR) of CDTN/CNEN. The synthesis of [{sup 11}C] Methionine was performed using two Sep-Pak tC18 plus cartridges one as solid support for the {sup 11}C-methylation of the precursor L-homocysteine thiolactone hydrochloride and another for purification. The pH, radionuclidic identity and purity, residual solvents, radiochemical and chemical purity of the final product were evaluated as described on the European Pharmacopoeia 7.0 monograph. Total synthesis time was 18 minutes, the radiochemical yield was approximately 15% (non-decay corrected) and radiochemical purity was greater than 95%. [{sup 11}C]Methionine was successfully synthesized at CDTN using the described procedures and complied with quality requirements. Due to the rapid growth of oncologic PET scans in last decade, {sup 11}C labelling holds great promises in the next few years with the application of other tracers beyond {sup 18}FDG. This pioneering work of UPPR/CDTN represents a response to the demands of a growing nuclear medicine in the country focused on achieving better diagnostic imaging. (author)

  9. Whole-body measurements of workers occupationally exposed to radionuclides at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Cardoso, Joaquim Carlos S.; Xavier, Marcos

    2015-01-01

    The intake of radioactive material by workers can occur in the radiopharmaceuticals production, during the handling of these in the medical fields (nuclear medicine) and in biological and research laboratories. The workers who work in areas where exposures are significant are routinely monitored to demonstrate that the workers are receiving adequate protection from internal contamination. Direct measurements of whole-body and thyroid contents provide an estimate of the activity of these radionuclides in the potentially exposed workers. The whole-body measurements of the workers, trainees and visitors are routinely performed by the In Vivo Monitoring Laboratory (LMIV) of the Energy and Nuclear Research Institute (IPEN/CNEN-SP). The frequency of measurements is defined by the Radioprotection Service (SRP) and the Dose Calculation Group of IPEN. For this purpose LMIV has two counters, whole body. NaITl (8 x 4”), and thyroid one, NaITl (3 x 3”). The system was calibrated in energy and efficiency, with calibration sources of Eu-152, Am-241 and Co-60 with gamma emissions between 59.54 and 1408.08 keV, positioned within Alderson Research Labs. anthropomorphic phantom. The background measures were obtained of worker's spectrum that was not exposed occupationally yet. The concepts adopted in the HPS N13.30 Standard and proposed in ISO documents for standardization were used for activity measurements. During the period January 2010 to December 2014, approximately 4500 measurements had been carried in workers who develop tasks related to the production and research. The activities of the radionuclides and the workers' tasks relationship had been evaluated. (author)

  10. Whole-body measurements of workers occupationally exposed to radionuclides at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Cardoso, Joaquim Carlos S.; Xavier, Marcos

    2013-01-01

    The intake of radioactive material by workers can occur in the radiopharmaceuticals production, during the handling of these in the medical fields (nuclear medicine) and in biological and research laboratories. The workers who work in areas where exposures are significant are routinely monitored to demonstrate that the workers are receiving adequate protection from internal contamination. Direct measurements of whole-body and thyroid contents provide an estimate of the activity of these radionuclides in the potentially exposed workers. The whole-body measurements of the workers, trainees and visitors are routinely performed by the In Vivo Monitoring Laboratory (LMIV) of the Energy and Nuclear Research Institute (IPEN/CNEN-SP). The frequency of measurements is defined by the Radioprotection Service (SRP) and the Dose Calculation Group of IPEN. For this purpose LMIV has two counters, whole body. NaIT1 (8x4″), and thyroid one, NaIT1 (3x3″). The system was calibrated in energy and efficiency, with calibration sources of Eu-152, Am-241 and Co-60 with gamma emissions between 59.54 and 1408.08 keV, positioned within Alderson Research Labs. anthropomorphic phantom. The background measures were obtained of worker's spectrum that wasn't exposed occupationally yet. The concepts adopted in the HPS N13.30 Standard and proposed in ISO documents for standardization were used for activity measurements. During the period January 2007 to December 2012, approximately 6700 measurements had been carried in workers who develop tasks related to the production and research. The activities of the radionuclides and the workers' tasks relationship had been evaluated. (author)

  11. Conditions of the potential for commercialization of the patent: the implementation of a technology public offering system technology at CNEN; Condicionantes do potencial de exploracao comercial da patente: a implantacao de um sistema de oferta publica de tecnologia na CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Archila, Daniela Lima Cerqueira

    2015-07-01

    This dissertation identifies the main factors which represent the conditions for the potential commercialization of patents aiming at the implementation of a system for technology public offering at CNEN as a strategy for creating licensing opportunities to the industrial sector. The method applied refers to an exploratory case study of a patented technology selected from a sample of CNEN's patent portfolio in the biopharmaceutical sector. The case study comprehends a field research of interviews conducted with two specialists in technology and innovation management, one researcher from CNEN and a biopharmaceutical company. The results show that among the nineteen main factors - related to technology, market, business and Science and Technology Organization (STO) - the market dynamics, the potential applications of the technology and an abstract of its main benefits compared to existing technologies are the major relevant information for each technology to be included in the public offering system. Other results indicate that the evaluation of such factors may be conducted by competent professionals to bring less uncertainty and risk to the early-stage of the innovation process, as well as enhance the potential interest of a company in the technology. On the other hand, the latter requires innovation capabilities to move the technology forward – additional R&D, scale-up, manufacturing and marketing - whilst the STO needs a entrepreneurial culture that mitigates its obstacles, creates more positive solutions for its routines and processes and gives sustainability to its Technology Transfer Office (TTO) through valuing its personnel in the long term. Finally, emphasis on technological partnerships with companies can be a motivating feature for directing the STO's patent strategy to the creation of proprietary technological platforms that reflect problems experienced by the commercial environment, as well as the development of this strategic patent

  12. Proposal for intake model for workers at IPEN-CNEN/SP who handle {sup 131} I; Proposta de um modelo de incorporacao para trabalhadores ocupacionais do IPEN-CNEN/SP que manuseiam {sup 131} I

    Energy Technology Data Exchange (ETDEWEB)

    Todo, A.S.; Potiens Junior, A.J.; Gaburo, J.C.; Sanches, M.P.; Oliveira, E.M. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-12-31

    The intake model for the two groups of workers at IPEN-CNEN/SP is presented. They handle iodine compounds during the processing of irradiated targets and at labeling of radiopharmaceutical compounds. The intake model for the workers are proposed from the knowledge of the activities carried out in the plant and the internal monitoring program of the workers. In this study, the intake is considered to be taken uniformly during the days of major activities carried out by the workers. In practice, the application of this model has be shown suitable, for the studied groups 5 refs., 2 figs., 1 tab.; e-mail: astodo at net.ipen.br

  13. Conditions of the potential for commercialization of the patent: the implementation of a technology public offering system technology at CNEN

    International Nuclear Information System (INIS)

    Archila, Daniela Lima Cerqueira

    2015-01-01

    This dissertation identifies the main factors which represent the conditions for the potential commercialization of patents aiming at the implementation of a system for technology public offering at CNEN as a strategy for creating licensing opportunities to the industrial sector. The method applied refers to an exploratory case study of a patented technology selected from a sample of CNEN's patent portfolio in the biopharmaceutical sector. The case study comprehends a field research of interviews conducted with two specialists in technology and innovation management, one researcher from CNEN and a biopharmaceutical company. The results show that among the nineteen main factors - related to technology, market, business and Science and Technology Organization (STO) - the market dynamics, the potential applications of the technology and an abstract of its main benefits compared to existing technologies are the major relevant information for each technology to be included in the public offering system. Other results indicate that the evaluation of such factors may be conducted by competent professionals to bring less uncertainty and risk to the early-stage of the innovation process, as well as enhance the potential interest of a company in the technology. On the other hand, the latter requires innovation capabilities to move the technology forward – additional R&D, scale-up, manufacturing and marketing - whilst the STO needs a entrepreneurial culture that mitigates its obstacles, creates more positive solutions for its routines and processes and gives sustainability to its Technology Transfer Office (TTO) through valuing its personnel in the long term. Finally, emphasis on technological partnerships with companies can be a motivating feature for directing the STO's patent strategy to the creation of proprietary technological platforms that reflect problems experienced by the commercial environment, as well as the development of this strategic patent

  14. Application of neutron actication analysis to the determination of impurities in rare earth oxides produced at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Saiki, M.; Oliveira Lellis, L. de.

    1988-07-01

    This paper describes a method for trace analysis in high purity rare earth oxides. This method is an application of instrumental neutron activation analysis. The results of analysis obtained in La 2 O 3 , CeO 2 , Pr 6 O 11 Nd 2 O 3 , Sm 2 O 3 and Gd 2 O 3 produced at IPEN-CNEN/SP are presented. A detailed study of the possible interference found in the neutron activation of these materials is also made. The sensitivity of the method is determined for impurities not detected in each sample. (author) [pt

  15. Comparative study between RDC number 20 from ANVISA of 2006 and standard CNEN NN 6.10 of 2014 on radiotherapy services; Estudo comparativo entre a RDC nº20 da ANVISA de 2006 e a norma CNEN NN 6.10 de 2014 para serviços de radioterapia

    Energy Technology Data Exchange (ETDEWEB)

    Silva, D.R.; Geraldo, J.M.; Batista, A.S.M., E-mail: adrinanuclear@yahoo.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Anatomia e Imagem

    2017-07-01

    Introduction: The internal procedures of a Radiotherapy Service are performed based on resolutions and standards of the control bodies, both health and radiation use. In the health area, the control is carried out by the National Health Surveillance Agency (ANVISA), through the Resolution of the Collegiate Board of Directors (RDC) number 20 of 2006. On the other hand, because it is a service that uses high energy ionizing radiation, it must comply with the rules of the National Nuclear Energy Commission (CNEN) specifically CNEN NN 6.10 of 2014. It is therefore necessary to integrate the recommendations contained in the ANVISA and CNEN determinations, requiring interpretation and transposition effort for the internal regime of procedures of each institution. Methods: The objective of this study was to compare, discuss and interpret RDC number 20 and CNEN NN 6.10 in relation to the understanding of how the two contribute to the applicability of radioprotection and radiation therapy rules. Results: Tables are presented in constant or not in the two documents and evaluated the contributions and focus of each of them. Conclusion: It is noted that each text is reconciled with the interests of each legislator and supervisory body, that is, CNEN and ANVISA. In the control of the use of radioactive sources and emitting equipment, in the case of CNEN, and in the control of agents harmful to health, ANVISA.

  16. Dosimetric studies of anti-CD20 labeled with therapeutic radionuclides at IPEN/CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Barrio, G.; Dias, C.R.B.R.; Osso Junior, J.A., E-mail: gracielabarrio@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2012-07-01

    Radioimmunotherapy (RIT) makes use of monoclonal antibodies (MAb) labeled with alpha/beta radionuclides for therapeutical purposes, leading to tumor irradiation and destruction, preserving the normal organs on the radiation excess. The therapeutic activity to be injected in a specific patient is based on information obtained in dosimetric studies. Beta emitting radionuclides such as {sup 131}I, {sup 188}Re, {sup 90}Y, {sup 177}Lu and {sup 166}Ho are useful for the development of therapeutic radiopharmaceuticals. Anti-CD20 (Rituximab) is a chimeric MAb directed against antigen surface CD20 on B-lymphocytes, used in non-Hodgkin lymphoma treatment (NHL). The association with beta radionuclides have shown greater therapeutic efficacy. Currently, two radiopharmaceuticals with Anti-CD20 for radioimmunotherapy have FDA approval for NHL treatment: {sup 131}I-AntiCD20 (Bexar) and {sup 90}Y-AntiCD20 (Zevalin). Techniques for the radiolabeling of {sup 188}Re-antiCD20 have been recently developed by IPEN-CNEN/SP in order to evaluate the clinical use of this radionuclide in particular. The use of {sup 188}Re (T{sub 1/2} 17h) produced by the decay of {sup 188}W (T{sub 1/2} 69d), from an {sup 188}W/{sup 188}Re generator system, has represented an alternative to RIT. Beyond high energy beta emission for therapy, {sup 188}Re also emits gamma rays (155keV) suitable for image. The aim of this new project is to compare the labeling of anti-CD20 with {sup 188}Re with the same MAb labeled with {sup 131}I, {sup 177}Lu, {sup 90}Y and even {sup 99m}Tc. The first step in this project is the review of the published data available concerning the labeling of this MAb with different radionuclides, along with data obtained at IPEN, taking into account labeling procedures, labeling yields, reaction time, level and kind of impurities and biodistribution studies. The pharmacokinetic code will be developed in Visual Studio.NET platform through VB.NET and C{sup ++} for biodistribution and dosimetric

  17. Replacing nuclear staff: The proactive work at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Pupak, M.O.; Rogero, J.R.

    2004-01-01

    In Brazil, young people do not learn nuclear science, nuclear engineering and related fields at College or Universities, because Brazilian Universities offer such specialized courses only as extension classes to normal curriculum. Another important aspect to be considered is that there are eight Brazilian Universities or Research Institute that offers MSc and PhD degree offered on only four State/Region of Brazil, e.g.: in the State of Sao Paulo/SP, Region Southeast of Brazil, there is only one programme, at Energy and Nuclear Research Institute - IPEN, in association with the University of Sao Paulo - USP; in the State of Rio de Janeiro/RJ, Region Southeast of Brazil, there are four programmes: the Federal University of Rio de Janeiro - UFRJ, the Army Engineering Institute - IME, the Institute of Nuclear Engineering - IEN, the Institute of Radiation Protection and Dosimetry - IRD; in the State of Minas Gerais, Region Southeast of Brazil, there are the Center of Nuclear Technology Development - CDTN and the Federal University of Minas Gerais - UFMG; in the State of Pernambuco, Region Northeast of Brazil, there is Federal University of Pernambuco - UFPE. Those four institutes: IPEN, IEN, IRD and CDTN are institutes belonging to the National Nuclear Energy Commission - CNEN. The situation of those nuclear programmes (mentioned above), their level of post graduation and the grade attributed by Capes - the Higher Education Coordinating Office of the Federal Ministry of Education, done three-annually on all Brazilian Courses, undergraduate and postgraduate is presented. This evaluation varies on a scale from 1 to 5, universities are allowed to conduct their programme only with grade up to 3, if not the course is disregarded. The acquirement of evaluation up to 5, i.e. 6 and 7 is given only to programme that has high academic level recognized internationally for expertise. IPEN it is a traditional research and educational institution, recognized internationally for the

  18. Storage pool water condition of multipurpose compact 60Co irradiator of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Kodama, Yasko; Rela, Paulo R.

    2008-01-01

    A new type compact gamma irradiator was developed and installed at IPEN-CNEN/SP, it is classified as category IV irradiator according to International Atomic Energy Agency-IAEA. The originality of its design remains on the rotating concrete door, which integrates the shielding system with the product handling system, permitting the input and output of the products in a continuous way, without the necessity to lower the sources and open the irradiator chamber to change the batch. The licensed capacity of this irradiator is 37 P Bq (1 MCi) and the water pool liner, manufactured in stainless steel, has 7.0 m deep and 2.7 m diameter. A sealed radiation source may be defined as a quantity of radioactive material sealed within non-radioactive material, which the confining barrier is intended to prevent leakage or escape of the radioactive material under normal handling conditions and also under foreseeable mishaps. The use of cobalt-60 radiation sources in a wet storage environment requires care in the control of that environment to avoid the potential for deterioration of the stainless steel. In the literature, the tests performed demonstrated that stainless steel had excellent performance under controlled environment conditions. The inspection includes assessing the condition of storage pool water and measuring the pool water conductivity. The demineralized water normally used in storage pools is usually an effective and secure medium in which to store stainless steel. However, there are certain constituents and contaminants in the water which can affect this behaviour. For instance, the pH has a small but definite effect on the tendency for pitting corrosion. Nevertheless, there is also evidence that both strongly alkaline and strongly acid environments can encourage pitting corrosion. In general, an around neutral pH is recommended. The conductivity is used as a measure of the extent to which ionic species are present in the pool water. International recommendations

  19. Thermal hydraulic evaluation for an experimental facility to investigate pressurized thermal shock (PTS) in CDTN/CNEN; Avaliacao termo-hidraulica da montagem experimental de choque termico pressurizado do CDTN/CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Palmieri, Elcio T.; Navarro, Moyses A.; Aronne, Ivam D.; Terra, Jose L. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)

    2002-07-01

    The goal of the work presented in this paper is to provide necessary thermal hydraulics information to the design of an experimental installation to investigate the Pressurized Thermal Shock (PTS) to be implemented at Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN). The envisaged installation has a test section that represents, in a small scale, a pressure vessel of a nuclear reactor. This test section will be heated and then exposed to a PTS in order to evaluate the appearance and development of cracks. To verify the behavior of the temperatures of the pressure vessel after a sudden flood through the annulus, calculations were made using the RELAP5/MOD 3.2.2 gamma code. Different outer radiuses were studied for the annular region. The results showed that the smaller annulus spacing (20 mm) anticipates the wetting of the surface and produces a higher cooling of the external surface, which stays completely wet for a longer time. (author)

  20. Investigation of radiological emergencies by the IPEN-CNEN/SP during the years 2001 to 2010; Averiguacoes de emergencias radiologicas pelo IPEN-CNEN/SP nos anos de 2001 a 2010

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Fabio Fumio; Mitake, Malvina Boni, E-mail: ffsuzuki@ipen.b, E-mail: mbmitake@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-10-26

    The Brazilian National Nuclear Energy Commission maintain, in each of its unities, a technical team for investigation and initial response to radiological and nuclear emergency situations which can occur outside of its installations. At the Sao Paulo state, Brazil, that task is accomplished by the Radioprotection Management (GRP) of the Instituto de Pesquisas Energeticas e Nucleares, IPEN-CNEN/SP, Brazil. This paper shows the results obtained by the GRP, analysing which entities action the system, the nature of the event, the involved type of radiation source and the geographical distribution of occurrences in the state. During the period between 2001 and 2010, the GRP attended to 98 notifications, and the entity which the most action the system was the Fire Department. The radionuclide of most incidence was the Am-241, mainly because of radioactive lightning-arrester, followed of radionuclides used in nuclear medicine such as Mo-99/Tc-99m and I-131

  1. Monitoring of the radioactive liquid effluents discharged from IPEN-CNEN/SP. Optimization of the procedures adopted

    International Nuclear Information System (INIS)

    Seki, C.R.

    1990-01-01

    The main purpose of a radioactive liquid effluents monitoring of a nuclear installation is to determine the amount of radioactivity discharged to the environment, as well as, to verify if this activity is below the authorized discharge limits established by the competent authority. Although this control has been established on a routine basis since the beginning of operation of the nuclear installations available at IPEN, the growing of such facilities in the last years has implied in an increase in the number of samples to be analyzed. The aim of this work is, therefore, to optimize the procedures adopted in the Environmental Monitoring Division of IPEN-CNEN/SP for the activity measurement of the liquid effluents discharged to the environment. Since these effluents are discharged to Pinheiros river, which presents a high dilution factor, a study is also carried out in order to verify if the activity present can be measured by the equipment available. (author)

  2. A dosimetric survey of the DC1500/25/04 electron beam plant installed at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Kuntz, Florent; Somessari, Elizabeth S.R.; Silveira, Carlos G.da; Bueno, Carmen C.; Calvo, Wilson A.P.; Napolitano, Celia M.; Goncalves, Josemary A.C.; Somessari, Samir L.

    2015-01-01

    In this work we describe a dosimetric survey of the DC1500/25/04 electron beam accelerator installed in the Intense Sources of Radiation Laboratory at IPEN/CNEN-SP. As this accelerator has been used for innumerable applications in radiation processing, product surface and internal doses must be targeted and controlled via operational qualification such as beam energy, beam current, scan width and conveyor speed. The qualification of the accelerator was carried out in order to observe the current performances of the irradiation plant using Alanine (ESR) and CTA (UV Spectrophotometry) dosimeters. Energy (Electron penetration in material) calculations, scanning width/length, homogeneity and irradiation uniformity were evaluated according to ISO/ASTM 51649 and ISO11137-3, as well as process uncertainty establishment. (author)

  3. Thermal hydraulic evaluation for an experimental facility to investigate pressurized thermal shock (PTS) in CDTN/CNEN

    International Nuclear Information System (INIS)

    Palmieri, Elcio T.; Navarro, Moyses A.; Aronne, Ivam D.; Terra, Jose L.

    2002-01-01

    The goal of the work presented in this paper is to provide necessary thermal hydraulics information to the design of an experimental installation to investigate the Pressurized Thermal Shock (PTS) to be implemented at Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN). The envisaged installation has a test section that represents, in a small scale, a pressure vessel of a nuclear reactor. This test section will be heated and then exposed to a PTS in order to evaluate the appearance and development of cracks. To verify the behavior of the temperatures of the pressure vessel after a sudden flood through the annulus, calculations were made using the RELAP5/MOD 3.2.2 gamma code. Different outer radiuses were studied for the annular region. The results showed that the smaller annulus spacing (20 mm) anticipates the wetting of the surface and produces a higher cooling of the external surface, which stays completely wet for a longer time. (author)

  4. Implementation of the Service for Radiological Emergency Response of CRCN-NE/CNEN-PE, Recife, PE, Brazil

    International Nuclear Information System (INIS)

    Menezes, Claudio J.M.

    2005-01-01

    In 1998, it was created in the Centro Regional de Ciencias Nucleares (CRCN-NE) - the Brazilian regional center of nuclear sciences -, Recife, PE, Brazil, the Service for Radiological Emergency Response with the objective of providing the population of Pernambuco and neighboring States a team of professionals specialized in emergency situations and radiological protection. This action has the purpose of decentralization of actions of the Brazilian National Nuclear Energy Commission (CNEN), an agency responsible for licensing and safety of radioactive sources in Brazil. With this study we can conclude that the settlement of SAER/CRCN came to meet initial expectations, having in the last years provided assistance in situations with suspected radioactive material and participated actively: with radioactive load simulation; of the Exercicio de Emergencia Aeronautica Completo (EXEAC) - an emergency simulated training in airports- from the Guararapes-Gilberto Freire Airport; trained, every two years, the services of emergency for accidents and participated in events of the area

  5. Activities of the Laboratory of Neutron Activation Analysis in the Radiochemistry Division - IPEN/CNEN/SP/Brazil

    International Nuclear Information System (INIS)

    Vasconcellos, M.B.A.

    1988-01-01

    Neutron activation analysis (NAA) is one of the relevant applications of nuclear research reactors. Due to the high neutron fluxes available in these reactors, an excellent sensitivity of analysis is attained for many elements. NAA is one of the most sensitive, precise and accurate analytical methods for trace element determination. NAA has been one of the main activities of the Radiochemistry Division of IPEN, since the befinning of the operation of the nuclear reactor IEA-R1. Most of the effort was devoted to research work, aimed to improvements in the method as well as to its applications to several kinds of matrixes (geological, biological, metallic, environmental, forensic). Besides, analytical services were also offered, to the CNEN, to industries, universities, mining companies and research institutes. In the present paper, a review is made of the research work being developed presently at the Radiochemistry Division of IPEN. A discussion is also made of the planned expansion of the analytical services offered. (author) [pt

  6. Evaluation of the radiological impact in the aquatic system in the surrounding of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Jacomino, V.M.F.; Gordon, A.M.P.L.; Venturini, L.

    1989-12-01

    In order to control the discharges of radioactive material in the aquatic system (Jaguare stream and Pinheiros river) in the vicinity of IPEN-CNEN/SP an effluent monitoring program was established on a routine basis. This control is carried out by measuring the activity of the radionuclides present in the liquid effluents (source term) using gamma spectrometry and/or spectrophotometry. The results obtained are then compared with the discharge limits adopted by CNEN when a decision is made upon the discharge of the effluent under consideration. In 1988 the total activity discharged by the nuclear installations available was 1997, 9x10 6 Bq in a total volume of 2421,4 m 3 . The next step was to evaluate the effective equivalent dose in the general public by using the results of the source term and the information available concerning the environment. It was assumed that the only critical pathway is the external gamma irradiation of the people that work in the nearby of the discharge points in Pinheiros river. The effective equivalent dose obtained was 39,4η Sv and the most relevant radionuclides that should be considered 60 Co, 137 Cs, 131 I and 226 Ra. This result is less than 1/10 of the maximum admissible dose limit adopted by the Radiological Protection Standards which is 10 -3 Sv/year. In order to measure the level of radioactivity in the environment, samples of ground water, water and sediments of Pinheiros river were collected and analyzed by using gamma spectrometry and fluorimetry. The radionuclides found were 226 Ra, 22228 Ra, U Nat, 40 K and 7 Be with activities corresponding to the background levels. The analysis of these results and the evaluation of the equivalent dose show that the radiological impact in the aquatic systems considered is insignificant. (author) [pt

  7. PRODUÇÃO E COMPARTILHAMENTO DO CONHECIMENTO NUCLEAR: UM ESTUDO DE CASO NO IEN/CNEN

    Directory of Open Access Journals (Sweden)

    Marcia Pires da Luz Bettencourt

    2012-04-01

    Full Text Available O estudo procurou identificar ações que possam contribuir para a produção e compartilhamento de conhecimentos e informações na Divisão de Radiofármacos do Instituto de Engenharia Nuclear da Comissão Nacional de Energia Nuclear (IEN/CNEN. A motivação para a pesquisa foi o risco, identificado em relatórios da área nuclear, de perda de conhecimento nessa área nos últimos anos. A gestão do conhecimento foi escolhida como ferramenta para o estudo do problema apontado, por possuir metodologias que visam estimular o processo de produção e compartilhamento de conhecimentos e informações, em empresas privadas e também em instituições públicas, como é o caso do IEN/CNEN. A gestão do conhecimento é uma disciplina relativamente nova, que mesmo não tendo nascido na Ciência da Informação, nela vem buscando sustentação teórica e legitimidade. A pesquisa identifica fatores que influenciam no compartilhamento de informação e conhecimento, tais como: redes sociais, comunidades de prática, ambientes facilitadores de colaboração, cultura organizacional, aprendizagem para formação de competências, e narrativas (storytelling. A revisão da literatura e analise dos dados obtidos, diversas práticas foram identificadas, e foram feitas algumas sugestões. Conclui-se que o estímulo institucional à colaboração e à troca de conhecimentos pode influenciar em resultados positivos em relação a um incremento na produção de novos conhecimentos.

  8. The CNEN Helium-Caesium Blow-Down MPD Facility and Experiments with a Prototype Duct

    Energy Technology Data Exchange (ETDEWEB)

    Bertolini, E.; Toschi, R. [CNEN, Frascati (Italy); Lindley, B. C. [C.A. Parsons and Co. Ltd (United Kingdom); Brown, R.; McNab, I. R. [International Research and Development Co. Ltd., Newcastle Upon Tyne (United Kingdom)

    1966-11-15

    The CNEN blow-down loop has been designed to study a helium-caesium MPD generator with particular regard to non-equilibrium ionization effects. An operating condition of the loop is: gas mass flow 0.2 kg/sec, seed fraction 1 at, wt.%, useful pulse duration 20 sec, stagnation temperature 2000 Degree-Sign K, stagnation pressure 5 atm abs, thermal power 1.6 MW, Mach number 0.6, magnetic field 4 Wb/m2, total impurity level less than 100 ppm. A sufficiently wide range of the stagnation conditions can be obtained with the present arrangement of the loop (temperature up to 2000*K, pressure from slightly sub-atmospheric to 6atmabs, gas mass flow from 50 g/sec to 400 g/sec, seed fraction from 0.1 to 2 at. wt.%. The storage heater is an alumina pebble bed electrically heated with tungsten elements and thermally insulated with zirconia fibre; the thermal capacity at 2000 Degree-Sign K is about 1000 MJ. Pure helium is obtained by evaporation of liquid helium at between 4.5 and 5 Degree-Sign K; liquid caesium is injected into a limited section of the pebble bed to provide a mixture of the two gases uniform in density and temperature. The duct is made of boron nitride (5 cm x 3 cm x 22 cm) with 25 pairs of tantalum electrodes whose geometry (electrode width 3 mm, segmentation pitch 9 mm) should prevent current leakage between adjacent electrodes; the duct walls and transfer can be pre-heated up to 1700 Degree-Sign K. A magnetic field of 4 Wb/m{sup 2} is obtained with a pulsed cryogenic magnet with pulse duration of 6 sec. Two series of experiments have been completed to assess the feasibility of the helium-caesium heating system and the generator duct. Heating system experiments, (a) Compatibility of alumina with tungsten, tantalum and caesium, with thermal cycling at 2000 Degree-Sign K; (b) Purification of zirconia fibre and its behaviour at high temperature, with thermal cycling at 2000 Degree-Sign K; (c) Capability of an alumina pebble bed of evaporating, heating and mixing

  9. Evaluation of radiological safety in industrial gammagraphy services during the construction of Bolivia-Brazil gas transmission lines (GASBOL), by regulatory inspections from brazilian CNEN

    International Nuclear Information System (INIS)

    Aquino, Josilto O. de; Silva, Francisco Cesar A. da; Leocadio, Joao Carlos; Pinho, Adaugoberto S. de; Souza, Luiz Antonio C. de; Lourenco, Manoel J.; Nicola, Marcello S.; Melo, Ivan F.

    2001-01-01

    This paper presents a brief description of the Brazilian Regulatory Authority's (National Commission of Nuclear Energy - CNEN) action about safety control on industrial radioactive installations. It shows some specific radiation safety inspections that were done during the construction of the Bolivia-Brazil Gas Transmission Line (GASBOL). In this GASBOL work, it was used industrial radiography sources for weld quality control. During two years were done thirty regulatory safety inspections in these movable installations that use gamma radiography devices. As final result, it was noticed that the national system of inspection to control the safe use of radioactive sources in industrial activities is really efficient because none overexposure was detect and every CNEN's recommendations were applied by the operators. Some result about the gamma devices and violations are also showed. (author)

  10. Portfolio of patents after the Brazilian Innovation Act: the case of the Comissao Nacional de Energia Nuclear - CNEN (Brazilian National Nuclear Energy Commission)

    International Nuclear Information System (INIS)

    Pereira, Gustavo Jose; Guimaraes, Regia Ruth Ramirez; Perry, Katia da Silva Peixoto; Teruya, Dirceu Yoshikazu

    2013-01-01

    The process of technological development is due to the need to promote a solution to a particular problem of agents, compete with products and/or processes on the international market and to promote scientific advancement. Thus, the patent system is a repository of knowledge for protection, for promotion of diffusion through licensing agreements and an indicator of technological development. In 2004, the Brazilian Government enacted the Brazilian Innovation Act and the mechanisms were improved for cooperation between firms and public education, science and technology organisations and also promoted the commercialisation of technology produced by public education, science and technology organisations and the mandatory establishment of Technology Transfer Offices. The Comissao Nacional de Energia Nuclear (CNEN) is a federal agency responsible for basic and applied research in the field of nuclear technology and has used the patent system since the 1980s to protect its knowledge. With the advent of the Innovation Act in 2004, there was a significant boost in requests for patents in CNEN which also established an internal set of normative acts and created a System of Innovation Management and Technology Innovation Offices in its research institutes to support management and dissemination of knowledge. The aim of this case study is to present the profile of the requests for patents by CNEN before and after the enactment of the Brazilian Innovation Act covering the period of time between 1980 and 2010. (author)

  11. Neutron activation analysis at CDTN/CNEN using the IPR-R1 Triga Mark I reactor

    International Nuclear Information System (INIS)

    Menezes, Maria Angela de B.C.; Maretti Junior, Fausto; Kastner, Geraldo Frederico; Amaral, Angela Maria; Souza, Wagner de

    2009-01-01

    This paper describes in summary the activities developed by the Laboratory for Neutron Activation Analysis since the starting up of the IPR-R1 TRIGA Mark I research reactor in 1960. This Laboratory is located at Centro de Desenvolvimento da Tecnologia Nuclear (Nuclear Technology Development Centre) / Comissao Nacional de Energia Nuclear (Brazilian Commission for Nuclear Energy), CDTN/CNEN. The activities of the Laboratory comprise the delayed fission neutron activation analysis, instrumental (comparative and parametric methods) and radiochemical / chemical methods. These methods are responsible for significant percentage of CDTN's analytical demand, meeting the clients' analytical needs and researches developed by the Laboratory, by CDTN and by other institutions. Over the years the work has been linked to the goals of the country and the institutions. Nowadays the neutron activation analysis is responsible for 70% of the analytical demand and the k 0 - Instrumental method for 80% of this demand answering clients' request and researches. In Brazil, CDTN is the only Institute that fully masters the Instrumental Neutron Activation Analysis k 0 -method using its own nuclear reactor. (author)

  12. Radioactive concrete sources at IRD/CNEN, Brazil, for calibration of uranium exploration and environmental field instruments

    International Nuclear Information System (INIS)

    Barreto, P.M.C.; Campos, C.A.; Malheiros, T.M.M.; Locborg, L.

    1988-01-01

    A radiometric calibration system consisting of eight radioactive concrete sources was constructed at the Institute of Radiation Protection and Dosimetry (IRD) of the Brazilian Nuclear Energy Commission (CNEN). These sources, stimulating rock outcrops, are available to geophysicists interested in uranium explotation and scientists working with natural radioactivity in environmental research. The sources are of cylindrical shape with 3m diameter and 0.5m thickness weighing approximately 7.5 tonnes each. They are disposed in a circle having in its centre a 4m diameter water pond for cosmi-ray and instrument noise corrections. Uranium, thorium and potassium ores were added to the concrete under such conditions as to achieve perfect homogenization. One hundred and four samples were collected and analysed by eight laboratories. In addition, in-situ radiometric grade determination were performed with calibrated instruments resulting a total of 2.100 determinations of U, Th and K, from which the reference values were assigned to each source. With this system, it is possible to calculate sensitivity constants and stripping ratios for portable gamma-ray spectrometers. It also provides excellent means for the calibration of radiation detectors used in environmental monitoring, in which humidity, temperature and omni-directional gamma flux, similar to the natural environmental, are simulated. (author) [pt

  13. Production of Cobalt-57 from irradiation of proton beams on nickel at CV-28 cyclotron of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Santos, Liliane Landini Mota; Osso Junior, Joao Alberto

    1996-01-01

    The 57 Co is produced at the Cyclotron of IPEN-CNEN/SP through the irradiation of natural Nickel with a protons beam of 24 MeV energy. The aim of this work was to measure the thick target production yield of 57 Co and of its principal radionuclide impurities and the determination of the excitation functions of the nuclear reactions on Ni, to evaluate the best conditions for the 57 Co production. The technique used was of the stacked-foil, of Ni, Cu and Al, being the two latter utilized as current and energy monitors of the protons beam, respectively. The thick target production yield of 57 Co, through the somatory of indirect and direct reaction, 11,31 days after E.O.B., was 905,76 kBq/μA.h (24,48 μCi/μA.h) and only by indirect reaction was 174,64 kBq/μA.h (4,72 μCi/μA.h). (author)

  14. Review of Brazilian activities related to the thorium fuel cycle and production of thorium compounds at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Lainetti, Paulo E.O.; Freitas, Antonio A.; Mindrisz, Ana C.

    2013-01-01

    The Brazilian's interest in the nuclear utilization of thorium has started in the 50's as a consequence of the abundant occurrence of monazite sands. Since the sixties, IPEN-CNEN/SP has performed some developments related to the thorium fuel cycle. The production and purification of thorium compounds was carried out at IPEN for about 18 years and the main product was the thorium nitrate with high purity, having been produced over 170 metric tons of this material in the period, obtained through solvent extraction. The thorium nitrate was supplied to the domestic industry and used for gas portable lamps (Welsbach mantle). Although the thorium compounds produced have not been employed in the nuclear area, several studies were conducted. Therefore, those activities and the accumulated experience are of strategic importance, on one hand due to huge Brazilian thorium reserves, on the other hand by the resurgence of the interest of thorium for the Generation IV Advanced Reactors. This paper presents a review of the Brazilian research and development activities related to thorium technology. (author)

  15. Radiological practices using dosimetric films and electronic dosimeters in F-18 production at cyclotron complex center at IEN/CNEN

    International Nuclear Information System (INIS)

    Santos, Osvaldir P. dos; Silva, J.C.P.; Silva, Luiz Carlos Reina P. da

    2009-01-01

    The aim of this work is to evaluate, guide and correct radiological practices based on dose rate values obtained from dosimetric films and electronic dosimeters used by technicians involved in Fluorine-18 production facilities at IEN/CNEN. Standard statistical methods have been used to analyze and to evaluate these results. The comparison between these results is the first step to orient decisions concerning radiological practices. Besides, radiometric routine surveys are under evaluation in order to improve radiological control in these facility areas. The electronic dosimeters provide the technicians immediate reading and this help them take protective action immediately. So the comparison between dosimetric film and electronic dosimeters data will provide information about how the recently employed electronic dosimeters are being used and what corrections in their practical use are necessary in order to achieve correct practices. In addition the results and observations obtained will be very important to implement possible changes in radiological routine practices in order to optimize them and keep occupationally exposed individuals radiological dose rates, as low as reasonably achievable, according to ALARA principle. (author)

  16. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de, E-mail: flavia.biaty@usp.br, E-mail: msrocha@ipen.br, E-mail: otavioluis@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  17. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    International Nuclear Information System (INIS)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de

    2017-01-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  18. Validation of dose-response calibration curve for X-Ray field of CRCN-NE/CNEN: preliminary results

    International Nuclear Information System (INIS)

    Silva, Laís Melo; Mendonç, Julyanne Conceição de Goes; Andrade, Aida Mayra Guedes de; Hwang, Suy F.; Mendes, Mariana Esposito; Lima, Fabiana F.; Melo, Ana Maria M.A.

    2017-01-01

    It is very important in accident investigations that accurate estimating of absorbed dose takes place, so that it contributes to medical decisions and overall assessment of long-term health consequences. Analysis of chromosome aberrations is the most developed method for biological monitoring, and frequencies of dicentric chromosomes are related to absorbed dose of human peripheral blood lymphocytes using calibration curves. International Atomic Energy Agency (IAEA) recommends that each biodosimetry laboratory sets its own calibration curves, given that there are intrinsic differences in protocols and dose interpretations when using calibration curves produced in other laboratories, which could add further uncertainties to dose estimations. The Laboratory for Biological Dosimetry CRCN-NE recently completed dose-response calibration curves for X ray field. Curves of chromosomes dicentrics and dicentrics plus rings were made using Dose Estimate. This study aimed to validate the calibration curves dose-response for X ray with three irradiated samples. Blood was obtained by venipuncture from healthy volunteer and three samples were irradiated by x-rays of 250 kVp with different absorbed doses (0,5Gy, 1Gy and 2Gy). The irradiation was performed at the CRCN-NE/CNEN Metrology Service with PANTAK X-ray equipment, model HF 320. The frequency of dicentric and centric rings chromosomes were determined in 500 metaphases per sample after cultivation of lymphocytes, and staining with Giemsa 5%. Results showed that the estimated absorbed doses are included in the confidence interval of 95% of real absorbed dose. These Dose-response calibration curves (dicentrics and dicentrics plus rings) seems valid, therefore other tests will be done with different volunteers. (author)

  19. Production of microspheres labeled with holmium-166 for liver cancer therapy: the preliminary experience at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Costa, Renata F.; Azevedo, Mariangela B.M.; Nascimento, Nanci; Sene, Frank F.; Martinelli, Jose R.; Osso Junior, Joao A.

    2009-01-01

    Microspheres labeled with therapeutic radionuclides for malignancies of liver are widely used in many countries. The internal radionuclide therapy uses a permanently implanted device, such as Therasphere R or SIR-Spheres R , or a biodegradable device that provides structural support for the radionuclide of choice and causes the tumor reduction. Three different types of material supports have been investigated, i.e., biodegradable polymer-based, glass-based and resin-based microspheres. Nowadays there is a project concerning the labeling of these 3 materials with 166 Ho being developed at IPEN-CNEN/SP and coordinated by the Radiopharmacy Directory. 166 Ho(t 1/2 =26.8 h) is a beta minus emitter (E max =1.84 MeV), with right properties for radiotherapy and can be produced with the low power Brazilian Nuclear Reactor IEA-R1m. The aim of this work is to describe the stage of development of this project. The initial experience used resin-based microspheres, a cation exchange resin labeled with 166 Ho, it showed the essential characteristics for liver therapy. Preliminary results of the preparation of glass-based microspheres labeled with 165 Ho showed that 5% of Ho 2 O 3 was incorporated in an aluminosilicate glass, through the process of spheronization by flame, which produced spherical microspheres with 20-40μm particle size. The preparation of biodegradable material, polymer-based microspheres, is in its initial stage and the objective is to prepare and label with 165 Ho different polymer-based microspheres. These combined efforts have been done to offer a national radiotherapeutic product for the the Brazilian nuclear medicine community at fair value and also to offer a viable possibility of treatment for patients affected by liver malignancies. (author)

  20. Validation of dose-response calibration curve for X-Ray field of CRCN-NE/CNEN: preliminary results

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Laís Melo; Mendonç, Julyanne Conceição de Goes; Andrade, Aida Mayra Guedes de; Hwang, Suy F.; Mendes, Mariana Esposito; Lima, Fabiana F., E-mail: falima@cnen.gov.br, E-mail: mendes_sb@hotmail.com [Centro Regional de Ciências Nucleares, (CRCN-NE/CNEN-PE), Recife, PE (Brazil); Melo, Ana Maria M.A., E-mail: july_cgm@yahoo.com.br [Universidade Federal de Pernambuco (UFPE), Vitória de Santo Antão, PE (Brazil). Centro Acadêmico de Vitória

    2017-07-01

    It is very important in accident investigations that accurate estimating of absorbed dose takes place, so that it contributes to medical decisions and overall assessment of long-term health consequences. Analysis of chromosome aberrations is the most developed method for biological monitoring, and frequencies of dicentric chromosomes are related to absorbed dose of human peripheral blood lymphocytes using calibration curves. International Atomic Energy Agency (IAEA) recommends that each biodosimetry laboratory sets its own calibration curves, given that there are intrinsic differences in protocols and dose interpretations when using calibration curves produced in other laboratories, which could add further uncertainties to dose estimations. The Laboratory for Biological Dosimetry CRCN-NE recently completed dose-response calibration curves for X ray field. Curves of chromosomes dicentrics and dicentrics plus rings were made using Dose Estimate. This study aimed to validate the calibration curves dose-response for X ray with three irradiated samples. Blood was obtained by venipuncture from healthy volunteer and three samples were irradiated by x-rays of 250 kVp with different absorbed doses (0,5Gy, 1Gy and 2Gy). The irradiation was performed at the CRCN-NE/CNEN Metrology Service with PANTAK X-ray equipment, model HF 320. The frequency of dicentric and centric rings chromosomes were determined in 500 metaphases per sample after cultivation of lymphocytes, and staining with Giemsa 5%. Results showed that the estimated absorbed doses are included in the confidence interval of 95% of real absorbed dose. These Dose-response calibration curves (dicentrics and dicentrics plus rings) seems valid, therefore other tests will be done with different volunteers. (author)

  1. Study of socio environmental actions of Energy and Nuclear Research Institute of Sao Paulo (IPEN/CNEN-SP)

    International Nuclear Information System (INIS)

    Mutarelli, Rita de Cassia; Sabundjian, Gaiane; Menzel, Francine

    2013-01-01

    Over the years the evolution of environmental concept comes solidifying increasingly through programs, conferences and various activities taking place in Brazil and worldwide. As a result of this development, sustainability and social responsibility began to be seen as something present in day to day business and institutions. In particular, the Institute of Energy and Nuclear Research (IPEN), state authority associated with University of Sao Paulo (USP) and managed by the National Commission of Nuclear Energy (CNEN), subordinate the Ministry of Science and Technology, which is the focus of this work, has the mission the commitment to society as regards: improving the quality of life of the population, producing scientific knowledge, developing technologies, generating products and services and training human resources in nuclear and related. Based on the mission of IPEN and in the lack of assessment tools of social actions, this paper aims to propose an instrument for assessing social responsibility and serve as a methodological option, strongly committed to the pursuit of improvements of IPEN. Through indicators and dimensions, built up a methodology that seeks to assess social responsibility and identify strengths, to be encouraged and weaknesses, which can be studied and improved. This methodology was applied to IPEN and the results that are presented in this work identified positives regarding their actions to their domestic audience and points to be improved in relation to their external audience. As an initial evaluation, the results were satisfactory; however, this work will continue in order to suggest the implementation of social and environmental actions feasible to be applied in IPEN. (author)

  2. Comparison between dosimeter films and electronic dosimeters results obtained in F-18 production practices at IEN/CNEN

    International Nuclear Information System (INIS)

    Paulo, Osvaldir; Carlos, Luiz R.J.; Mendes, Milton

    2008-01-01

    Full text: The aim of the present work is the comparison of the dose rates values obtained from dosimeter films with the values obtained from electronic dosimeters used by radiological protection technician involved in practices with fluorine-18 production in CV-28 cyclotron at IEN/CNEN. The motivation for this work was the increase on the demand of this radiopharmaceutical. Nowadays there is an increase demand on the number of clinics and hospitals which had started to use the technique of radiodiagnostic using positron-emission tomography (PET). Therefore, the produced radionuclide activities (physics quantity) and also the complexity of the practices of radiological protection in the areas of that facility had increased a lot. The conventional statistical methods will be used to evaluate the results obtained in the analysis of the data obtained in the reading of the dosimeters. This comparative method is however a first step to taking decisions regarding radiological protection service. Therefore that the radiometric surveys of routine are taken in consideration, as well as the information from the technician of radiological protection that is working in those areas. All this data will give support to improve and implement methods and practices on the accelerators' facilities. In addition, the use of these electronic dosimeters will makes possible the technician read these dose rates received immediately during the practices and use these information you make decisions. In case of dose rates values to present above the expected the practice will be ploughed. Another point to be considered is that this work will propitiate the future updates of the procedures designated to those practices and to conduct at the radiological protection optimization. (author)

  3. The whole body counting experience on the internal contamination of radionuclides at IPEN/CNEN-SP, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cardoso, Joaquim C.S.; Xavier, Marcos, E-mail: jcardoso@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2017-07-01

    The intake of radioactive material by workers can occur in the radiopharmaceuticals production, during the handling of these in the medical fields (nuclear medicine) and in biological and research laboratories. The workers who work in areas where exposures are significant are routinely monitored to demonstrate that the workers are receiving adequate protection from internal contamination. Direct measurements of whole-body and thyroid contents provide an estimate of the activity of these radionuclides in the potentially exposed workers. The whole-body measurements of the workers, trainees and visitors are routinely performed by the In Vivo Monitoring Laboratory (LMIV) of the Energy and Nuclear Research Institute (IPEN/CNEN-SP). The frequency of measurements is defined by the Radioprotection Service (SRP) and the Dose Calculation Group of IPEN. For this purpose LMIV has two counters whole body. NalTl ( 8 x 4″), and thyroid one, NaITl (3 x 3″). The system was calibrated in energy and efficiency, with calibration sources of Eu-152, Am-241 and Co-60 with gamma emissions between 59.54 and 1408.08 keV, positioned within Alderson Research Labs. anthropomorphic phantom. The background measures were obtained of worker's spectrum that was not exposed occupationally yet. The concepts adopted in the HPS N13.30 Standard and proposed in ISO documents for standardization were used for activity measurements. During the period January 2012 to December 2016, approximately 3800 measurements had been carried in workers who develop tasks related to the production and research. The activities of the radionuclides and the workers' tasks relationship had been evaluated. (author)

  4. The experience of CDTN/CNEN, Centro de Desenvolvimento da Tecnologia Nuclear: A medium size nuclear research centre in Brazil

    International Nuclear Information System (INIS)

    Sobrinho, P.

    2001-01-01

    At first a university research centre, then a captive research centre of the state owned company in charge of establishing a nuclear industry in Brazil, then a research centre of CNEN (the Brazilian Nuclear Energy Authority), nearing its 50 th anniversary, CDTN has a rich experience. even keeping the project portfolio around a number of traditional nuclear energy areas such as nuclear reactors, materials, environment, process engineering, waste management, radiological protection, the institution experienced an evolution in the substance of the proposed projects. This evolution represents the different institutional insertions, but the major changes occurred at a time when, due to a lesser demand from the nuclear sector and other factors, the explicit idea of producing outputs for the benefit of society received a large acceptance from the employees. The challenges to the institution at this time are commented upon. Retirements, coupled to the lack of job openings, work together for the decrease in the staff number, one major challenge. Up to a certain point, private companies have been hired to fill some of the organisational needs, but it is felt that a limit to this policy is being reached. It is argued that, even in the absence of a strong demand from the energy generation sector, a number of opportunities are still available to a NRC in a developing country. Maturity of nuclear energy and applications of radiation tend to transfer the focus of the activities from the fundamentals of nuclear science and technology to quality related issues, a requirement of the modern times. quality systems cannot substitute for the in depth knowledge of the fundamentals. (author)

  5. Improvement of the WBC calibration of the Internal Dosimetry Laboratory of the CDTN/CNEN using MCNPX code

    Energy Technology Data Exchange (ETDEWEB)

    Guerra P, F.; Heeren de O, A. [Universidade Federal de Minas Gerais, Departamento de Engenharia Nuclear, Programa de Pos Graduacao em Ciencias e Tecnicas Nucleares, Av. Pte. Antonio Carlos 6627, 31270-901 Belo Horizonte, Minas Gerais (Brazil); Melo, B. M.; Lacerda, M. A. S.; Da Silva, T. A.; Ferreira F, T. C., E-mail: tcff01@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear, Programa de Pos Graduacao / CNEN, Av. Pte. Antonio Carlos 6627, 31270-901 Belo Horizonte, Minas Gerais (Brazil)

    2015-10-15

    The Plan of Radiological Protection licensed by the National Nuclear Energy Commission - CNEN in Brazil includes the risks of assessment of internal and external exposure by implementing a program of individual monitoring which is responsible of controlling exposures and ensuring the maintenance of radiation safety. The Laboratory of Internal Dosimetry of the Center for Development of Nuclear Technology - LID/CDTN is responsible for routine monitoring of internal contamination of the Individuals Occupationally Exposed (IOEs). These are, the IOEs involved in handling {sup 18}F produced by the Unit for Research and Production of Radiopharmaceuticals sources; as well a monitoring of the entire body of workers from the Research Reactor TRIGA IPR-R1/CDTN or whenever there is any risk of accidental incorporation. The determination of photon emitting radionuclides from the human body requires calibration techniques of the counting geometries, in order to obtain a curve of efficiency. The calibration process normally makes use of physical phantoms containing certified activities of the radionuclides of interest. The objective of this project is the calibration of the WBC facility of the LID/CDTN using the BOMAB physical phantom and Monte Carlo simulations. Three steps were needed to complete the calibration process. First, the BOMAB was filled with a KCl solution and several measurements of the gamma ray energy (1.46 MeV) emitted by {sup 40}K were done. Second, simulations using MCNPX code were performed to calculate the counting efficiency (Ce) for the BOMAB model phantom and compared with the measurements Ce results. Third and last step, the modeled BOMAB phantom was used to calculate the Ce covering the energy range of interest. The results showed a good agreement and are within the expected ratio between the measured and simulated results. (Author)

  6. Study of socio environmental actions of Energy and Nuclear Research Institute of Sao Paulo (IPEN/CNEN-SP)

    Energy Technology Data Exchange (ETDEWEB)

    Mutarelli, Rita de Cassia; Sabundjian, Gaiane; Menzel, Francine, E-mail: rmutarelli@gmail.com, E-mail: gdjian@ipen.br, E-mail: fmenzel@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    Over the years the evolution of environmental concept comes solidifying increasingly through programs, conferences and various activities taking place in Brazil and worldwide. As a result of this development, sustainability and social responsibility began to be seen as something present in day to day business and institutions. In particular, the Institute of Energy and Nuclear Research (IPEN), state authority associated with University of Sao Paulo (USP) and managed by the National Commission of Nuclear Energy (CNEN), subordinate the Ministry of Science and Technology, which is the focus of this work, has the mission the commitment to society as regards: improving the quality of life of the population, producing scientific knowledge, developing technologies, generating products and services and training human resources in nuclear and related. Based on the mission of IPEN and in the lack of assessment tools of social actions, this paper aims to propose an instrument for assessing social responsibility and serve as a methodological option, strongly committed to the pursuit of improvements of IPEN. Through indicators and dimensions, built up a methodology that seeks to assess social responsibility and identify strengths, to be encouraged and weaknesses, which can be studied and improved. This methodology was applied to IPEN and the results that are presented in this work identified positives regarding their actions to their domestic audience and points to be improved in relation to their external audience. As an initial evaluation, the results were satisfactory; however, this work will continue in order to suggest the implementation of social and environmental actions feasible to be applied in IPEN. (author)

  7. Optimization of the internal target system of the C V-28 cyclotron at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Araujo, Sumair Gouveia de

    1996-01-01

    The C V-28 cyclotron at IPEN-CNEN/S P is used mainly for radioisotope production to be utilized in nuclear medicine for diagnostic purposes. Among these radioisotopes we can cite 67 Ga and 111 In, which are obtained by irradiation of Zn and Cd solid targets. Up to now, the irradiations were performed in the external beam line, which has limitations in beam current due to the extraction system, that can at best extract between 50 and 70% of the produced beam. This is a critical point for an efficient radioisotope production. A possible solution to achieve high beam currents is a system that allows the irradiation of these solid targets with the internal beam. In this case, the total produced beam can be used. For this, the objective of this work was to modify and improve the internal target system of the C V-28 Cyclotron, which had three critical points in the original project, that made the system useless. First, the transport of the target to the irradiation position was modified: the pneumatic tube was changed to a motor drive service. Secondly, the target cooling system was improved. Third and the most critical, the modification on the locking system of the target holder that could bring the cyclotron tank to atmosphere. These modifications implied on a change in all logical sequence of the target control. With these modifications the system became more versatile and showed more reproducibility and reliability than the original internal target system. The loss of mass in natural Zn targets irradiated with currents up to 80 μA was negligible. The production yield of 67 Ga obtained, at EOB, was 21.2 MBq/μAh (0.57 mCi/μAh), that is in good agreement with those obtained in the irradiation with external beams. (author)

  8. Improvement of the WBC calibration of the Internal Dosimetry Laboratory of the CDTN/CNEN using MCNPX code

    International Nuclear Information System (INIS)

    Guerra P, F.; Heeren de O, A.; Melo, B. M.; Lacerda, M. A. S.; Da Silva, T. A.; Ferreira F, T. C.

    2015-10-01

    The Plan of Radiological Protection licensed by the National Nuclear Energy Commission - CNEN in Brazil includes the risks of assessment of internal and external exposure by implementing a program of individual monitoring which is responsible of controlling exposures and ensuring the maintenance of radiation safety. The Laboratory of Internal Dosimetry of the Center for Development of Nuclear Technology - LID/CDTN is responsible for routine monitoring of internal contamination of the Individuals Occupationally Exposed (IOEs). These are, the IOEs involved in handling 18 F produced by the Unit for Research and Production of Radiopharmaceuticals sources; as well a monitoring of the entire body of workers from the Research Reactor TRIGA IPR-R1/CDTN or whenever there is any risk of accidental incorporation. The determination of photon emitting radionuclides from the human body requires calibration techniques of the counting geometries, in order to obtain a curve of efficiency. The calibration process normally makes use of physical phantoms containing certified activities of the radionuclides of interest. The objective of this project is the calibration of the WBC facility of the LID/CDTN using the BOMAB physical phantom and Monte Carlo simulations. Three steps were needed to complete the calibration process. First, the BOMAB was filled with a KCl solution and several measurements of the gamma ray energy (1.46 MeV) emitted by 40 K were done. Second, simulations using MCNPX code were performed to calculate the counting efficiency (Ce) for the BOMAB model phantom and compared with the measurements Ce results. Third and last step, the modeled BOMAB phantom was used to calculate the Ce covering the energy range of interest. The results showed a good agreement and are within the expected ratio between the measured and simulated results. (Author)

  9. Production of microspheres labeled with holmium-166 for liver cancer therapy: the preliminary experience at IPEN/CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Renata F.; Azevedo, Mariangela B.M.; Nascimento, Nanci; Sene, Frank F.; Martinelli, Jose R.; Osso Junior, Joao A., E-mail: renatafcosta@usp.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2009-07-01

    Microspheres labeled with therapeutic radionuclides for malignancies of liver are widely used in many countries. The internal radionuclide therapy uses a permanently implanted device, such as Therasphere{sup R} or SIR-Spheres{sup R}, or a biodegradable device that provides structural support for the radionuclide of choice and causes the tumor reduction. Three different types of material supports have been investigated, i.e., biodegradable polymer-based, glass-based and resin-based microspheres. Nowadays there is a project concerning the labeling of these 3 materials with {sup 166}Ho being developed at IPEN-CNEN/SP and coordinated by the Radiopharmacy Directory. {sup 166}Ho(t{sub 1/2}=26.8 h) is a beta minus emitter (E{sub max}=1.84 MeV), with right properties for radiotherapy and can be produced with the low power Brazilian Nuclear Reactor IEA-R1m. The aim of this work is to describe the stage of development of this project. The initial experience used resin-based microspheres, a cation exchange resin labeled with {sup 166}Ho, it showed the essential characteristics for liver therapy. Preliminary results of the preparation of glass-based microspheres labeled with {sup 165}Ho showed that 5% of Ho{sub 2}O{sub 3} was incorporated in an aluminosilicate glass, through the process of spheronization by flame, which produced spherical microspheres with 20-40mum particle size. The preparation of biodegradable material, polymer-based microspheres, is in its initial stage and the objective is to prepare and label with {sup 165}Ho different polymer-based microspheres. These combined efforts have been done to offer a national radiotherapeutic product for the the Brazilian nuclear medicine community at fair value and also to offer a viable possibility of treatment for patients affected by liver malignancies. (author)

  10. The whole body counting experience on the internal contamination of radionuclides at IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Cardoso, Joaquim C.S.; Xavier, Marcos

    2017-01-01

    The intake of radioactive material by workers can occur in the radiopharmaceuticals production, during the handling of these in the medical fields (nuclear medicine) and in biological and research laboratories. The workers who work in areas where exposures are significant are routinely monitored to demonstrate that the workers are receiving adequate protection from internal contamination. Direct measurements of whole-body and thyroid contents provide an estimate of the activity of these radionuclides in the potentially exposed workers. The whole-body measurements of the workers, trainees and visitors are routinely performed by the In Vivo Monitoring Laboratory (LMIV) of the Energy and Nuclear Research Institute (IPEN/CNEN-SP). The frequency of measurements is defined by the Radioprotection Service (SRP) and the Dose Calculation Group of IPEN. For this purpose LMIV has two counters whole body. NalTl ( 8 x 4″), and thyroid one, NaITl (3 x 3″). The system was calibrated in energy and efficiency, with calibration sources of Eu-152, Am-241 and Co-60 with gamma emissions between 59.54 and 1408.08 keV, positioned within Alderson Research Labs. anthropomorphic phantom. The background measures were obtained of worker's spectrum that was not exposed occupationally yet. The concepts adopted in the HPS N13.30 Standard and proposed in ISO documents for standardization were used for activity measurements. During the period January 2012 to December 2016, approximately 3800 measurements had been carried in workers who develop tasks related to the production and research. The activities of the radionuclides and the workers' tasks relationship had been evaluated. (author)

  11. Internal contamination monitoring through measurements in vivo at whole body contamination unity of IRD-CNEN, Rio de Janeiro, Brazil; Monitoracao da contaminacao interna atraves de medicoes in vivo na Unidade de Contador de Corpo Inteiro do IRD-CNEN, Rio de Janeiro, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Dantas, Ana Leticia A.; Lucena, Eder A.; Dantas, Bernardo M., E-mail: adantas@ird.gov.b, E-mail: eder@ird.gov.b, E-mail: bmdantas@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. de Monitoracao In Vivo. Servico de Monitoracao Individual Interna

    2011-10-26

    The present work approaches the internal contamination monitoring capacity through measurements performed at the Whole-body Counter Unity of the in-vivo monitoring laboratory (LABMIV) of the IRD-CNEN, Rio de Janeiro, Brazil, present thr main parameters related to the monitoring techniques developed, and the the available instrumentation for identification and quantification in vivo of photon emitter radionuclides with energy in the range of 10-3000 keV, incorporated by workers and public individuals

  12. Procedures for calibration of clinical dosemeters of radiotherapy with gamma radiation Co-60 in the IPEN-CNEN, Sao Paulo, Brazil

    International Nuclear Information System (INIS)

    Damatto, Willian B.; Santos, Gelson P.; Potiens, Maria da Penha A.; Vivolo, Vitor

    2009-01-01

    The periodic calibration of clinic dosimeters is a very important task, because those measurement systems performing the control quality of the radioactive source and for that assure the control quality of the patient dose estimative. This paper shows the calibration procedures and routine improved in the calibration laboratory of IPEN/CNEN-SP to be applied to the clinic dosimeters following international and national recommendations and yet the spend care that the clients should have with the utilization of that measurement systems for control quality of the radiotherapy procedures, for reduce the dose received for patient, and workers, and for increase the confidence level of the measurements.(author)

  13. Considerations about the impact of the Convention on Nuclear Safety on the regulatory action of the CNEN in Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    Camargo, Claudio; Pontedeiro, Auro

    1995-01-01

    Preliminary discussion is conducted about the impact of the terms of the Convention on Nuclear safety, adopted by Diplomatic Conference in September 1994 in the International Atomic Energy Agency, on the regulatory action of Brazilian Nuclear Regulatory Body - CNEN. Following the Convention articles structure, the paper emphasizes technical aspects of the nuclear safety standards adopted in the licensing process of Brazilian Nuclear Power Plants. The recent experience in the issuance of Angra-1 NPP Permanent Operation Authorization is used to demonstrate that current safety standards in Brazil are in compliance with the international compromises and in agreement with what is expected by the so called Safety Culture. (author). 9 refs

  14. Proposal of a model for evaluation of research and development projects in a public scientific and technological institution: a survey in CNEN

    International Nuclear Information System (INIS)

    Silva, Eduardo de Assumpcao

    2017-01-01

    Science and technology are directly related to the development of a country. The research and development projects in CNEN are financed by the direct resources of the budget of the Union and of the Development Agencies such as FINEP and CNPq. In general, project managers believe they can succeed when they complete a project on schedule, budget, and anticipated requirements, which is commonly known as a 'triple constraint' or 'iron triangle'. However, in the review of the literature, other criteria for evaluating success in projects, such as the benefits generated by society, the development of the team's capabilities, future opportunities, new technologies, among others, were verified. In this way, in order to assist the manager in the evaluation of this type of project, the present research carried out a review in the literature aiming to find concepts about success in projects and their evaluation criteria, proposed a model based on the theoretical reference and Importance and use of these criteria with the CNEN specialists, who work directly in the R and D projects of a public ICT in the nuclear area. The results showed that the criteria proposed in the model have a high degree of importance and show a decrease in the degree of utilization, suggesting that the criteria used in the model can help managers in the evaluation of these projects. (author)

  15. Prospection of implementation of distance learning at IPEN/CNEN-SP for the course on fundamentals of nuclear physics using infrastructure of free software

    Energy Technology Data Exchange (ETDEWEB)

    Tondin, Jose Egidio M.; Menezes, Mario O. de; Vasconcellos, Marina B.A.; Osso Junior, Joao A., E-mail: mbvascon@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2009-07-01

    The main objective of the present work is to prospect the implementation of the methods and techniques of distance learning to the course of Fundamentals of Nuclear Physics,which is obligatory for all students of the graduate course of IPEN/CNEN-SP (USP - Area of Nuclear Technology). It was chosen the free software MOODLE (Modular Object-Oriented Dynamic Learning Environment), created in 2001, which allows the collaborative educational work by means of internet navigation. The first part of the present work was to prepare a pilot project for the implantation of distance learning for the course on Fundamentals of Nuclear Physics at the graduate course of IPEN/CNEN-SP, by inserting in the platform all the lecture presentations prepared by the teacher responsible for the course, as well as papers related to the subject, videos, exercises and tests. A total of 118 students at MSc and PhD levels of IPEN participated of the research, as well as 16 professors responsible for several courses at IPEN. The data collection comprised the following phases: questionnaires about the profile of the students, utilization of the course inserted in the Moodle platform, opinion of the students about the use of the platform and opinion of the professors about distance learning. (author)

  16. Prospection of implementation of distance learning at IPEN/CNEN-SP for the course on fundamentals of nuclear physics using infrastructure of free software

    International Nuclear Information System (INIS)

    Tondin, Jose Egidio M.; Menezes, Mario O. de; Vasconcellos, Marina B.A.; Osso Junior, Joao A.

    2009-01-01

    The main objective of the present work is to prospect the implementation of the methods and techniques of distance learning to the course of Fundamentals of Nuclear Physics,which is obligatory for all students of the graduate course of IPEN/CNEN-SP (USP - Area of Nuclear Technology). It was chosen the free software MOODLE (Modular Object-Oriented Dynamic Learning Environment), created in 2001, which allows the collaborative educational work by means of internet navigation. The first part of the present work was to prepare a pilot project for the implantation of distance learning for the course on Fundamentals of Nuclear Physics at the graduate course of IPEN/CNEN-SP, by inserting in the platform all the lecture presentations prepared by the teacher responsible for the course, as well as papers related to the subject, videos, exercises and tests. A total of 118 students at MSc and PhD levels of IPEN participated of the research, as well as 16 professors responsible for several courses at IPEN. The data collection comprised the following phases: questionnaires about the profile of the students, utilization of the course inserted in the Moodle platform, opinion of the students about the use of the platform and opinion of the professors about distance learning. (author)

  17. Radiation protection program applied to occupationally exposed individuals at the IPEN/CNEN-SP pilot plant in the 1980s for natural uranium compounds

    International Nuclear Information System (INIS)

    Silva, Teresinha de Moraes da; Sordi, Gian Maria A.A.; Vasques, Francisco Mário Feijó

    2017-01-01

    The work evidences the chemical processing of natural uranium from the yellowcake phase to the production of UF 6 natural uranium hexafluoride, a process carried out at the IPEN/CNEN-SP pilot plant. Radiation protection management was intended to monitor occupationally exposed individuals - IOEs, the workplace and the environment. An individual monitoring program for IOEs was developed for both external irradiation and incorporation of radioactive material. The IOEs were monitored externally with film-type dosimeters and the in vitro method was applied internally for urine analysis. For the workplace the monitoring program for equipment and floors was developed, determining the exposure rate from the process equipment, surface contamination expressed in Bq.cm -2 in equipment and floors, complemented by the air monitoring program both for the worker as well as for the workplace. Cellulose filters with aerodynamic diameter of 0.3 micron to 8.0 micron were used

  18. Radioprotection planned operation to deactivate an old fabrication plant of UO2 pellets in IPEN - CNEN/SP to perform decommissioning

    International Nuclear Information System (INIS)

    Sanchez Cambises, Paulo Brasil; Paiva, Julio Evangelista de; Almeida, Claudio C.; Silva, Teresinha M.; Rodrigues, Demerval L.

    2008-01-01

    In this work, the steps adopted in the operation planned for the deactivation and decommissioning of the previous plant (building 24), to manufacture the tablets of dioxide of Uranium of the Nuclear and Energy Research Institute, IPEN - CNEN/SP are shown, with decommissioning aims. This operation involved the planning, training the operators of the installation, radiometric analysis of the workstations and surveys for monitoring external radiation, contaminated surfaces and air contamination. The training involved the procedures for the manipulation of radioactive materials, decontamination of surfaces, segregation of materials and practical procedures for monitoring the individual surface body contamination, footwear and clothes. Procedures for the transport of radioactive materials had also been established, relative to the internal rules of the installation; provisory confinement of wastes; effluent, riddance of materials and finding areas free of contamination. (author)

  19. Radioprotection planned operation to deactivate an old fabrication plant of UO{sub 2} pellets in IPEN-CNEN/SP to perform decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Cambises, Paulo B.S.; Paiva, Julio Evangelista de; Almeida, Claudio C.; Silva, Teresinha M.; Rodrigues, Demerval L. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mails: cambises@ipen.br; jepaiva@ipen.br; calmeida@ipen.br; tmsilva@ipen.br; dlrodri@ipen.br

    2007-07-01

    In this work, the steps adopted in the operation planned for the deactivation of the previous plant (building 24), to manufacture the tablets of dioxide of Uranium of the Nuclear and Energy Research Institute, IPEN - CNEN/SP are shown, with decommissioning aims. This operation involved the planning, training the operators of the installation, radiometric analysis of the workstations and surveys for monitoring external radiation, contaminated surfaces and air contamination . The training involved the procedures for the manipulation of radioactive materials, decontamination of surfaces, segregation of materials and practical procedures for monitoring the individual surface body contamination, footwear and clothes. Procedures for the transport of radioactive materials had also been established, relative to the internal rules of the installation; provisory confinement of wastes; effluent, riddance of materials and finding areas free of contamination. (author)

  20. Radioprotection planned operation to deactivate an old fabrication plant of UO2 pellets in IPEN-CNEN/SP to perform decommissioning

    International Nuclear Information System (INIS)

    Cambises, Paulo B.S.; Paiva, Julio Evangelista de; Almeida, Claudio C.; Silva, Teresinha M.; Rodrigues, Demerval L.

    2007-01-01

    In this work, the steps adopted in the operation planned for the deactivation of the previous plant (building 24), to manufacture the tablets of dioxide of Uranium of the Nuclear and Energy Research Institute, IPEN - CNEN/SP are shown, with decommissioning aims. This operation involved the planning, training the operators of the installation, radiometric analysis of the workstations and surveys for monitoring external radiation, contaminated surfaces and air contamination . The training involved the procedures for the manipulation of radioactive materials, decontamination of surfaces, segregation of materials and practical procedures for monitoring the individual surface body contamination, footwear and clothes. Procedures for the transport of radioactive materials had also been established, relative to the internal rules of the installation; provisory confinement of wastes; effluent, riddance of materials and finding areas free of contamination. (author)

  1. Production and sharing of the nuclear knowledge: knowledge management at the Radiopharmaceutical Division of the Instituto de Engenharia Nuclear of Brazilian CNEN

    International Nuclear Information System (INIS)

    Bettencourt, Marcia Pires da Luz

    2011-01-01

    The Brazilian nuclear area made great progress in recent years, bringing many benefits to society, not only in producing electric power, but also in agriculture, industry and medicine. One of the problems in this area, nowadays, is the risk losing nuclear knowledge. Although it is difficult to understand how knowledge is created and used, can be seen that the sharing and production are influenced by some factors that provide favorable conditions. This research focused its attention on identifying actions that contribute to the production and sharing of knowledge and information at the Divisão de Radiofármacos of Instituto de Engenharia Nuclear of Comissão Nacional de Energia Nuclear (IEN/CNEN). Knowledge management was chosen as a tool to study the problem identified, because it has methodologies aimed at stimulating the knowledge production process and knowledge and information sharing, both in private companies and public institutions, such as IEN/CNEN. Knowledge management is an interdisciplinary relatively new discipline, and although it had not been born in Information Science, there has been seeking theoretical support and legitimacy at this interdisciplinary science. This research conceptualizes, historically contextualizes and analyzes developments and trends in knowledge management. The study discourses on the peculiarities and aspects in common between the knowledge management and information management and identifies factors that influence the sharing of information and knowledge such as: social networks, communities of practice, collaborative spaces, organizational culture, organizational learning, and storytelling. In reviewing the literature and after data analysis of interviews, some actions have been identified, and it was possible to make some suggestions. It is concluded that institutional incentive for collaboration and knowledge sharing can influence positive results and increase the production of new knowledge. (author)

  2. Proposal of a model for evaluation of research and development projects in a public scientific and technological institution: a survey in CNEN; Proposta de modelo de avaliacao de projetos de pesquisa e desenvolvimento em uma instituicao cientifica e tecnologica publica da area nuclear: um survey na CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Eduardo de Assumpcao

    2017-11-01

    Science and technology are directly related to the development of a country. The research and development projects in CNEN are financed by the direct resources of the budget of the Union and of the Development Agencies such as FINEP and CNPq. In general, project managers believe they can succeed when they complete a project on schedule, budget, and anticipated requirements, which is commonly known as a 'triple constraint' or 'iron triangle'. However, in the review of the literature, other criteria for evaluating success in projects, such as the benefits generated by society, the development of the team's capabilities, future opportunities, new technologies, among others, were verified. In this way, in order to assist the manager in the evaluation of this type of project, the present research carried out a review in the literature aiming to find concepts about success in projects and their evaluation criteria, proposed a model based on the theoretical reference and Importance and use of these criteria with the CNEN specialists, who work directly in the R and D projects of a public ICT in the nuclear area. The results showed that the criteria proposed in the model have a high degree of importance and show a decrease in the degree of utilization, suggesting that the criteria used in the model can help managers in the evaluation of these projects. (author)

  3. Results of the technical evaluation of dentistry X-ray equipment of a faculty of Dentistry of Rio Grande do Sul State, based on Regulation 453 of Health Ministry and IRD/CNEN-BR recommendations

    International Nuclear Information System (INIS)

    Staevie, G.L.G.; Jahn, T.R.; Barbieri, D.X.; Mas, C.R Dal; Sbaraini, P.; Saba, J.C.P.

    2001-01-01

    This paper describes the technical evaluation of odontology X-ray equipment installed in a local school of odontology with regard to the fulfillment of requirements of Regulation No. 453, issued by Brazilian Ministry of Health and the recommendations of the Institute of Radiation Protection and Dosimetry, IRD/CNEN. Fifteen intra-oral odontology X-ray equipment were evaluated and their conformities and non-conformities were identified, followed by recommendations to be adopted by the school. (author)

  4. Radiation protection program applied to occupationally exposed individuals at the IPEN/CNEN-SP pilot plant in the 1980s for natural uranium compounds; Programa de radioproteção aplicado aos indivíduos ocupacionalmente expostos na usina piloto do IPEN-CNEN/SP na década de 80 para compostos de urânio natural

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Teresinha de Moraes da; Sordi, Gian Maria A.A.; Vasques, Francisco Mário Feijó, E-mail: tmsilva@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The work evidences the chemical processing of natural uranium from the yellowcake phase to the production of UF{sub 6} natural uranium hexafluoride, a process carried out at the IPEN/CNEN-SP pilot plant. Radiation protection management was intended to monitor occupationally exposed individuals - IOEs, the workplace and the environment. An individual monitoring program for IOEs was developed for both external irradiation and incorporation of radioactive material. The IOEs were monitored externally with film-type dosimeters and the in vitro method was applied internally for urine analysis. For the workplace the monitoring program for equipment and floors was developed, determining the exposure rate from the process equipment, surface contamination expressed in Bq.cm{sup -2} in equipment and floors, complemented by the air monitoring program both for the worker as well as for the workplace. Cellulose filters with aerodynamic diameter of 0.3 micron to 8.0 micron were used.

  5. O Processo de Avaliação de Estagiários da Comissão Nacional de Energia Nuclear - CNEN: focalizando seu instrumento

    Directory of Open Access Journals (Sweden)

    Regina Márcia Rocha Lidington

    2010-01-01

    Full Text Available O artigo apresenta o processo avaliativo e os resultados da avaliação do instrumento utilizado para a avaliação de estagiários da Comissão Nacional de Energia Nuclear - CNEN, denominado Avaliação do Estágio pelo Supervisor. A avaliação se concentrou na definição dos cinco Conceitos utilizados para avaliar os nove Aspectos que compõem o instrumento, buscando estabelecer Padrões capazes de minimizar o efeito das interferências subjetivas capazes de comprometer a avaliação do estagiário. Foram utilizadas as abordagens Centrada nos Consumidores, Centrada em Especialistas e Responsiva. Participaram do processo avaliativo os três públicos interessados: Ex-estagiários, Orientadores/Supervisores de Estágio e profissionais da área de Recursos Humanos que atuam no gerenciamento do Programa de Estágios, na Instituição. Os resultados do estudo englobam sugestões de ordem quantitativa e qualitativa para cada um dos Padrões propostos no instrumento.

  6. Two-faces stationary irradiation method and dosimetric considerations for radiation processing at the multipurpose gamma irradiation facility / IPEN-CNEN

    International Nuclear Information System (INIS)

    Santos, Paulo S.; Vasquez, Pablo A.S.

    2015-01-01

    Over the last ten years, the Multipurpose Gamma Irradiation Facility of the Nuclear and Energy Research Institute - IPEN/CNEN located inside the Sao Paulo University campus has been providing services on radiation processing, especially for sterilization of health care and disposable medical products as well as support to research studies on modification of physical, chemical and biological properties of several materials. Placed at the same campus operates an extremely important radiopharmaceutical production facility when almost all disposable supplies used to produce medical products as the technetium-99m are continuously sterilized by gamma radiation. Many university biomedical research laboratories specially those working with equipment for cell cultures and vaccine production also make use of the gamma sterilization. Animal feed and shavings used by certified bioteries are routinely disinfected. Alternative underwater irradiation methods were developed to meet the demand of gemstone color enhancement. Human tissues including bone, skin, amniotic membranes, tendons, and cartilage belonging to National Banks are usually irradiated too. Different kind of polymers, hydrogels, foods as well native fruits, have been irradiated in this facility. Cultural heritage objects as books, paintings and furniture are disinfected routinely by gamma radiation. The success of the implementation of radiation processing in this facility is due to research and development of irradiation and dosimetry methods suitable for each condition. In this work are presented some considerations about the distribution dose and the two-faces stationary irradiation method developed and validated for this facility. (author)

  7. Immunoradiometric assay for the determination of E. coli proteins in recombinant dna derived human growth hormone produced at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Soares, Carlos R.J.

    1995-01-01

    An immunoradiometric assay (IRMA) for the determination of multiple antigens was set up in order to quantify E. coli (ECP) in lots of purified recombinant human growth hormone (rec-hGH). SDS-PAGE and Western Blotting techniques were carried out, in parallel, to confirm the results obtained by IRMA and to provide more information about the contaminants. Anti-ECP antibodies were obtained by rabbit immunization with ECP, which were submitted to the same purification process utilized for rec-hGH with the exception of the last step. A strain-process-specific assay was thus set up. The antiserum obtained was purified through an affinity column prepared with the same ECP used for immunization, this provided an highly sensitive assay (0,03 ng ECP/mL). This IRMA was shown to be specific, not presenting any cross reaction with hGH and studies carried out on precision, accuracy and linearity of response with dilution confirmed its validity as one of the fundamental purity tests for rec-hGH produced at IPEN-CNEN/SP, whose principles can be easily extended to the analysis of other similar products. These studies have also shown that the utilization of an affinity column, prepared with the described anti-ECP antiserum was very effective, providing rec-hGH lots with less then 10 parts per million (0,001%) of contaminating proteins. (author). 45 refs., 15 figs., 11 tabs

  8. Two-faces stationary irradiation method and dosimetric considerations for radiation processing at the multipurpose gamma irradiation facility / IPEN-CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Paulo S.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    Over the last ten years, the Multipurpose Gamma Irradiation Facility of the Nuclear and Energy Research Institute - IPEN/CNEN located inside the Sao Paulo University campus has been providing services on radiation processing, especially for sterilization of health care and disposable medical products as well as support to research studies on modification of physical, chemical and biological properties of several materials. Placed at the same campus operates an extremely important radiopharmaceutical production facility when almost all disposable supplies used to produce medical products as the technetium-99m are continuously sterilized by gamma radiation. Many university biomedical research laboratories specially those working with equipment for cell cultures and vaccine production also make use of the gamma sterilization. Animal feed and shavings used by certified bioteries are routinely disinfected. Alternative underwater irradiation methods were developed to meet the demand of gemstone color enhancement. Human tissues including bone, skin, amniotic membranes, tendons, and cartilage belonging to National Banks are usually irradiated too. Different kind of polymers, hydrogels, foods as well native fruits, have been irradiated in this facility. Cultural heritage objects as books, paintings and furniture are disinfected routinely by gamma radiation. The success of the implementation of radiation processing in this facility is due to research and development of irradiation and dosimetry methods suitable for each condition. In this work are presented some considerations about the distribution dose and the two-faces stationary irradiation method developed and validated for this facility. (author)

  9. Methodology of ABNT ISO/IEC GUIA 25 implantation in the laboratories of radionuclides analysis in environmental samples of the Analysis Division/CNEN

    International Nuclear Information System (INIS)

    Oliveira, Josue Peter de

    1997-07-01

    The ISO/EEC Guide 25: 1993 Standard G eneral requirements for the competence of calibration and testing laboratories . Is published in Brazil by Brazilian Association for Technical Standards (ABNT) as ABNT ISO/DEC GUIA 25 and establishes general requirements a laboratory must demonstrate to meet, in order to be recognized as having technical competence (accreditation) to carry out specifics calibration or testing. Therefore, the accredited laboratory starts, respectively, taking part from the Brazilian Calibration Network (RBC) or from the Brazilian Testing Laboratories Network (RBLE) . The Environmental Radioanalysis Division (DIAMB) from Environmental Radiological Protection Department (DEPRA) from Institute of Radiation Protection and Dosimetry (IRD) from Brazilian National Nuclear Energy Commission (CNEN) is a laboratory responsible for analyzing radionuclides deriving for the samples from DEPRA's Surveillance Program, research and servings, due to an eventual radionuclide contamination in environment, foods and others raw materials for human consumption; including for importation and exportation products certification purposes. For all these reasons, DIAMB needs its formal recognition for carrying out radionuclides analysis in environmental samples. This work aims to provide a methodology in order to guide a laboratory which has the intention to implement a accreditation process. It also describes policies to meet the requirements related to the Standard, guidance needed to specification of some steps and also comments some points from the Standard in order to become easier all the accreditation process comprehension. (author)

  10. A new {sup 124}Xe irradiation system for {sup 123}I routine production at the 30 MeV IPEN-CNEN/SP cyclotron

    Energy Technology Data Exchange (ETDEWEB)

    Lapolli, André L.; Barcellos, Henrique; Matsuda, Hylton; Sumiya, Luiz C. do A.; Junqueira, Fernando de C., E-mail: alapolli@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2017-11-01

    Since 2001 the Nuclear and Energy Research Institute (IPEN/CNEN-SP, Brazil) has produced about 2.5 mCi/μAh of {sup 123}I weekly using a manual irradiation system fully developed by its researchers. Ultrapure {sup 123}I has been produced and distributed to hospitals and clinics where several diagnostic imaging procedures are done for thyroid, brain and cardiovascular functions. Due to the short half-life and emission of low-energy photons, this radioisotope becomes suitable for diagnosis in children. Currently IPEN researchers are involved in the development of a new fully automated irradiation system dedicated to {sup 123}I routine production employing enriched xenon gas ({sup 124}Xe) as the target material. This new system consists of a target port, a water and a helium cooling system, a cryogenic system, an electric power system, a control and process monitoring unit composed of a supervisory software connected to a Programmable Logic Controller (PLC) via personal computer. In this new concept, there is no need for human interference during radioisotope production, reducing the possibility of eventual failures or incidents involving radioactive material. In this way, with this new system, a specific yield of approximately 3.5 mCi/μAh per irradiation is expected and this will meet a large part of the national demand for this important radioisotope. In the present work will be presented all the technical and constructive aspects of this new system as well as the results obtained in the irradiation of tests. (author)

  11. Quality control studies of 99Mo used in 99Mo/99mTc generators produced at IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Said, Daphne S.; Brambilla, Tania P.; Matsuda, Margareth M.N.; Osso Junior, Joao A.

    2015-01-01

    99m Tc is the most used radionuclide in nuclear medicine. In Brazil, the 99 Mo/ 99m Tc generators are produced exclusively by the Center of Radiopharmacy at IPEN-CNEN/SP, by importing 99 Mo from different suppliers. 99 Mo (t 1/2 = 66 h) is a fission product of 235 U, therefore, it can be accompanied by several radioisotopes that are highly prejudicial for human health, demanding a strict quality control of this product for generators safe use. The European Pharmacopoeia established some parameters and limits that evaluate the quality of the solution of sodium [ 99 Mo]molybdate, that is used as raw material for generator's production. The European Pharmacopoeia also recommends some analytical methods to perform these evaluations, however, it has been observed difficulties on the implementation of these methods by the generator's producers. These difficulties are probably related to the lack of practicability of the proposed methods and the extensive list of utilized reagents. In this work some procedures of the European Pharmacopoeia's quality control method for 99 Mo were evaluated. Different types of solid phase exchanger cartridges were tested for retention of 99 Mo in 3 different conditions. Cartridges that presented percentages of retention higher than 90% were also tested for separation of 99 Mo from possible contaminants (Ru e Te). The results shown that solid phase exchanger cartridges that presented percentages of retention of Mo higher than 90% also presented significant percentages of retention of Ru and Te. An alternative method for separation of 99 Mo from 131 I (other contaminant) are also proposed. (author)

  12. Quality control studies of {sup 99}Mo used in {sup 99}Mo/{sup 99m}Tc generators produced at IPEN/CNEN-SP, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Said, Daphne S.; Brambilla, Tania P.; Matsuda, Margareth M.N.; Osso Junior, Joao A., E-mail: daphnesaid@usp.br, E-mail: taniabrambilla@yahoo.com.br, E-mail: mmatsuda@ipen.br, E-mail: jaosso@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    {sup 99m}Tc is the most used radionuclide in nuclear medicine. In Brazil, the {sup 99}Mo/{sup 99m}Tc generators are produced exclusively by the Center of Radiopharmacy at IPEN-CNEN/SP, by importing {sup 99}Mo from different suppliers. {sup 99}Mo (t{sub 1/2} = 66 h) is a fission product of {sup 235}U, therefore, it can be accompanied by several radioisotopes that are highly prejudicial for human health, demanding a strict quality control of this product for generators safe use. The European Pharmacopoeia established some parameters and limits that evaluate the quality of the solution of sodium [{sup 99}Mo]molybdate, that is used as raw material for generator's production. The European Pharmacopoeia also recommends some analytical methods to perform these evaluations, however, it has been observed difficulties on the implementation of these methods by the generator's producers. These difficulties are probably related to the lack of practicability of the proposed methods and the extensive list of utilized reagents. In this work some procedures of the European Pharmacopoeia's quality control method for {sup 99}Mo were evaluated. Different types of solid phase exchanger cartridges were tested for retention of {sup 99}Mo in 3 different conditions. Cartridges that presented percentages of retention higher than 90% were also tested for separation of {sup 99}Mo from possible contaminants (Ru e Te). The results shown that solid phase exchanger cartridges that presented percentages of retention of Mo higher than 90% also presented significant percentages of retention of Ru and Te. An alternative method for separation of {sup 99}Mo from {sup 131}I (other contaminant) are also proposed. (author)

  13. Implementation of 'Davies and Gray/NBL Method' for potentiometric titration of uranium in the Safeguards Laboratory of CNEN by the use of a DL-67 mettler titrator

    International Nuclear Information System (INIS)

    Araujo, Radier Mario Silveira de; Barros, Pedro Dionisio de

    2005-01-01

    To meet the requirements of the Brazilian State System of Accounting for and Control of Nuclear Materials - SSAC, the Safeguards Laboratory of CNEN - LASAL has been applying the 'Davies and Gray/NBL' method for potentiometric determination of total uranium concentration in uranium samples taken during safeguards inspections at nuclear facilities since 1984, using a Radiometer ETS 822 titrator. In order to improve the analytical capability and the procedures related to the titration methodology, the same method was also implemented by using a METTLER DL - 67 titrator. This equipment is microprocessor - controlled and can be connected to additional devices such as printers, analytical balances, etc. It also provides accurate and reproducible results for end-point titrations, providing analytical performance according to the current international safeguards requirements. The implementation of the method in such equipment included the addition of analytical data as well as the improvement of the equipment parameters for uranium determination. Parameters like predispensing volume; titrant data and end-point value were studied. Some uranium samples (solids and solutions) were used during the initial tests with the titrator. A solution of pure uranyl nitrate was used as reference sample for this paper. From this, aliquots were analyzed in both Radiometer ETS-822 and METTLER DL-67. Results obtained from each equipment were compared with the reference value of the sample. The comparison showed that results from METTLER DL-67 meets the precision and accuracy requirements for this kind of analysis and led to the conclusion that the performance of this titrator is adequate for the determination of total uranium content in samples of nuclear materials for safeguards purposes. (author)

  14. A new "1"2"4Xe irradiation system for "1"2"3I routine production at the 30 MeV IPEN-CNEN/SP cyclotron

    International Nuclear Information System (INIS)

    Lapolli, André L.; Barcellos, Henrique; Matsuda, Hylton; Sumiya, Luiz C. do A.; Junqueira, Fernando de C.

    2017-01-01

    Since 2001 the Nuclear and Energy Research Institute (IPEN/CNEN-SP, Brazil) has produced about 2.5 mCi/μAh of "1"2"3I weekly using a manual irradiation system fully developed by its researchers. Ultrapure "1"2"3I has been produced and distributed to hospitals and clinics where several diagnostic imaging procedures are done for thyroid, brain and cardiovascular functions. Due to the short half-life and emission of low-energy photons, this radioisotope becomes suitable for diagnosis in children. Currently IPEN researchers are involved in the development of a new fully automated irradiation system dedicated to "1"2"3I routine production employing enriched xenon gas ("1"2"4Xe) as the target material. This new system consists of a target port, a water and a helium cooling system, a cryogenic system, an electric power system, a control and process monitoring unit composed of a supervisory software connected to a Programmable Logic Controller (PLC) via personal computer. In this new concept, there is no need for human interference during radioisotope production, reducing the possibility of eventual failures or incidents involving radioactive material. In this way, with this new system, a specific yield of approximately 3.5 mCi/μAh per irradiation is expected and this will meet a large part of the national demand for this important radioisotope. In the present work will be presented all the technical and constructive aspects of this new system as well as the results obtained in the irradiation of tests. (author)

  15. Implantation of tomography qualities in Centro Regional de Ciencias Nucleares do Nordeste, Brazil; Implantacao das qualidades de tomografia no Centro Regional de Ciencias Nucleares do Nordeste, CNEN-PE, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Diniz, Osana F.; Silveira, Renata R.; Melo, Roberto T.; Oliveira, Marcia L., E-mail: osana.diniz@hotmail.com [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PB (Brazil)

    2016-07-01

    The quality guarantee of the service offered by a ionizing radiation metrology laboratory is deeply connected to the conformity to the radiation beams implanted to the determination and definition present in the international standards and adopted by the Brazilian National Commission of Nuclear Energy – CNEN. The objective of this work was the implementation of computerized tomography qualities, RQT 8, 9 e 10, in accordance with the IEC-61267 standard in the Metrology Laboratory of the Northeast Regional Center of Nuclear Sciences (CRCN-NE), PE, Brazil. (author)

  16. Decommissioning of uranium pilot plants at IPEN-CNEN/SP: Facilities dismantling, decontamination and reuse as new laboratories for strategic programs

    International Nuclear Information System (INIS)

    Oliveira Lainetti, P.; Freitas, A.; Cotrim, M.; Pires, M.

    2014-01-01

    Radical changes of the Brazilian nuclear policy, in the beginning of 1990s, determined the interruption of most nuclear fuel cycle activities and the facilities shutdown at IPEN. Those facilities had already played their roles of technological development and personnel's training, with transfer of the technology for institutions entrusted of the ''scale up'' of the units. Most of the pilot plants interrupted the activities more than ten years ago, due to the lack of resources for the continuity of the research. The appropriate facilities maintenance had been also harmed by the lack of resources, with evident signs of deterioration in structures and equipment. The existence of those facilities also implicated in the need of constant surveillance, representing additional obligations, costs and problems. It should be emphasized that one of the most concerning aspects, with relationship to the future of the facilities and the postponement of the dismantling, was the loss of the experience accumulated by the personnel that set up and operated the referred units. Besides the mentioned aspects, other reasons to promote the dismantling of the IPEN´s Nuclear Fuel Cycle Pilot Plants elapsed mainly from the need of physical space for new activities, since the R in the nuclear fuel cycle area were interrupted. In the last decade IPEN has changed its “nuclear profile” to a “comprehensive and multidisciplinary profile”. During this period, IPEN has been restructured in 13 Research Centers. With the end of most nuclear fuel cycle activities, the former facilities were distributed in four different centers: Environmental and Chemical Technology Center; Fuel Cell Center; Materials Science and Engineering Center; Nuclear Fuel Center. Each center has adopted a different strategy and priority to face the R problem and to reintegrate the areas. The resources available depend on the specific program developed in each area (resources available from other sources, not only CNEN

  17. Methodological study for management of the generated effluents during MTR-type fuel elements fabrication at IPEN/CNEN-SP plant

    International Nuclear Information System (INIS)

    Tanzillo Santos, Glaucia Regina

    2008-01-01

    CCN/IPEN-CNEN more efficiency concerning financial and environmental aspects. This work will surely contribute to the sustainability of our enterprise, assuring the growth of CCN in economically viable, socially fair and environmental responsible way. (author)

  18. Surface decontamination in the old storage shed number 99 of the General Plan of IPEN/CNEN-SP, containing production equipment of natural uranium hexafluoride (UF6), aiming at its decommissioning

    International Nuclear Information System (INIS)

    Almeida, Claudio C. de; Cambises, Paulo B.S.; Paiva, Julio E. de; Paiva, Julio E. de; Silva, Teresina M.; Rodrigues, Demerval L.

    2013-01-01

    This paper presents the steps adopted in the operation planned for the decontamination of surfaces in the old storage shed number 99 the general layout of the Energy Research and Nuclear IPEN-CNEN/SP, Brazil, and contained various types of equipment originating from production hexafluoride natural uranium (UF6). This operation involved the planning, training of operators of the facility, analysis of workplaces and radiometric surveys for monitoring of external radiation and surface contamination. The training involved the procedures for decontamination of surfaces, segregation of materials and practical procedures for individual monitoring of contamination outside of the body. Were also established rules for the transport of radioactive materials in the internal and external facility and release of material and sites already decontaminated

  19. Surface decontamination in the old storage shed number 99 of the General Plan of IPEN/CNEN-SP, containing production equipment of natural uranium hexafluoride (UF{sub 6}), aiming at its decommissioning; Descontaminacao de superficies no antigo galpao de estocagem numero 99 da planta geral do IPEN/CNEN-SP, contendo equipamentos da producao de hexafluoreto de uranio natural, (UF{sub 6}), visando seu descomissionamento

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Claudio C. de; Cambises, Paulo B.S.; Paiva, Julio E. de; Paiva, Julio E. de; Silva, Teresina M.; Rodrigues, Demerval L., E-mail: calmeida@ipen.br, E-mail: cambises@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    2013-11-01

    This paper presents the steps adopted in the operation planned for the decontamination of surfaces in the old storage shed number 99 the general layout of the Energy Research and Nuclear IPEN-CNEN/SP, Brazil, and contained various types of equipment originating from production hexafluoride natural uranium (UF6). This operation involved the planning, training of operators of the facility, analysis of workplaces and radiometric surveys for monitoring of external radiation and surface contamination. The training involved the procedures for decontamination of surfaces, segregation of materials and practical procedures for individual monitoring of contamination outside of the body. Were also established rules for the transport of radioactive materials in the internal and external facility and release of material and sites already decontaminated.

  20. CNEN activities and brazilian nuclear power policy

    International Nuclear Information System (INIS)

    Costa, E.M. da

    1989-01-01

    The goal of the brazilian policy in nuclear power is to provide its use in a pacific way to promote the well being of our people. It is intended, as well, to finish the construction of Angra II and III and proceed with the implementation of the nuclear fuel cycle, progressively fomenting its nationalization. (A.C.A.S.)

  1. Production and sharing of the nuclear knowledge: knowledge management at the Radiopharmaceutical Division of the Instituto de Engenharia Nuclear of Brazilian CNEN; Produção e compartilhamento do conhecimento nuclear: a gestão do conhecimento na Divisão de Radiofármacos do Instituto de Engenharia Nuclear da Comissão Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Bettencourt, Marcia Pires da Luz

    2011-07-01

    The Brazilian nuclear area made great progress in recent years, bringing many benefits to society, not only in producing electric power, but also in agriculture, industry and medicine. One of the problems in this area, nowadays, is the risk losing nuclear knowledge. Although it is difficult to understand how knowledge is created and used, can be seen that the sharing and production are influenced by some factors that provide favorable conditions. This research focused its attention on identifying actions that contribute to the production and sharing of knowledge and information at the Divisão de Radiofármacos of Instituto de Engenharia Nuclear of Comissão Nacional de Energia Nuclear (IEN/CNEN). Knowledge management was chosen as a tool to study the problem identified, because it has methodologies aimed at stimulating the knowledge production process and knowledge and information sharing, both in private companies and public institutions, such as IEN/CNEN. Knowledge management is an interdisciplinary relatively new discipline, and although it had not been born in Information Science, there has been seeking theoretical support and legitimacy at this interdisciplinary science. This research conceptualizes, historically contextualizes and analyzes developments and trends in knowledge management. The study discourses on the peculiarities and aspects in common between the knowledge management and information management and identifies factors that influence the sharing of information and knowledge such as: social networks, communities of practice, collaborative spaces, organizational culture, organizational learning, and storytelling. In reviewing the literature and after data analysis of interviews, some actions have been identified, and it was possible to make some suggestions. It is concluded that institutional incentive for collaboration and knowledge sharing can influence positive results and increase the production of new knowledge. (author)

  2. Neutron Spectrometry Work at the CNEN; La spectrometrie neutronique au CNEN; Raboty po nejtronnoj spektrometrii v nkyaeh; Trabajos de espectrometria neutronica realizados en el CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Caglioti, G; Ascarelli, P [Comitato Nazionale per L' energia Nucleare Euratom, G. C. R. Ispra, Varese (Italy)

    1963-01-15

    In this communication the main features of the triple axis spectrometer recently installed at the Ispra-1 reactor are presented. Preliminary results in the quasi elastic angular distribution of 1.4A neutrons scattered in liquid bromine are shown and briefly discussed. (author) [French] Dans ce memoire, l'auteur decrit les principales caracteristiques du spectrometre triaxial installe recemment au reacteur Ispra-1. Il donne et examine brievement les resultats preliminaires des experiences sur la distribution angulaire quasi elastique de neutrons de 1.4A a diffuses dans du brome liquide. (author) [Spanish] La memoria describe las principales caracteristicas del espectrometro triaxial recientemente instalado en el reactor lspra-1. Asimismo, expone brevemente los resultados iniciales de las determinaciones de distribucion angular de neutrones de 1,4 A dispersados en forma cuasi elastica por bromo liquido. (author)

  3. Evolutionary computing in Nuclear Engineering Institute/CNEN-Brazil

    International Nuclear Information System (INIS)

    Pereira, Claudio M.N.A.; Lapa, Celso M.F.; Lapa, Nelbia da Silva; Mol, Antonio C.

    2000-01-01

    This paper aims to discuss the importance of evolutionary computation (CE) for nuclear engineering and the development of this area in the Instituto de Engenharia Nuclear (IEN) at the last years. Are describe, briefly, the applications realized in this institute by the technical group of CE. For example: nuclear reactor core design optimization, preventive maintenance scheduling optimizing and nuclear reactor transient identifications. It is also shown a novel computational tool to implementation of genetic algorithm that was development in this institute and applied in those works. Some results were presents and the gains obtained with the evolutionary computation were discussing. (author)

  4. National Laboratory of Ionizing Radiation Metrology - Brazilian CNEN

    International Nuclear Information System (INIS)

    1992-01-01

    The activities of the Brazilian National Laboratory of Ionizing Radiations Metrology are described. They include research and development of metrological techniques and procedures, the calibration of area radiation monitors, clinical dosemeters and other instruments and the preparation and standardization of reference radioactive sources. 4 figs., 13 tabs

  5. Reactor instrumentation experience at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Soares, A.J.

    1997-01-01

    The Instituto de Pesquisas Energeticas e Nucleares (IPEN) in Sao Paulo started in 1977 development of nuclear instrumentation. In 1982 two groups were established, one responsible for maintenance of electronic equipment and the other, the Nuclear Instrumentation Section (NIS), for new projects, such as a light water moderated critical facility (IPEN/MB-0). The NIS had the responsibility to execute all necessary activities to develop the ''nonconventional'' instrumentation systems: control, protection and radiation monitoring for the IPEN/MB-01 facility. After the commissioning of the critical facility the NIS group started the development of instrumentation systems for a power reactor. As a first step an overall review of the quality assurance programme was implemented. In parallel the development of self powered detectors was carried out. (author). 7 figs

  6. National Laboratory of Ionizing Radiation Metrology - Brazilian CNEN; Laboratorio Nacional de Metrologia das Radiacoes Ionizantes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    The activities of the Brazilian National Laboratory of Ionizing Radiations Metrology are described. They include research and development of metrological techniques and procedures, the calibration of area radiation monitors, clinical dosemeters and other instruments and the preparation and standardization of reference radioactive sources. 4 figs., 13 tabs.

  7. Safeguards organizational system at Centro de Desenvolvimento da Tecnologia Nuclear/CNEN-Br

    International Nuclear Information System (INIS)

    Oliveira, Cleber Lopes de; Stasiulevicius, Roberto

    1996-01-01

    Since 1960, the CDTN is working according to a safeguards system, which has been updated in 1992, after the quadripartite agreement involving the government of Brazil and Argentina and the organizations IAEA and ABACC. In this work is presented the SS-CDTN and the acquired experience with the implantation of this system. (author)

  8. Mining adaptation to the radioprotection regulations: evaluation of the regulation CNEN-NN-4.01

    International Nuclear Information System (INIS)

    Pereira, Wagner de Souza; Kelecom, Alphonse; Silva, Cleber Jabarra da; Campinhos, Gabriela Michalsky

    2011-01-01

    This paper proposes a generic model of monitoring to be used in mining with uranium or thorium associated viewing to estimate the dose of workers for classification the mining in the specific question of worker exposure. Besides the monitoring model, a dosimetric model also is proposed. It is indicated some instruments and techniques used in individual and area monitoring, besides to point out the necessity of radioprotection supervisor specific in this area

  9. Individual performance evaluation of the Brazilian Nuclear Energy Commission (CNEN): a meta-evaluative study

    International Nuclear Information System (INIS)

    Bezerra, Leonardo Ferreira

    2017-01-01

    The present study is a summative meta-evaluation that had as objective to evaluate the quality of the process of evaluation of individual performance of the servers of the National Commission of Nuclear Energy, being guided by the scientific curiosity to know to what extent the evaluation of performance the National Commission for Nuclear Energy meets the quality standards disseminated by the Joint Committee on Standards for Educational Evaluation. The methodology chosen to be used was based on the management approach and had as a guiding principle of the study the elaboration of a framework of criteria considering the aforementioned standards. The criteria established in the criteria framework guided the preparation of the items of the questionnaire sent to the National Commission of Nuclear Energy servers. In addition to the questionnaire, the observation of this author was considered in the context where the phenomenon occurred, which allowed a better reflective analysis of the data collected by the questionnaire. Regarding the results, it can be inferred that the performance evaluation developed at the National Commission of Nuclear Energy can be considered of quality, highlighting the servers' trust for the data, the communication process of the program stages, the credibility of the evaluators, the process of negotiation of goals and adaptability of the instrument over the course of the cycle. However, there are some opportunities for improvement, considering the relevance of evaluation as a tool to improve the performance of the autarchy's servers. Among the points that need to be improved is that there is currently a lack of knowledge about the legal basis and justification of the process of evaluation process by the servers and the lack of clarity regarding the content of the final evaluation report. Among the recommendations of this study, one can consider as the most relevant the need to: disseminate the results of this meta-evaluation to the servers; promotion of meetings to raise awareness of the importance of evaluation, explaining its legal basis, justifications; and qualification of the National Commission of Nuclear Energy people management area evaluators in order to pass them through specialization processes in the field of individual performance appraisal. (author)

  10. Characteristics of the natural uranium ingots developed in IPEN - CNEN/SP

    International Nuclear Information System (INIS)

    Soares, M.C.B.; Koshimizu, S.

    1990-01-01

    The natural uranium consists of two primary isotopes, the U sup(235) (0,7%) and the U sup(238) (99,3%). The isotopic separation carried out in order to obtain enriched uranium, generates a by-product called depleted uranium, which can be applied for industrial uses. The most singular property, from engineering standpoint, is its high density. When the density is the only important factor, the uranium has great advantage over other heavy metals related to economic and technical considerations. Among some applications of uranium are aircraft and missile counterweights, kinetics energy penetrators, radiation shielding, gyro rotors and oil-well sinker bars. The uranium ingot fabrication is done by direct reduction of UF, with magnesium, without remelting. The microstructure of as-cast uranium is, as in the other as-cast, formed by coarse and. (author)

  11. Radiation protection in cyclotron and radioisotope production laboratories of IEN - (Instituto de Engenharia Nuclear - CNEN)

    International Nuclear Information System (INIS)

    Fajardo, P.W.; Silva, J.J.G.

    1988-01-01

    The Cyclotron at Instituto de Engenharia Nuclear is used for the radioisotope production, neutron production and irradiation damages analysis, etc. The risks associated with the operation and maintenance of cyclotron and the neutron radiation of wide energy spectrum, external and internal contamination. A summary of the radioprotection program for these areas are show and the results obtained from the air and surface analysis, liquid efluents and equivalentes doses of workers of the several activities are given. (Author) [pt

  12. Uranium recovery from waste of the nuclear fuel cycle plants at IPEN-CNEN/SP, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Freitas, Antonio A.; Ferreira, Joao C.; Zini, Josiane; Scapin, Marcos A.; Carvalho, Fatima Maria Sequeira de, E-mail: afreitas@ipen.b, E-mail: jcferrei@ipen.b, E-mail: jzini@ipen.b, E-mail: mascapin@ipen.b, E-mail: fatimamc@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Sodium diuranate (DUS) is a uranium concentrate produced in monazite industry with 80% typical average grade of U{sup 3}O{sup 8}, containing sodium, silicon, phosphorus, thorium and rare earths as main impurities. Purification of such concentrate was achieved at the nuclear fuel cycle pilot plants of uranium at IPEN by nitric dissolution and uranium extraction into an organic phase using TBP/Varsol, while the aqueous phase retains impurities and a small quantity of non extracted uranium; both can be recovered later by precipitation with sodium hydroxide. Then the residual sodium diuranate goes to a long term storage at a safeguards deposit currently reaching 20 tonnes. This work shows how uranium separation and purification from such bulk waste can be achieved by ion exchange chromatography, aiming at decreased volume and cost of storage, minimization of environmental impacts and reduction of occupational doses. Additionally, the resulting purified uranium can be reused in nuclear fuel cycle.(author)

  13. Subsonic Constant-Area MHD Generator Experiments with the CNEN Blow-Down Loop Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bertolini, E.; Gasparotto, M.; Gay, P.; Toschi, R. [Laboratorio Conversione Diretta, CNEN, Frascati (Italy)

    1968-11-15

    The design of the facility, described at the Salzburg Symposium, was somewhat modified following the results of the commissioning tests; the changes were mainly concerned with the thermal insulation, duct materials and caesium recovery system. The facility went into full operation in March 1967 and since then two series of MHD experiments, a total of twenty-six runs, have been performed. During the MHD runs the facility has been working mostly under the following operating conditions: stagnation temperature 1500 to 1800 Degree-Sign K; stagnation pressure-1 to 3 atm. abs.; mass How 50 to 150 g/sec; seeding 2 to 5 at.%- ; magnetic field 0 to 45 k G; Mach number 0.4 to 0.8; Hall parameter up to 6. The main purpose of the experiments was to study the performance of relatively small generators (cross-section 3 x 5 cm{sup 2}, length 8-20 cm) both when the non-equilibrium ionization is expected to be negligible and when it should be, in a very idealized model, relevant. As a first step, efforts were made to ascertain whether any of the unsatisfactory results reported in Salzburg, both for equilibrium and non-equilibrium generators, stemmed not from the basic functioning principle of an MHD small-scale generator but rather from some inadequacy of the experimental apparatus. Therefore particular attention was paid to: ceasium vaporization and mixing with helium; plasma insulation from ground; electrical insulation from ground and from each other of those electrically conductive parts of the facility which may, during the functioning, come into contact with the plasma; temperature control of the duct; purity level; duct materials; measurement system and control. In the equilibrium regime the Faraday field measured is very close to the ideal value and it reaches 80 V/cm (400 volts between electrodes); the Hall field still remains below the ideal value uB{beta}L (50% at {beta} = 3). The maximum Hall field was about 35 V/cm for a corresponding voltage of 600 V. Preionization may especially influence the Hall field, confirming the presence of some axial leakages; some artificial changes in the gound-loop resistance have shown experimentally how drastically the Hall field may be reduced if a less than very careful approach is taken to the problems of electrical insulation. Current densities of a few amperes per square centimetre at the electrodes were measured and the electrical power generated in the duct was of the order of few watts per cubic centimetre. (author)

  14. Implementation of a OSL dosimetry laboratory at IRD/CNEN-BR

    International Nuclear Information System (INIS)

    Moura, Jose; Alencar, Marcus A. Vallim de; Mauricio, Claudia L.P.; Hunt, John

    2005-01-01

    The optically stimulated luminescence (OSL) it is a phenomenon characterized by the luminous emission of an insulating material or semiconductor, during your exhibition to the light, after it being previously exposed to the ionizing radiation. This phenomenon has been used more and more in the dosimetry of the ionizing radiations, why the intensity OSL of some materials is proportional to the absorbed dose in these. The processes OSL and thermoluminescence (TL) they only differ in the stimulation form for light emission. One of the advantages of the OSL process in relation to the traditional technique of TL dosimetry is the no complete destruction of the information of the absorbed dose in the material during the reading. Following this world tendency, the External Individual Monitoring Service of the Institute of Radioprotection and Dosimetry (SEMEX/IRD) implemented the OSL dosimetry laboratory. The acquired reader was the reader model LAUGHTER TL/OSL-GIVE-15B/C. With that reader it is possible to do readings TL and OSL. After the installation of the equipment in a darkroom with temperature and humidity controlled, they were made the preliminary tests with the equipment and the laboratory became operational. After this first stage, they were initiate the studies with the Al 2 O 3 :C dosimeters by Harshaw under the denomination TLD 500. The reading parameters and thermal treatment were optimized to study the applicability of OSL technique with the TLD 500 dosimeter for the use in environmental monitoring. It was also verified the linearity of the system for high doses (10 mGy-1 Gy) seeking your use in radiotherapy, as well as the effect of the thermal treatment in the OSL signal of the Al 2 O 3 :C dosimeter. The results prove the possibility of use of this system in environmental monitoring. The reproductivity of the system for the air kerma value of 100 mGy, considering a degree of confidence of 95%, was to 4,8% for OSL readings and 5,6% for TL. In the two cases, the minimum value detectable of the air kerma dose was to 5 mGy. The system comes linear for a air kerma in the interval of 10-500 mGy and the influence of the thermal treatment in the OSL signal for a air kerma dose inferior to 1 Gy was of approximately 3,7%. (author)

  15. National Laboratory of Ionizing Radiation Metrology - Brazilian CNEN; Laboratorio Nacional de Metrologia das Radiacoes Ionizantes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-31

    The activities of the Brazilian National Laboratory of Ionizing Radiations Metrology are described. They include research and development of metrological techniques and procedures, the calibration of area radiation monitors, clinical dosemeters and other instruments and the preparation and standardization of reference radioactive sources. 4 figs., 13 tabs.

  16. Temporal comportment assessment of metals in groundwater on the campus at IPEN/CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Faustino, Mainara G.; Monteiro, Lucilena R.; Stellato, Thamiris B.; Soares, Sabrina M.V.; Silva, Tatiane B.S.C.; Silva, Douglas B. da; Marques, Joyce R.; Pires, Maria A.F.; Cotrim, Marycel E.B., E-mail: mainarag@usp.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    Since 2006, Nuclear and Energy Research Institute (IPEN) performs yearly the Environmental Monitoring Program of Stable Chemical Compounds (PMA-Q).Among other parameters, metals and semi metals in groundwater, collected at IPEN’s facility, are evaluated. The monitoring is conducted in nine wells, in attendance to the current Brazilian environmental legislation, which requires the monitoring of metals and semi metals in groundwater, in accordance with CETESB and CONAMA’s resolutions. CETESB is the Sao Paulo State environmental regulatory agency and CONAMA is the Environmental National Council, both agencies that regulate environmental standards in Brazil and regulate IPEN’s environmental activities. Besides these two environmental regulators, IPEN have to follow the request of the Term for the Adjustment of Conduct (TAC) from (IBAMA), in order to support programs to prevent and control pollution resulting from activities of IPEN’s facilities. In the current PMA-Q, Aluminum (Al) Antimony (Sb), Silver (Ag), Arsenic (As), Lead (Pb), Chromium (Cr), Cobalt (Co), Zinc (Zn), Boron (B), Barium (Ba), Calcium (Ca), Iron (Fe), Manganese (Mn), Mercury (Hg) and Nickel (Ni) are analyzed by using sensitive analytical techniques as inductively coupled plasma optical emission spectrometry (ICP-OES) and graphite furnace atomic absorption spectrometry (GF-AAS). These elements results are in this paper evaluated. Both internal and external quality controls that uses data from interlaboratory programs are discussed here. It was possible to conclude that IPEN’s groundwater attends national standards and IPEN’s monitoring system operates under controlled quality conditions. (author)

  17. Brazilian Institute for Radiation Protection and Dosimetry (IRD/CNEN-RJ): Report 2000-2010

    International Nuclear Information System (INIS)

    2010-01-01

    This report presents the activities of the Institute for Radiation Protection and Dosimetry of the Brazilian Nuclear Energy Commission from 2000 to 2010 and has eight chapters: 1) history; 2) main designations and attributions; 3) metrology and assays; 4) conformity evaluation; 5) assistance to radiological and nuclear emergencies; 6) capacity and training; 7) infrastructure of information technology and 8) operational indicators

  18. Certification of biological reference materials: participation of the Neutron Activation Laboratory (LAN-IPEN/CNEN-SP)

    International Nuclear Information System (INIS)

    Ticianelli, Regina B.; Figueiredo, Ana Maria G.

    2007-01-01

    Analytical laboratories have as one of their important goals to demonstrate their competence allowing international acceptance and comparison of analytical data. The IPEN Neutron Activation Laboratory (LAN-IPEN) has implemented its Quality Assurance Program which comprises, among other activities, the participation in intercomparison runs. As a part of this Quality Assurance Program, LAN-IPEN has participated in interlaboratorial trials to analyze two biological candidate reference materials: INCT-CF-3 Corn Flour and INCT-SBF-4 Soya Bean Flour from the Institute of Nuclear Chemistry And Technology (Warszawa, Poland). The elements Br, Ca, Co, Cs, Fe, K, Na, Rb and Zn were analyzed in the candidate reference materials by instrumental neutron activation analysis (INAA). The performance of the laboratory was statistically evaluated in relation to the consensus values for these materials using the Z-Score test. This laboratory evaluation method has been accepted as a standard by ISO/IUPAC. In the present study, adequate Z-Score values (|Z|<2) were observed for all of the analyzed elements, confirming the accuracy of the nuclear methodology employed. The contribution of LAN-IPEN in the certification of the reference materials analyzed was very important, since the results provided were used in the statistical evaluation of the certified value. (author)

  19. Activity report 1991 from IPEN - Brazilian Institute of Energy and Nuclear Researches, CNEN/SP

    International Nuclear Information System (INIS)

    1991-01-01

    This report presents the main events achieved at IPEN in 1991: actions related to international cooperation, developed administrative activities as well as the matched results in the areas of Fuel Cycle, Nuclear Reactors, Application of Nuclear Techniques, Radiation Protection and Logistic Support

  20. Utilization of the RELAP4 in the experimental water loop of the IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Sabundjian, G.

    1991-09-01

    For a better security of the nuclear power station and the population, thermal hydraulics codes for accident analysis were developed. Within all codes, the RELAP4, developed by Aerojet Nuclear Company of the Idaho Falls Engineering Laboratory (U.S.A.), has been the more used mostly by the fact of been available to the public. These code presents the most satisfactory results when used for various sort of problems. Basely the paper analyzes and compares the RELAP4/MOD3 and MOD5 versions, through the simulation on the Water Experimental Loop (C.E.A.) of the IPEN, in the steady state and in accidents conditions. Although the C.E.A. had been constructed to simulate PWR and BWR reactors, in these paper the tests were made only for PWR. Through the results analysis found in these paper, we concluded that the model adaptation for the simulations made with the RELAP4 code (version MOD3 and MOD5), were satisfactory. The accidents simulations indicates that the C.E.A. can support accident situation with the emergency system acting. Comparing the two versions, the MOD5 presented the better results compared with the real estimations. (author)

  1. Temporal comportment assessment of metals in groundwater on the campus at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Faustino, Mainara G.; Monteiro, Lucilena R.; Stellato, Thamiris B.; Soares, Sabrina M.V.; Silva, Tatiane B.S.C.; Silva, Douglas B. da; Marques, Joyce R.; Pires, Maria A.F.; Cotrim, Marycel E.B.

    2015-01-01

    Since 2006, Nuclear and Energy Research Institute (IPEN) performs yearly the Environmental Monitoring Program of Stable Chemical Compounds (PMA-Q).Among other parameters, metals and semi metals in groundwater, collected at IPEN’s facility, are evaluated. The monitoring is conducted in nine wells, in attendance to the current Brazilian environmental legislation, which requires the monitoring of metals and semi metals in groundwater, in accordance with CETESB and CONAMA’s resolutions. CETESB is the Sao Paulo State environmental regulatory agency and CONAMA is the Environmental National Council, both agencies that regulate environmental standards in Brazil and regulate IPEN’s environmental activities. Besides these two environmental regulators, IPEN have to follow the request of the Term for the Adjustment of Conduct (TAC) from (IBAMA), in order to support programs to prevent and control pollution resulting from activities of IPEN’s facilities. In the current PMA-Q, Aluminum (Al) Antimony (Sb), Silver (Ag), Arsenic (As), Lead (Pb), Chromium (Cr), Cobalt (Co), Zinc (Zn), Boron (B), Barium (Ba), Calcium (Ca), Iron (Fe), Manganese (Mn), Mercury (Hg) and Nickel (Ni) are analyzed by using sensitive analytical techniques as inductively coupled plasma optical emission spectrometry (ICP-OES) and graphite furnace atomic absorption spectrometry (GF-AAS). These elements results are in this paper evaluated. Both internal and external quality controls that uses data from interlaboratory programs are discussed here. It was possible to conclude that IPEN’s groundwater attends national standards and IPEN’s monitoring system operates under controlled quality conditions. (author)

  2. Assessment of Radioactive Liquid Effluents Release at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Bessa Nisti, Marcelo; Godoy dos Santos, Adir Janete

    2008-01-01

    A continuous effluent monitoring program has been established at IPEN's plant in order to allow an environmental impact assessment due to radioactive liquid effluent discharge to sanitary system. Representative samples of radioactive liquid effluents are analyzed by using high resolution gamma spectroscopy and instrumental neutron activation analysis, facing to Brazilian radioprotection regulatory rules. The results are consolidating yearly in the Institute source-term. In this paper, results of the source-term are presented, concerning to years 2004, 2005 and 2006. The total activity discharged was 8.5xl0 8 Bq, 5.7x10 8 Bq and 2.7xl0 8 Bq, respectively. As the release is strongly dependent on the total amount of the effluent and on the dilution factor, special attention is needed in order to obtain the correct value of that last one. The estimated inside plant dilution factor, considering the recent facilities and the reshaping of the sewerage system was 80, 180 and 130, for period of 2004, 2005 and 2006 discharged liquid radioactive effluent

  3. Study of groundwater collection protocols on the IPEN/CNEN-SP campus

    International Nuclear Information System (INIS)

    Marques, Joyce R.; Villa, Sabrina M.; Monteiro, Lucilena R.; Cotrim, Marycel E.B.; Pires, Maria Aparecida F.

    2013-01-01

    As per Brazilian Health Ministry's evaluation, industry is the second activity that most contaminates the soil in Sao Paulo Metropolitan region. In order to assess this scenario and keep a continuous logging of IPEN's installations effect over chemical compounds levels, and to improve the installation radioactive logging, in the region under its campus influence, since 2006, IPEN performs the groundwater monitoring, in the region where it is located. Collections are performed bimonthly in seven monitoring wells, evaluating 17 parameters. These values are compared to the ones established by CONAMA 396/08 Resolution, which provides the groundwater classification and environmental guidelines to chemically stable compounds. So far IPEN keeps the wells in good conditions and performs sampling methods studies to adequate it to current legal standards. The groundwater collection method and the wells characterization, concerning the anionic species content (F - , Cl - , Br - , NO 2 - , NO 3 - , PO 4 -3 e SO 4 -2 ), are evaluated in the present study. The purge procedure requirement was also evaluated. The well purging is the procedure for withdrawing water from inside the well, so the collection is performed only after the water level restoration, thereby ensuring that the water collected represents the aquifer. The use of 'bailer', which requires purging, and a called 'low flow pump', which requires no purging for sample collection, was also evaluated. These methods were selected in this study because they are recommended by CETESB 6410/88, the local standard to groundwater sample collection. Thus some anions concentrations in groundwater sampled with different purging procedures and collection were compared. The concentration change in each well performed with the same collection procedure was compared with the other collection methods variation in order to evaluate if these are equivalents. From the results obtained in this comparative study was possible to optimize the collect methods, shaping changes in sampling protocol, with neither invalidate nor lose the historic program data. (author)

  4. The Brazilian National Intercomparison Program (PNI/IRD/CNEN): evaluation of 15 years of data

    International Nuclear Information System (INIS)

    Tauhata, Luiz; Vianna, Maria Elizabeth Couto M.; Oliveira, Antonio Eduardo de; Ferreira, Ana Cristina; Braganca, Maura Julia C.; Clain, Almir Faria; Quelvia de Faria, Rute

    2006-01-01

    The Instituto de Radioprotecao e Dosimetria has been coordinating the National Intercomparison Program (PNI) for 15 years, from 1991 to 2005. The objective is to evaluate the analytical performance of the laboratories in low-level activity concentration radionuclide assays in environmental samples. This work presents an evaluation of PNI data from 42 intercomparison runs, which distributed to 22 Brazilian laboratories 2511 samples evaluating 5768 radionuclide assays involving 32 radionuclides in the period from 1991 to 2004. The laboratory performance was evaluated using the Normalized Standard Deviation used by the U.S. EPA. For comparison aims, the Normalized Deviation, used by BIPM was also applied. Laboratory performance were grouped and evaluated in three periods of 5 years each. The first period shows, an average value of good performance of 71.2%, the second shows an average of 78.6% and the last an average of 82.3%. Performance for each kind of radionuclide is also presented

  5. Historical and perspectives of thorium compounds production and purification at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Lainetti, Paulo E.O.; Abrao, A.; Freitas, Antonio A.; Carvalho, Fatima M.S. de; Bergamaschi, Vanderlei S.; Cunha, Edgar F.; Ayoub, Jamil M.S.; Mindrisz, Ana C.

    2000-01-01

    The production and purification of some thorium compounds has been performed in the IPEN in the last 15 years. Some raw materials have been employed in this production, obtained from the monazite exploitation in industrial scale that it was performed in Sao paulo during the period 1948 until 1994. More than 160 t of high purity thorium nitrate were produced, purified by the solvent extraction process. The thorium nitrate has been supplied for the Brazilian portable gaslight industry to the production of Welsbach Mantle. Nowadays, a new facility is being designed and built. The main concern is the recovering of the production capacity, lost after some years of operation without suitable maintenance. This activity has an important strategic role, considering the huge Brazilian thorium resources and the renewed interest in thorium fuel cycle. This paper describes a brief historical background of thorium activities in the IPEN as well as their perspectives. (author)

  6. Activities of the IPEN laboratory (CNEN/SP - Brazil) of nuclear metrology

    International Nuclear Information System (INIS)

    Dias, M.S.; Koskinas, M.F.; Pocobi, E.; Silva, C.A.M.; Machado, R.R.

    1987-01-01

    The determination of radionuclide activity for radioactive sources and standardized solutions is reported as the main purpose of the IPEN laboratory of nuclear metrology. The measurement systems installed in the laboratory, the measurable activity intervals and some of the standardized radionuclides (emphasizing the ones used in nuclear medicine) are presented. (M.A.C.) [pt

  7. Radiotoxicology analysis in Nuclear and Energetic Research Institute (IPEN-CNEN/SP)

    International Nuclear Information System (INIS)

    Duarte, C.L.; Gaburo, J.C.; Bellintani, S.A.

    1987-01-01

    The radiotoxicology laboratory of Nuclear and Energetic Research Institute (IPEN) has the objective of control the internal contamination of workers that handle radioactive materials, in industrial and medical sectors. This control is made through radiochemical analysis of excreta. Nowadays in this laboratory are realized occupational controls on individual, exposure to uranium, tritium, iodine, fluorine, lead compounds, for workers of IPEN and for external institutions, when solicited. (C.G.C.) [pt

  8. Neutron spectrum survey around the cyclotron of IEN/Brazilian CNEN: calibration of neutron personnel dosemeter

    International Nuclear Information System (INIS)

    Fajardo, P.W.

    1991-01-01

    The albedo neutron dosimeter is calibrated directly at the work place due to its high energy dependence. This thesis deals with the study, analysis and application of neutron measurement techniques in order to obtain information about the neutron spectrum and neutron dose equivalent at several representative working places of the cyclotron laboratory of the Nuclear Engineering Institute (IEN). These data are employed mainly in the calibration of the brazilian albedo neutron dosimeter. Bonner spheres and foil activation were used in neutron spectra measurements and the neutron dose equivalents were measured with the single sphere albedo technique. BF 3 and 3 He proportional detectors and 6 LiI scintillation detector were also used in these measurements. The single sphere technique turned out to be more appropriate for neutron dosimetry for calibrating the albedo dosimeter in the varying fields of the cyclotron. Calibration the albedo dosimeter in the varying fields of the cyclotron. Calibration factors were found for routine applications, when the workers are protected by shielding and for radiological accident applications, in the case that a worker is exposed inside the cyclotron room. In all situations the performance of the brazilian albedo dosimeter is compared with that of the german albedo dosimeters. (author)

  9. Study of the radioactive impurities gamma emitters present in the radiopharmaceutical solutions produced at IPEN/CNEN-SP; Estudo das impurezas radioativas gama emissoras presentes nos radiofarmacos produzidos no IPEN-CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Jamille da Silveira

    2017-11-01

    This work aims to investigate the concentration of radioactive impurities gamma emitters in the radiopharmaceutical solutions produced at Nuclear and Energy Research Institute -IPEN in Sao Paulo, So that this radiopharmaceutical may be used properly, its quality should be evaluated in accordance with the procedures established by quality control agencies, such as General Requirements for the Competence of Testing and Calibration Laboratories' ISO/IEC 17025:2005 and the 'Good Laboratory Practice (GLP), controlled by ANVISA (National Agency Health Surveillance), in Brazil, requiring a confirmation of the values of impurities related at the certificates supplied by the manufacturers. To determine the activity, a high resolution gamma spectrometer were used in two source-detector distances. One was 18 cm and the other 1.7 cm. For the 18 cm distance, the high pure germanium spectrometer was calibrated in the energy range between 81 keV and 1408 keV by measuring sealed ampoules of {sup 60}Co, {sup 133}Ba, {sup 137}Cs and {sup 152}Eu, standardized at the Nuclear Metrology Laboratory (NML) of IPEN. For lower activity of the impurities, the distance source-detector of 1.7 cm was assumed. However, as at this distance, the sum coincidence effect is very high, making the measurement of the standard calibration ampoules difficult, the spectrometer efficiency curve was obtained by a Monte Carlo simulation code, developed at IPEN. In this code, all details of the detection system are modeled and the response curves for x-rays and gamma rays are calculated by the MCNPX radiation transport code. The gamma spectra were analyzed by Alpino code, which applies the method of numeric peak integration of the area under the photopeaks. For gamma emitter impurities, not visually detected, the decision threshold and the detection limits were calculated from the background count rate, under the peak area. The radiopharmaceutical solutions analyzed were {sup 67}Ga, {sup 99}Mo, {sup 99m}Tc, {sup 111}In, {sup 131}I, {sup 153}Sm, {sup 177}Lu and {sup 201}Tl. The results of impurities ratio for analyzed solutions are in accordance with the manufacturers' certificate and with the ANVISA. (author)

  10. A model for environmental scanning oriented for the strategic planning of the Brazilian Nuclear Energy Commission (CNEN); Um modelo de monitoramento ambiental (environmental scanning) orientado para o planejamento estrategico da CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Braga, Fabiane dos Reis

    1997-07-01

    Presently, all the organizations involved with nuclear activities must be one step ahead of what happens in the specific activity areas in order to avoid surprises, to guarantee their activity continuity and the objective extents, and taking into account the external environment influence exercised by the organization on their activities. So, it is necessary a continuous follow up of their transformations. This paper aims to structure a model of the environmental monitoring system oriented to the strategic planning of the Brazilian Nuclear Energy Commission, as function of that new informational needs viewing the fulfilment of that observed gap. (author)

  11. Mining adaptation to the radioprotection regulations: evaluation of the regulation CNEN-NN-4.01; Adaptacao da mineracao as normas de radioprotecao: avaliacao da Norma CNEN-NN-4.01

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Wagner de Souza; Kelecom, Alphonse [Universidade Federal Fluminense (LARARA/UFF), Niteroi, RJ (Brazil). Lab. de Radiobiologia e Radiometria; Silva, Cleber Jabarra da; Campinhos, Gabriela Michalsky [Jabarra Servicos e Comercio de Radioprotecao Ltda., Rio de Janeiro, RJ (Brazil). Consultoria em Radioprotecao

    2011-10-26

    This paper proposes a generic model of monitoring to be used in mining with uranium or thorium associated viewing to estimate the dose of workers for classification the mining in the specific question of worker exposure. Besides the monitoring model, a dosimetric model also is proposed. It is indicated some instruments and techniques used in individual and area monitoring, besides to point out the necessity of radioprotection supervisor specific in this area

  12. Study of social responsibility of the Nuclear and Energy Research Institute of Sao Paulo (IPEN/CNEN-SP); Estudo da responsabilidade social do Instituto de Pesquisas Energeticas e Nucleares de Sao Paulo (IPEN/CNEN-SP)

    Energy Technology Data Exchange (ETDEWEB)

    Mutarelli, Rita de Cassia

    2014-07-01

    Over the years, the socio-environmental concept has grown through programs, conferences and several activities that have been held in Brazil and worldwide. Sustainability and social responsibility are now an integral part of everyday life of organizations The Instituto de Pesquisas Energeticas e Nucleares (IPEN), which is the focus of this research, is committed to the improvement of Brazilian quality of life. Based on IPEN's mission, and due to the lack of tools for assessing socio-environmental actions, this research aims to propose an assessment tool for social responsibility, which may also be a methodological resource committed to the improvement of the Institute. Through indicators and dimensions, a methodology to assess social responsibility and identify both strengths and weaknesses was designed. The methodology was administered to IPEN, and the results demonstrated positive aspects regarding actions towards the internal publics and negative aspects towards the external publics that require improvement. The results obtained were satisfactory. Nevertheless, as the subject of this study is a broad theme, further studies are suggested. IPEN's board may use the results of this research as a tool to help them identify feasible socio-environmental actions to be implemented in the institute. (author)

  13. Activity report 1991 from IPEN - Brazilian Institute of Energy and Nuclear Researches, CNEN/SP; Relatorio de Atividades 1991 IPEN - Institutos de Pesquisas Energeticas e Nucleares, CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-07-01

    This report presents the main events achieved at IPEN in 1991: actions related to international cooperation, developed administrative activities as well as the matched results in the areas of Fuel Cycle, Nuclear Reactors, Application of Nuclear Techniques, Radiation Protection and Logistic Support.

  14. Participation of the IPEN/CNEN/SP Environmental Diagnostic Division on programs of laboratory intercomparisons in environmental samples; Participacao da Divisao de Diagnostico Ambiental do IPEN/CNEN/SP em programas de intercomparacao laboratoriais em amostras ambientais

    Energy Technology Data Exchange (ETDEWEB)

    Cotrim, Marycel Barboza; Sato, Ivone Mulako; Salvador, Vera Lucia R.; Dantas, Elizabeth Sonoda Keiko; Cantagallo, Maria Ines; Lemes, Marcos Jose L.; Scapin, Marcos Antonio; Sisti, Cristina; Silveira, Elias Santana; Furusawa, Helio Akira; Pires, Maria Aparecida Faustino [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: mecotrim@ipen.br, e-mail: imsato@ipen.br, e-mail: vsalvado@ipen.br, e-mail: esdantas@ipen.br, e-mail: cantagal@ipen.br, e-mail: mjllemes@ipen.br, e-mail: helioaf@ipen.br, e-mail: mapires@ipen.br

    2003-07-01

    The present work presents the participation of the Environmental Diagnostic Division Laboratories (MQA) at the intercomparison national and international laboratories, (PI/SABESP - Interlaboratory Sao Paulo, Brazil, Program; Program for Interlaboratorial Analytic Quality Control of Metals in Water (CBM/COMETRO); Programa para La Calidad de las Mediciones Quimicas (PCQM/INTI) - Argentine, and the Commission d'Etablissement des Methodes d'Analyse, France (CETAMA/CEA). Those essay providers have using statistical tests such as the t-Student, Zscore and Cochran and Grubbs for the data evaluations. The obtained results are presented involving the analytical such as atomic absorption spectrometry: flame, graphite oven and hydride generation (AAS), emission spectrometry with induced plasma (ICP-OES), X-ray fluorescence WD-XRFS), ion chromatography and voltametry (VRA). The elements such as B, Al, K, Mg, Ca, Cr, Fe, Co, Cu, Zn and Pb, and the anions such as Cl-, NO{sub 3}{sup -}, SO{sub 4}{sup 2-} and F{sup -}, were determined at trace level (mgL{sup -1}), and the elements such as Cr, As, Cd, Pb e Hg, at the trace level ({mu}gL{sup -1}) in water matrices. The evaluation of analytical results, in the period 1997 to 2002, demonstrate a continuous improvement evidencing the importance of Laboratories participation at those type of exercises.

  15. A model for environmental scanning oriented for the strategic planning of the Brazilian Nuclear Energy Commission (CNEN)

    International Nuclear Information System (INIS)

    Braga, Fabiane dos Reis

    1997-01-01

    Presently, all the organizations involved with nuclear activities must be one step ahead of what happens in the specific activity areas in order to avoid surprises, to guarantee their activity continuity and the objective extents, and taking into account the external environment influence exercised by the organization on their activities. So, it is necessary a continuous follow up of their transformations. This paper aims to structure a model of the environmental monitoring system oriented to the strategic planning of the Brazilian Nuclear Energy Commission, as function of that new informational needs viewing the fulfilment of that observed gap. (author)

  16. Improvement of the quality control program of the clinical dosimeters calibration laboratory of the IPEN/CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Damatto, Willian B.; Potiens, Maria da Penha A.; Vivolo, Vitor, E-mail: wbdamatto@ipen.br, E-mail: mppotiens@ipen.br, E-mail: vivolo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    A set of clinical dosimeters (thimble ionization chamber coupled to an electrometer) commonly used in radiotherapy in Brazil and sent to the Calibration Laboratory of IPEN were under several tests and analysis parameters for the dosimeters behaviour were established, specifying their sensitivities and operating characteristics. Applied tests were: repeatability, reproducibility and current leakage. Thus it was possible to determine the most common defects found in these equipment and the actions that could be taken to prevent it (clinical dosimeters quality control programs). The behaviour of 167 dosimeters was analyzed and in this study, 62 of them have been tested. The main problem detected during calibration tests was current leakage, i.e. electronic noise. The tests were applied to the routine measurements at the Calibration Laboratory implementing an ideal calibration procedure. New calibration criteria were established following international recommendations. Therefore, it was made the improvement of the quality control programme of the clinical dosimeters calibration laboratory, benefiting the users of such equipment with better consistent calibration measurements. (author)

  17. Improvement of the quality control program of the clinical dosimeters calibration laboratory of the IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Damatto, Willian B.; Potiens, Maria da Penha A.; Vivolo, Vitor

    2013-01-01

    A set of clinical dosimeters (thimble ionization chamber coupled to an electrometer) commonly used in radiotherapy in Brazil and sent to the Calibration Laboratory of IPEN were under several tests and analysis parameters for the dosimeters behaviour were established, specifying their sensitivities and operating characteristics. Applied tests were: repeatability, reproducibility and current leakage. Thus it was possible to determine the most common defects found in these equipment and the actions that could be taken to prevent it (clinical dosimeters quality control programs). The behaviour of 167 dosimeters was analyzed and in this study, 62 of them have been tested. The main problem detected during calibration tests was current leakage, i.e. electronic noise. The tests were applied to the routine measurements at the Calibration Laboratory implementing an ideal calibration procedure. New calibration criteria were established following international recommendations. Therefore, it was made the improvement of the quality control programme of the clinical dosimeters calibration laboratory, benefiting the users of such equipment with better consistent calibration measurements. (author)

  18. Technology for manufacturing dispersion nuclear fuel at Instituto de Pesquisas Energeticas e Nucleares IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Durazzo, M.; Carvalho, E.F. Urano de; Saliba-Silva, A.M.; Souza, J.A.B.; Riella, H.G.

    2008-01-01

    IPEN has been working for increasing radioisotope production in order to supply the expanding demand for radiopharmaceutical medicines requested by the Brazilian welfare. To reach this objective, the IEA-R1 research reactor power capacity was recently increased from 2 MW to 3.5 MW. Since 1988 IPEN has been manufacturing its own fuel element, initially based on U 3 O 8 -Al dispersion fuel plates with 2.3 g U/cm 3 . To support the reactor power increase, higher uranium density had to be achieved for better irradiation flux and also to minimize the irradiated fuel elements to be stored. Uranium silicide was the chosen option. This paper describes the results of this program and the current status of silicide fuel fabrication and qualification. (author)

  19. Evaluation of uncertainties in X radiation metrologic chain in the Secondary Standard Dosimetry Laboratory/IRD-Brazilian CNEN

    International Nuclear Information System (INIS)

    Fonseca Coelho, B.C. da.

    1987-01-01

    The equipment to measure ionizing radiation used in medicine needs appropriate technical qualifications to comply with their purposes and regular calibrations to assure the correct evaluation of associated quantities. By legal requirements, the annual calibration of users' dosemeters is to be done in a Secondary Standard Dosimetry Laboratory (SSDL), andthe SSDL'S standard dosemeters are refered to a Primary Standard Dosimetry (PSDL), establishing a rigourous metrological network. The SSDL network. The SSDL needs to maintain, regularly, a quality control program for short and Long term stability of standard dosemeters. The purpose of the work was to determine the uncertainties associated to technical procedures of X-rays calibration at the SSDL/IRD/IRD. To evaluate the influence of the nine main parameters that can give origin to uncertainties, specific procedures and methods are established, according to international requirements and recomendations. The methods are based on the comparison of the behaviour of the users' dosemeters, with a standard dosemeter in the many measuring conditions set up for the secondary standard used as a reference. The total uncertainty obtained was 1,81% usig a conservative procedure, to protect the users and patients. When needed to transfer the calibration factor and their uncertainty, the procedure used was to determine the uncertainty under the worsst possible operating conditions of the equipment, to obtain a superestimated value. This represents an excellent result for an SDDL of IAEA Network. (autor) [pt

  20. Study of dosimetric parameters for iodine-125 brachytherapy sources development from IPEN-CNEN/SP using Monte Carlo method

    International Nuclear Information System (INIS)

    Oliveira, Tiago Batista de

    2016-01-01

    Expectations of the World Health Organization for the year 2030 are that the number of cancer deaths is approximately 13.2 million, reflecting the high proportion of this disease in global health issue. With respect to prostate cancer, according to the National Cancer Institute, the number of cases diagnosed worldwide in 2012 was approximately 1.1 million, while in Brazil the data demonstrated the incidence of 68,000 new cases. The treatment of cancer can be performed with surgery (prostatectomy) or radiation therapy. Among radiotherapy, we can highlight the brachytherapy technique, which consists in the introduction of small radioactive sources (seeds) within the prostate, which is delivered a high dose value in the treatment volume and low dose in the surrounding tissues. In Brazil, the medical profession estimates a demand of approximately 8000 seeds / month, and the unit cost of each seed at least US $ 26.00. The AAPM protocol TG-43 recommend the dose-rate constant, radial dose function and anisotropy function for dosimetric analysis LDR brachytherapy seeds. In this work, Monte Carlo simulations were performed in order to assess the dosimetric parameters of the OncoSeed-6711, manufactured by Oncura-GEHealthcare, and a seed developed by Radiation Technology Center, using the MCNP5 code. A 6711 seed, an IPEN seed and the 30 x 30 x 30cm 3 phantom filled with water were modeled to simulate the dose distribution. The 6711 seed parameters were compared with literature, and the results presented relative error less than 0.1% for Λ. In comparison with the 6711 seed, the IPEN model seed dosimetric parameters were similar, account the statistical uncertainty. (author)

  1. Education in nuclear science at IPEN - CNEN, Sao Paulo, Brazil. Advanced School of Nuclear Energy-EAEN

    International Nuclear Information System (INIS)

    Semmler, R.; Catharino, M.G.M.; Vasconcellos, M.B.A.

    2012-01-01

    EAEN (Advanced School of Nuclear Energy, 2010) is an annual school that consists of a week of activities in the area of Nuclear Physics, Radiochemistry and uses of Nuclear Energy for a public made of high school students. The EAEN project represents a pioneering program on science education and dissemination of knowledge, conducted by researchers and focused mainly on high school and scientific education for the population in general. The school's priority is to explore the failures and the lack of education in the dissemination of nuclear energy for high school students as well as to attract prospective students with great potential for graduate courses of IPEN and other institutions in Sao Paulo and in Brazil. (author)

  2. Application of NAA to the determination of mineral and trace elements in Brazilian diets at IPEN/CNEN/SP

    International Nuclear Information System (INIS)

    Favaro, D.I.T.; Maihara, V.A.; Souza, S.A.; Vasconcellos, M.B.A.; Mafra, D.; Cordeiro, M.B.C.; Cozzolino, S.M.F.

    2000-01-01

    Concentration of the 14 elements Br, Ca, Cl, Co, Cs, Fe, K, Mn, Na, Rb, Sc, Se and Zn have been determined by INAA in diets of four different groups: (a) 19 pre-school children, (b) 18 healthy adults, (c) 23 elderly people living in private institutions and (d) 19 patients with chronic renal failure (CRF). The contents of proteins, lipids and carbohydrates were also analysed in the diets. The daily intakes of the elements analysed were compared to the recommended values set by RDA or WHO. (author)

  3. Assessment of the occupational exposure of the workers involved in the 123I production at the IEN/CNEN-RJ

    International Nuclear Information System (INIS)

    Araujo, Francisco de

    2005-01-01

    123 I is a gamma emitter used for diagnosis in Nuclear Medicine. Since 1998 it is produced in the Institute of Nuclear Energy (IEN) and supplied to the Clinics and Hospitals located in the city of Rio de Janeiro. The annual production is in the approximately of 0,74 TBq (20 Ci), which represents a risk of external and internal exposure to the workers involved in this activity. A survey of external doses in the period of 1994 to 2004 was carried out based on the individual registries available in the CONEXO Data Base operated by the Institute of Radiation Protection and Dosimetry (IRD). It was verified an increase of the external exposure associated to the production curve. However, the individual doses are all bellow the annual limits established by the regulatory board. On the other hand, the variation of doses among individuals involved in the same tasks suggests the possibility of optimization of procedures. Regarding internal exposure it was calculated a decision factor above 1mSv for the practice, which justifies the need for internal monitoring. An evaluation of the process based on the results of in vivo thyroid monitoring in the period of 2000 to 2004 was carried out to identify the steps which represent higher risk of internal exposure. The available data indicate that the laboratory of quality control is the critical step in terms of internal contamination. This conclusion can be justified by the high volatility of iodine which is manipulated in the form of a liquid open source during this step. With the aim of optimizing monitoring procedures for the control of occupationally exposed workers in the production of 123 I, in vivo and in vitro bioassay methods were developed to identify and quantify internal contamination by such radionuclide, using the detection systems available at the Bioassay Laboratory and at the In Vivo Measurements Laboratory. The techniques developed present sensitivity compatible with the derived registry level associated to the committed effective dose equivalent of 1mSv. It was also established a methodology for the interpretation of bioassay data using the software AIDE. The methods developed in this work can be used to implement improvements in the radiation protection program of the IEN. It is suggested to increase the frequency of in vivo measurements and to include in vitro bioassay in the monitoring program, which will permit a better evaluation of the internal doses of the workers(author)

  4. Toxicity evaluation of the effluent of the ammonium diuranate process proceeding from the Uranium Reconversion Cycle (IPEN/CNEN-SP)

    International Nuclear Information System (INIS)

    Osti, Silvio Cesar de

    2001-01-01

    This project was developed with the objective to evaluate the acute and chronic toxicity of the ammonium diuranate proceeding from the process used to obtain uranium hexafluoride (UF 6 ), substance which is necessary to produce fuel used by the IEA-R1-IPEN reactor. Five acute toxicity tests were done with Daphnia similis in which concentration values of EC(I)50;48h, between 0,39% and 0,57% of the effluent were determined, and other five with Danio rerio in which concentration values of EC(I)50;48h, between 0,06% and 0,07% of the effluent were determined. Three chronic toxicity tests with Selenastrum capricornutum were done, having found NOEC values for concentrations below 0,12% of the effluents. To determine the ion fluoride toxicity in the Daphnia similis, five acute toxicity tests were done in which values of EC(I)50;48h, between 263.90 mgL -1 and 292.82 mgL -1 were found. The acute toxicity tests done with D. similis demonstrated that the effluent toxicity persisted during its storage period. The acute toxicity test with D.rerio and chronic ones with S. capricornutum using the effluents after the ionic-replace treatment, which objective is to recover uranium for reuse, demonstrated the effluent toxicity persistency. (author)

  5. Neutron and gamma radiation levels analysis for 18 MeV cyclotron operation at IPEN-CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Paula P.N.; Fernandes, Ivani M.; Silva, Amanda J. da; Rodrigues, Demerval L.; Romero Filho, Christovam R., E-mail: ppsilva@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The Accelerator Cyclotron Facility provides activities that involve exposure to ionizing radiation, so it is necessary to establish a monitoring program that allows the dose control of the workers, based on the principles of the radiation protection. Besides the individual monitoring, the area monitoring is carried out aiming to evaluate the dose rates in areas that are occupied by workers during the execution of their tasks. This study aims to present the levels of neutron and gamma radiation results, obtained by monitoring the Accelerator Cyclotron Facility areas, during the Cyclone-18 operation. The study was based on data gathered from the area monitoring reports conducted by the radioprotection team in the years 2010 and 2011. To determine the dose rate, specific equipment was used. It was monitored 09 spots (from A to I), totalizing 280 and 205 measurements at each spot in the years 2010 and 2011, respectively. The 'B' spot showed the least influence for gamma and neutron radiation in both years. The spots with the highest neutron and gamma dose rates, in both years, were the 'E' and 'I' spots, respectively. With these results, we can say that the area monitoring is carrying out with its goal of preventing the doses that can be accumulated by the workers during the course of their work. (author)

  6. Study of the elution {sup 99}Mo-{sup 99m}Tc generators produced at IPEN-CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Paula Regina Corain [Pontificia Univ. Catolica de Sao Paulo, SP (Brazil); Instituto de Pesquisas Energeticas e Nucleares IPEN/CNEN-SP, Sao Paulo, SP (Brazil)]. E-mail: corain.lopes@uol.com.br; Osso Junior, Joao Alberto [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: jaosso@ipen.br

    2007-07-01

    Over the last years {sup 99m}Tc has become a very important asset in modern nuclear medicine, due to the emission of gamma ray of optimal energy (140 keV) and a suitable half-life (6.04 h). A further attribute of {sup 99m}Tc is its formation from the decay of {sup 99}Mo and the availability from {sup 99}Mo-{sup 99m}Tc generator systems. The most common and practical generator types consist of a chromatographic column packed with aluminium oxide, onto which the highly purified fission product {sup 99}Mo (imported from Canada) is adsorbed in the form of molybdate. {sup 99m}Tc is further eluted with saline solution. The objective of this work is to study the performance and the elution profile of {sup 99m}Tc from high activity generators in order to decrease molybdenum and aluminium concentration. The experiments involved the use of paper filters and Sep Pak columns and also the changing in the time interval between elutions. {sup 99}Mo breakthrough was measured using a dose calibrator and aluminium by UV-Vis spectrophotometry. The best results were achieved using a Sep Pak column containing neutral aluminium oxide. (author)

  7. Study of the elution 99Mo-99mTc generators produced at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Lopes, Paula Regina Corain; Osso Junior, Joao Alberto

    2007-01-01

    Over the last years 99m Tc has become a very important asset in modern nuclear medicine, due to the emission of gamma ray of optimal energy (140 keV) and a suitable half-life (6.04 h). A further attribute of 99m Tc is its formation from the decay of 99 Mo and the availability from 99 Mo- 99m Tc generator systems. The most common and practical generator types consist of a chromatographic column packed with aluminium oxide, onto which the highly purified fission product 99 Mo (imported from Canada) is adsorbed in the form of molybdate. 99m Tc is further eluted with saline solution. The objective of this work is to study the performance and the elution profile of 99m Tc from high activity generators in order to decrease molybdenum and aluminium concentration. The experiments involved the use of paper filters and Sep Pak columns and also the changing in the time interval between elutions. 99 Mo breakthrough was measured using a dose calibrator and aluminium by UV-Vis spectrophotometry. The best results were achieved using a Sep Pak column containing neutral aluminium oxide. (author)

  8. IRD-CNEN whole body counter capabilities for in vivo monitoring of internally deposited radionuclides in human body

    Energy Technology Data Exchange (ETDEWEB)

    Dantas, A.L.A.; Lucena, E.A.; Dantas, B.M., E-mail: adantas@ird.gov.br, E-mail: eder@ird.gov.br, E-mail: bmdantas@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. de Monitoracao in Vivo

    2015-07-01

    Internal exposure to radionuclides may occur as a result of a variety of practices, such as in nuclear industry, production of radiopharmaceuticals and nuclear medicine, biological research and agriculture; as well as in mining and milling of minerals with associated NORM. The IRD whole-body counter consists of shielded room equipped with an array of four HPGe detectors and two NaI(Tl) with dimensions of 8” x 4” and 3” x 3”. The detection systems are able to detect and quantify a large variety of radionuclides emitting photons in the energy range from 10 to 3000 keV. The minimum detectable activities for most of the radionuclides of interest allow occupational monitoring as well evaluation of accidental intakes. (author)

  9. A simple and powerful XY-Type current monitor for 30 MeV IPEN/CNEN-SP cyclotron

    Energy Technology Data Exchange (ETDEWEB)

    Barcellos, Henrique; Matsuda, Hylton; Sumyia, Luiz Carlos do A.; Junqueira, Fernando de C.; Costa, Osvaldo L. da, E-mail: hbolivei@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2017-11-01

    A water-cooled XY-type current monitor was designed and built in the Cyclotrons Laboratory of the Nuclear and Energy Research Institute (IPEN). It is a very simple design and easily adaptable to the cyclotron beam lines. Tests were done demonstrating to be an instrument of great assistance in proton beam position along beam transport line and target port. Nowadays the XY-type current monitor has been widely used in {sup 18}F-FDG routine productions, employing irradiation system which were originally designed for productions on 18 MeV cyclotron accelerator only, however, applying the XY-type current monitor the target port may be exchanged between the 30 MeV and 18 MeV cyclotrons and the observed results are in perfect agreement with expected. (author)

  10. Personnel dosimetry of extremities by using Harshaw rings XD-100 at Centro Regional de Ciencias Nucleares, CRCN, Brazilian CNEN

    International Nuclear Information System (INIS)

    Lima, Ricardo de Andrade; Vilela, Eudice; Nogueira, Maria do Socorro; Ferreira Filho, Alfredo Lopes; Castro, Walber Amorim

    2000-01-01

    Data concerning calibration and type tests of an extremity system based on XD100 rings (Harshaw) are presented. Dosemeter used is a thermoluminescent chip inserted in a sealed pouch and was read out using a Harshaw 6600 reader. The dosimetric system complied with all ISO/DIS 12794-1 draft report suggested tests, in which this work was based on. This work obtained results point to the applicability of those recommendations to Brazilian institutes and suggest its adoption by the national regulatory commission. (author)

  11. Low yield syntheses of [18F]FDG at CDTN/CNEN-MG: problem diagnosis and corrective actions

    International Nuclear Information System (INIS)

    Dalle, Hugo M.; Silva, Juliana B.; Valente, Eduardo S.; Malamut, Carlos; Nascimento, Leonardo T.C.; Silveira, Marina B.; Ferreira, Soraya M.Z.M.D.; Borges, Leonardo T.; Truong, Phong; Olsson, Ake

    2017-01-01

    The Nuclear Technology Development Center manages, since 2007, a Radiopharmaceuticals Research and Production Unit. In the first months of 2014, the radiopharmaceuticals syntheses yields started to fall well under the nominal values. This paper presents a summary of the tests performed to identify the causes of the low yield syntheses and the actions taken to resolve. By sharing our experience, we aim to help other radiopharmaceuticals producers facing similar situation, as solution may not be trivial, neither fast nor cheap. (author)

  12. Study of social responsibility of the Nuclear and Energy Research Institute of Sao Paulo (IPEN/CNEN-SP)

    International Nuclear Information System (INIS)

    Mutarelli, Rita de Cassia

    2014-01-01

    Over the years, the socio-environmental concept has grown through programs, conferences and several activities that have been held in Brazil and worldwide. Sustainability and social responsibility are now an integral part of everyday life of organizations The Instituto de Pesquisas Energeticas e Nucleares (IPEN), which is the focus of this research, is committed to the improvement of Brazilian quality of life. Based on IPEN's mission, and due to the lack of tools for assessing socio-environmental actions, this research aims to propose an assessment tool for social responsibility, which may also be a methodological resource committed to the improvement of the Institute. Through indicators and dimensions, a methodology to assess social responsibility and identify both strengths and weaknesses was designed. The methodology was administered to IPEN, and the results demonstrated positive aspects regarding actions towards the internal publics and negative aspects towards the external publics that require improvement. The results obtained were satisfactory. Nevertheless, as the subject of this study is a broad theme, further studies are suggested. IPEN's board may use the results of this research as a tool to help them identify feasible socio-environmental actions to be implemented in the institute. (author)

  13. The radiological safety in the use of nuclear technique -activities developed by Centro de Desenvolvimento da Tecnologia Nuclear - CNEN

    International Nuclear Information System (INIS)

    Wakabayashi, T.; Pereira, E.G.; Hirayama, T.

    1991-01-01

    The activities developed by the Centro de Desenvolvimento da Tecnologia Nuclear - CDTN supporting the users of nuclear techniques are described. The methodology used and future plans for the group are shown. (E.G.)

  14. Bridging Nuclear Knowledge to a Brazilian Decree: A Case Study at the National Nuclear Energy Commission (CNEN)

    International Nuclear Information System (INIS)

    Muguet-Haisman, T. M.

    2016-01-01

    Full text: Since the term“knowledge management”was coined, it has gained more and more attention in an effort to re-structure organizations. A good deal of effort has been done in order to better implement a knowledge management culture in organizations throughout all the work sectors. The Brazilian Federal Government through the Decree no.5.707, dated February 23, 2006, democratically created a national policy for human development. This initiative made equally available additional education opportunities for all staff in order to form a competent workforce which included official recognition of work-related skills. In the field of nuclear energy, the National Nuclear Energy Commission is a Brazilian governmental authority which has long served as the leader in the matter. In this respect, and in the light of the International Atomic Energy Agency (IAEA) nuclear knowledge management role and the perspective of the first and third dimensions, the aim of this paper is to share the outcome of the Government programme in the National Nuclear Energy Commission. (author

  15. Evaluation of controlled areas in the fuel element facility IPEN/CNEN/SP by the technique of surface contamination

    International Nuclear Information System (INIS)

    Silva, Teresinha de Moraes da; Sordi, Gian Maria A.A.; Almeida, Claudio C.; Brasil, Paulo; Paiva, Julio E.

    2013-01-01

    Working with radioactive materials makes the safety culture is present in everyday life of nuclear facilities. The radiological protection management provides the monitoring program for individual occupational exposure (IOE) and for the working place. The facilities are monitored by the radiometric surface and air survey. This paper presents a surface monitoring technique which assesses the workplace and estimates the dose in real time that the worker is subject to, considering the radionuclides used in the process. In this study, the radionuclide is uranium enriched to 19.5%. (author)

  16. Implementation of a metrology programme to provide traceability for radionuclides activity measurements in the CNEN Radiopharmaceuticals Producers Centers

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Erica A.L. de; Braghirolli, Ana M.S.; Tauhata, Luiz; Gomes, Regio S.; Silva, Carlos J., E-mail: erica@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Delgado, Jose U.; Oliveira, Antonio E.; Iwahara, Akira, E-mail: ealima@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The commercialization and use of radiopharmaceuticals in Brazil are regulated by Agencia Nacional de Vigilancia Sanitaria (ANVISA) which require Good Manufacturing Practices (GMP) certification for Radiopharmaceuticals Producer Centers. Quality Assurance Program should implement the GMP standards to ensure radiopharmaceuticals have requirements quality to proving its efficiency. Several aspects should be controlled within the Quality Assurance Programs, and one of them is the traceability of the Radionuclides Activity Measurement in radiopharmaceuticals doses. The quality assurance of activity measurements is fundamental to maintain both the efficiency of the nuclear medicine procedures and patient and exposed occupationally individuals safety. The radiation doses received by patients, during the nuclear medicine procedures, is estimated according to administered radiopharmaceuticals quantity. Therefore it is very important either the activity measurements performed in radiopharmaceuticals producer centers (RPC) as the measurements performed in nuclear medicine services are traceable to national standards. This paper aims to present an implementation program to provide traceability to radionuclides activity measurements performed in the dose calibrators(well type ionization chambers) used in Radiopharmaceuticals Producer Center placed in different states in Brazil. The proposed program is based on the principles of GM Pand ISO 17025 standards. According to dose calibrator performance, the RPC will be able to provide consistent, safe and effective radioactivity measurement to the nuclear medicine services. (author)

  17. Evaluation of controlled areas in the fuel element facility IPEN/CNEN/SP by the technique of surface contamination

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Teresinha de Moraes da; Sordi, Gian Maria A.A.; Almeida, Claudio C.; Brasil, Paulo; Paiva, Julio E., E-mail: tmsilva@ipen.br, E-mail: calmeida@ipen.br, E-mail: cambises@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    Working with radioactive materials makes the safety culture is present in everyday life of nuclear facilities. The radiological protection management provides the monitoring program for individual occupational exposure (IOE) and for the working place. The facilities are monitored by the radiometric surface and air survey. This paper presents a surface monitoring technique which assesses the workplace and estimates the dose in real time that the worker is subject to, considering the radionuclides used in the process. In this study, the radionuclide is uranium enriched to 19.5%. (author)

  18. Recent advances and actual status of actinides and Lanthanides research at the IPEN-CNEN/Sao Paulo, Brazil

    International Nuclear Information System (INIS)

    Abrao, A.

    1988-01-01

    This paper focuses on the experience acquired with the operation of a pulsed columns solvent extraction unit for the refining of yellowcake produced from the industrial treatment of monazite sand, and the further experimental production of ammonium diuranate, uranium oxides, uranyl tricarbonate and tetra-and hexafluorides of uranium at the pilot plant scale. Special studies have been devoted to the decontamination of the rare earth elements, thorium and zirconium. The refining of thorium in a solvent extraction composite column and the experimental production of crystallized nuclear grade thorium nitrate at the pilot plant scale is also discussed. Thorium hydroxide sludges and crystallized thorium sulphate are used as raw materials, both produced from an alkaline breaking up monazite process. Developmental efforts have also been directed towards the rare earth fractionation using as a first step previous chemical fractionation of the rare earth chlorides and the ion-exchane individual fractionation as the final process step to obtain extremely pure oxides. Finally, the establishment of analytical procedures as an important support to the technical work is emphasized. An extended version of this work will be published elsewhere. (author) [pt

  19. Participation of IRD/CNEN-Br in International Intercomparison of Criticality Accident Dosimetry Systems at Silene reactor, France

    International Nuclear Information System (INIS)

    Mauricio, Claudia Lucia P.; Fonseca, Evaldo S. da

    1996-01-01

    IRD has participated in an International Intercomparison of Criticality Accident Dosimetry Systems at the SILENE reactor, France on June 1993. The dosemeters were irradiated on phantoms and free in air, in bare and lead shield reactor pulses, simulating different irradiation fields that can be found in criticality accidents. Comparing with the reference measurements, the calculated mean neutron kerma found by IRD was only 2% greater for lead shield and 14% greater for bare reactor. For gamma absorbed dose, the differences were, respectively + 22% and -9% for the dosemeters free in air and -19% and -9% for dosemeters on phantoms. IRD results are closer to the real values than the mean values measured by the participants. IRD results show a good performance if its simple criticality accident system. (author)

  20. Program for in-pile qualification of high density silicide dispersion fuel at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Silva, Jose E.R. da; Silva, Antonio T. e; Terremoto, Luis A.A.; Durazzo, Michelangelo

    2009-01-01

    The development of high density nuclear fuel (U 3 Si 2 -Al) with 4,8 gU/cm 3 is on going at IPEN, at this time. This fuel has been considered to be utilized at the new Brazilian Multipurpose Reactor (RMB), planned to be constructed up to 2014. As Brazil does not have hot-cell facilities available for post-irradiation analysis, an alternative qualifying program for this fuel is proposed based on the same procedures used at IPEN since 1988 for qualifying its own U 3 O 8 -Al (1,9 and 2,3 gU/cm 3 ) and U 3 Si 2 -Al (3,0 gU/cm 3 ) dispersion fuels. The fuel miniplates and full-size fuel elements irradiations should be tested at IEA-R1 core. The fuel characterization along the irradiation time should be made by means of non-destructive methods, including periodical visual inspections with an underwater video camera system, sipping tests for fuel elements suspected of leakage, and underwater dimensional measurements for swelling evaluation, performed inside the reactor pool. This work presents the program description for the qualification of the high density nuclear fuel (U 3 Si 2 -Al) with 4,8 gU/cm 3 , and describes the IPEN fuel fabrication infrastructure and some basic features of the available systems for non-destructive tests at IEA-R1 research reactor. (author)

  1. Regulatory quality control in the metal and semi metal environmental monitoring program at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Faustino, Mainara G.; Silva, Doulgas Batista; Monteiro, Lucilena R.; Dantas, Elizabeth S.K.; Pires, Maria Aparecida F.; Cotrim, Marycel E.B.

    2013-01-01

    The CONAMA's Resolution 430 recently published in May 13 th of 2011, that completes and modifies the Resolution 357/2005, defined new quality standards to perform liquid effluent monitoring essays in order to allow the release in the public sewer system. This Resolution has established that the essay laboratories must be certified by Brazilian National Metrology, Normalization and Industrial Quality Institute - INMETRO and also count with an implemented quality control system. Thereby this publication affected directly IPEN's Environmental Monitoring Program of Stables Chemical Compound (PMA-Q), performed since 2007. In this program, 20 parameters related to the metallic and non-metallic chemical elements content are monitored by using sensitive analytical techniques such as graphite furnace atomic absorption spectrometry - GF-AAS or inductively coupled plasma spectrometry - ICP-OES. Therefore this paper presents improvements to determine the laboratory individual performance performed by GF-AAS and ICP-OES. To achieve the legislation compliance for these parameters, the following actions were implemented: the construction of control charts (internal quality control) and the participation of the laboratory in interlaboratory proficiency tests (external quality control). These actions are presented and discussed with the results of elements such as Arsenic and Lead that are analyzed through GF-AAS as well as Chromium, Cooper, Zinc, Iron and Nickel, that are analyzed through ICP-OES. These actions of quality control allowed the continuous monitoring of laboratory performance, the identification and resolution of analytic problems and interlaboratory differences, provide additional confidence to monitoring program. (author)

  2. The implementation of CP1 computer code in the Honeywell Bull computer in Brazilian Nuclear Energy Commission (CNEN)

    International Nuclear Information System (INIS)

    Couto, R.T.

    1987-01-01

    The implementation of the CP1 computer code in the Honeywell Bull computer in Brazilian Nuclear Energy Comission is presented. CP1 is a computer code used to solve the equations of punctual kinetic with Doppler feed back from the system temperature variation based on the Newton refrigeration equation (E.G.) [pt

  3. Participation of the IPEN/CNEN/SP Environmental Diagnostic Division on programs of laboratory intercomparisons in environmental samples

    International Nuclear Information System (INIS)

    Cotrim, Marycel Barboza; Sato, Ivone Mulako; Salvador, Vera Lucia R.; Dantas, Elizabeth Sonoda Keiko; Cantagallo, Maria Ines; Lemes, Marcos Jose L.; Scapin, Marcos Antonio; Sisti, Cristina; Silveira, Elias Santana; Furusawa, Helio Akira; Pires, Maria Aparecida Faustino

    2003-01-01

    The present work presents the participation of the Environmental Diagnostic Division Laboratories (MQA) at the intercomparison national and international laboratories, (PI/SABESP - Interlaboratory Sao Paulo, Brazil, Program; Program for Interlaboratorial Analytic Quality Control of Metals in Water (CBM/COMETRO); Programa para La Calidad de las Mediciones Quimicas (PCQM/INTI) - Argentine, and the Commission d'Etablissement des Methodes d'Analyse, France (CETAMA/CEA). Those essay providers have using statistical tests such as the t-Student, Zscore and Cochran and Grubbs for the data evaluations. The obtained results are presented involving the analytical such as atomic absorption spectrometry: flame, graphite oven and hydride generation (AAS), emission spectrometry with induced plasma (ICP-OES), X-ray fluorescence WD-XRFS), ion chromatography and voltametry (VRA). The elements such as B, Al, K, Mg, Ca, Cr, Fe, Co, Cu, Zn and Pb, and the anions such as Cl-, NO 3 - , SO 4 2- and F - , were determined at trace level (mgL -1 ), and the elements such as Cr, As, Cd, Pb e Hg, at the trace level (μgL -1 ) in water matrices. The evaluation of analytical results, in the period 1997 to 2002, demonstrate a continuous improvement evidencing the importance of Laboratories participation at those type of exercises

  4. Study of the radioactive impurities gamma emitters present in the radiopharmaceutical solutions produced at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Almeida, Jamille da Silveira

    2017-01-01

    This work aims to investigate the concentration of radioactive impurities gamma emitters in the radiopharmaceutical solutions produced at Nuclear and Energy Research Institute -IPEN in Sao Paulo, So that this radiopharmaceutical may be used properly, its quality should be evaluated in accordance with the procedures established by quality control agencies, such as General Requirements for the Competence of Testing and Calibration Laboratories' ISO/IEC 17025:2005 and the 'Good Laboratory Practice (GLP), controlled by ANVISA (National Agency Health Surveillance), in Brazil, requiring a confirmation of the values of impurities related at the certificates supplied by the manufacturers. To determine the activity, a high resolution gamma spectrometer were used in two source-detector distances. One was 18 cm and the other 1.7 cm. For the 18 cm distance, the high pure germanium spectrometer was calibrated in the energy range between 81 keV and 1408 keV by measuring sealed ampoules of "6"0Co, "1"3"3Ba, "1"3"7Cs and "1"5"2Eu, standardized at the Nuclear Metrology Laboratory (NML) of IPEN. For lower activity of the impurities, the distance source-detector of 1.7 cm was assumed. However, as at this distance, the sum coincidence effect is very high, making the measurement of the standard calibration ampoules difficult, the spectrometer efficiency curve was obtained by a Monte Carlo simulation code, developed at IPEN. In this code, all details of the detection system are modeled and the response curves for x-rays and gamma rays are calculated by the MCNPX radiation transport code. The gamma spectra were analyzed by Alpino code, which applies the method of numeric peak integration of the area under the photopeaks. For gamma emitter impurities, not visually detected, the decision threshold and the detection limits were calculated from the background count rate, under the peak area. The radiopharmaceutical solutions analyzed were "6"7Ga, "9"9Mo, "9"9"mTc, "1"1"1In, "1"3"1I, "1"5"3Sm, "1"7"7Lu and "2"0"1Tl. The results of impurities ratio for analyzed solutions are in accordance with the manufacturers' certificate and with the ANVISA. (author)

  5. Low yield syntheses of [{sup 18}F]FDG at CDTN/CNEN-MG: problem diagnosis and corrective actions

    Energy Technology Data Exchange (ETDEWEB)

    Dalle, Hugo M.; Silva, Juliana B.; Valente, Eduardo S.; Malamut, Carlos; Nascimento, Leonardo T.C.; Silveira, Marina B.; Ferreira, Soraya M.Z.M.D.; Borges, Leonardo T. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Truong, Phong [GE Healthcare do Brasil, São Paulo, SP (Brazil); Olsson, Ake, E-mail: dallehm@cdtn.br, E-mail: leonardo.borges@ge.com, E-mail: phong.truong@ge.com [GE Healthcare, Uppsala (Sweden)

    2017-07-01

    The Nuclear Technology Development Center manages, since 2007, a Radiopharmaceuticals Research and Production Unit. In the first months of 2014, the radiopharmaceuticals syntheses yields started to fall well under the nominal values. This paper presents a summary of the tests performed to identify the causes of the low yield syntheses and the actions taken to resolve. By sharing our experience, we aim to help other radiopharmaceuticals producers facing similar situation, as solution may not be trivial, neither fast nor cheap. (author)

  6. Dosimetric characterization of low dose rate Iridium 192 wires used in interstitial brachytherapy, produced by Brachytherapy Sources Laboratory the CTRS/IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Silva, Marco Antonio da

    2003-01-01

    In this work they were some dosimetric parameters established by the dosimetry protocol AAPM TG-43 for the thread of 192 Ir with the purpose of complementing the dosimetric specifications of an original source produced at the country. For so much quantities such as the constant of dose rate, A , function of radial dose, g(r), and anisotropy function, F(r,θ), they were experimentally determined and the geometry function, G(r,θ), it was calculated. Measurements with TLD of LiF, with dimensions of 1 mm X 1 mm X 1 mm, was made in a phantom made of 5 plates of solid water RW3 material with dimensions of 300 mm X 300 mm X 10 mm, where it was obtained values of dose rate for some radial distances of the source, between 10 and 100 mm, to for an angle of 90 deg, for g(r), and also for other angles between 0 deg and 180 deg for F(r,θ). Threads of 192 Ir were studied in the lengths of 10 mm, 20 mm, 30 mm, 50 mm and 100 mm. The stored energy on the thermoluminescent dosimeters was integrated by means of a TLD reader Harshaw 2000 meantime into a cycle of thermal treatment to which the thermoluminescent dosimeters was submitted being, 400 C in an interval of time of 1 hour proceeded immediately for more 2 hours to 105 C, after this treatment the thermoluminescent dosimeters was irradiated; even so, before the reading the detectors was still warm to 105 deg C for 10 minutes. The constant of dose rate for the threads of 192 Ir of 10 mm, 20 mm, 30 mm, 50 mm and 100 mm are (1,076 =- 3,7%); (0,931 =- 3,7%); (0,714 =- 3,7%); (0,589 =-3,7%) and (0,271 =- 3,7%) cGyh -1 U -1 , respectively (1U = unit of kerma intensity in the air = 1mGy m 2 h -1 = 1cGy cm 2 h -1 ). The results obtained for g(r) and F(r,θ) have uncertainties of (=- 4,5%) and they are compared with values obtained by Monte Carlo simulation and also for other values presented in the literature. (author)

  7. Study for correction of neutron scattering in the calibration of the albedo individual monitor from the Neutron Laboratory (LN), IRD/CNEN-RJ, Brazil

    International Nuclear Information System (INIS)

    Freitas, B.M.; Silva, A.X. da

    2014-01-01

    The Instituto de Radioprotecao e Dosimetria (IRD) runs a neutron individual monitoring service with albedo type monitor and thermoluminescent detectors (TLD). Moreover the largest number of workers exposed to neutrons in Brazil is exposed to 241 Am-Be fields. Therefore a study of the response of albedo dosemeter due to neutron scattering from 241 Am-Be source is important for a proper calibration. In this work, it has been evaluated the influence of the scattering correction in two distances at the Low Scattering Laboratory of the Neutron Laboratory of the Brazilian National Laboratory (Lab. Nacional de Metrologia Brasileira de Radiacoes Ionizantes) in the calibration of that albedo dosemeter for a 241 Am-Be source. (author)

  8. Review of criterias for shallow burial sites and geohydrological evaluation around the site of temporary storage of low-level solid radioactive wastes of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Chandra, U.; Marcelino, S.

    1986-01-01

    Some comments about norms of pollutants release from nuclear and other industries are made. For radioactive discharges, the strictly implemented national norms/criterias, are much more advanced technically than those existing for other pollutants. Based on the criterias of site selection and site evaluations, the site of IPEN for temporary storage of low level solid radioactive waster has been evaluated geohydrologically. Rainfall infiltration rate (297 cm/y) was determined by tritium labelling technique. Ground water velocity (max. 46.1 cm/d) and direction (to north) was determined by various radioactive (Br-82, I-131, Cr-51) tracers using single well techniques. (Author) [pt

  9. Main results of the standardization through anti-coincident from the Brazilian Laboratory for Metrology of Ionizing Radiations - LNMRI/IRD/CNEN-RJ in the last 8 years

    International Nuclear Information System (INIS)

    Silva, Carlos J. da

    2014-01-01

    The LNMRI implemented in 2006 a system of time keeping in anticoincidence live in this time and dead time extensible today 18 radionuclides were standardized. To store the results of these primary standardization the LNMRI/IRD reference with ionization chamber were calibrated with these standards. In this work will be discussed the main operational difficulties and components of uncertainty and the main results. (author)

  10. Evaluation of instrumental parameters for obtaining acceptable analytical results of the Dosimetry Laboratory of Chemistry of the Regional Center of Nuclear Sciences, CNEN-NE, Recife, Brazil

    International Nuclear Information System (INIS)

    Souza, V.L.B.; Figueiredo, M.D.C.; Cunha, M.S.

    2008-01-01

    Instrumental parameters need to be evaluated for obtaining acceptable analytical results for a specific instrument. The performance of the UV-VIS spectrophotometer can be verified for wavelengths and absorbances with appropriate materials (solutions of different concentrations of K 2 CrO 4 , for example). The aim of this work was to demonstrate the results of the procedures to control the quality of the measurements carried out in the laboratory in the last four years. The samples were analyzed in the spectrophotometer and control graphics were obtained for K 2 CrO 4 and Fe 3+ absorbance values. The variation in the results obtained for the stability of the spectrophotometer and for the control of its calibration did not exceed 2%. (author)

  11. Optimization of radiation protection for an electron accelerator used in paint cure in films approved by Brazilian Nuclear Energy Commission - CNEN, Rio de Janeiro, Brazil

    International Nuclear Information System (INIS)

    Rios, Denise A. da S.; Sordi, Gian Maria A.A.

    2014-01-01

    This study aims to evaluate the radiological protection system in an installation where there is a self-shielded accelerator Category I, used for paint curing in polymer films, in order to optimize it in situations in which it is appropriate. For this a radiometric survey was conducted in the designated areas to check rate doses at different distances from the radiation focus, in which there is a possibility of presence or persons which can reliably detect any abnormality in the accelerator operation. The comparison of the obtained values related to the accelerator operating current with the natural background radiation showed that they are compatible, signaling that the principle of optimization is already being followed

  12. Development of Technology for the Preparation of 90Sr/90Y Generators at the Radiopharmacy Directory of IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Barrio, Graciela

    2010-01-01

    90 Y (T /2 = 2,67 d; Eβmax = 2,28 MeV) is a radionuclide with efficacy established for various cancer therapies, labeling biomolecules and treating of radiosinovectomy. Due to its nuclear properties, is obtained through the decay of 90 Sr T /2 = 28 y in the form of a generator. Several types of 90 Sr/ 90 Y generators were developed, and the most employed are the cation exchange resins, where Sr and Y are adsorbed and 90 Y is selectively eluted with acetate or EDTA. The disadvantage of this type of generator is the radiolysis, which degrades its use. The electrochemical generator is a proposed solution because there is no significant effect of radiation. In this concept, the difference between the electrochemical potentials of the elements Sr and Y is used to obtain a rapid separation of 90 Y from 90 Sr. The production of 90 Y via colloid formation is the simplest method for the separation, based on the colloid formation of Y in high alkaline pH, which can be filtered and separated from Sr, and subsequently dissolved in HCl. The objective of this work was the development of technologies for the preparation of 90 Sr/ 90 Y generators, and three technologies were developed: generators using cation resins columns, generators through colloid formation and electrochemical generators. Radionuclidic quality control of 90 Y was also evaluated by liquid scintillation, radionuclide identity, extraction paper chromatography (EPC) using complexing agents for 90 Y and by Optical Emission Spectrometry with Inductively Coupled Plasma (ICP-OES). The results showed that generators using cation resins have the best results related to the elution efficiency (∼83%), the reproducibility and radionuclidic purity. The electrochemical generator showed a potential for development, having the advantage of not suffering the effects of radiolysis of the pair 90 Sr/ 90 Y as the resin. A comparison and evaluation of the methods of the radionuclidic quality control showed that the EPC is very sensitive and allows for virtually instantaneous assessment of the quality of 90 Y generator. (author)

  13. Flow distribution experimental study on the emergency core cooling system of the IEA-R1m - IPEN-CNEN/SP - Brazil

    International Nuclear Information System (INIS)

    Torres, Walmir Maximo; Baptista Filho, Benedito Dias; Ting, Daniel Kao Sun

    1999-01-01

    This paper presents a brief description of Emergency Core Cooling System designed by the IEA-R1m Reactor and the experimental results of flow distribution over the core. Several parameters were evaluated, such as: relative position of spray header to the reactor core; type and quantity of spray nozzles; spray nozzles position on spray header; and total spray flow. The main conclusions are presented. (author)

  14. Production of 57Co, 109Cd, 111In and 117mSn using CV-28 cyclotron at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Osso, J.A. Jr.; Landini, L.; Lion, L.F.; Moraes, V.

    2001-01-01

    Full text: Several radioisotopes produced in Cyclotrons have physical properties of decay suitable to be used as: radiopharmaceuticals, for in vivo Diagnosis images (with the techniques of SPET and PET, Single Photon Emission Tomography and Positron Emission Tomography, respectively) and for Therapy, in Nuclear Medicine; calibration sources of several instruments applied in the nuclear area and in Metrology; and as radioactive tracers of elements investigated in many fields, such as Chemistry, Physics and Biology. This work describes the production of four of these radioisotopes that are very important in these areas: 57 Co, 109 Cd, 111 ln and 117m Sn. They can be obtained using the CV-28 Cyclotron at IPEN, because it can accelerate proton beams with energies up to 24MeV and currents up to 20μA (external). 57 Co (t 1/2 =271.3 d) decays by electron capture to 57 Fe with the emission of γ-rays and one characteristic X-ray. It is widely used as calibration source of detectors such as: Ge(Li), Ge(HP), Nal(TI) and dose calibrators (well type detectors). Besides these applications, 57 Co Flood Sources are used to test the response uniformity of gamma cameras, in Nuclear Medicine. 109 Cd has a half-life of 462.6 d and decays by electron capture to 109 Ag with the emission of one γ-ray and one characteristic X-ray. This radioisotope can be employed as calibration source of X-ray and γ-rays detectors; as a radioactive tracer of Cd, an environment pollutant and used in the EDXRF (Energy Dispersion X-Ray Fluorescence) technique. 57 Co was produced through the irradiation of nat Ni. Thick target yields for 55 Co, 56 Co, 57 Co, 58 CO, 56 Ni and 57 Ni were measured and the mean values were 346.69kBq/μA.h (9.37μCi/μA.h), for the direct production of 57 Co and 150.59kBq/μA.h (4.07μCi/μA.h), through the decay of 57 Ni (11.31 days after EOB - End of Bombardment). A solution of 57 CoCl 2 was prepared, to fill a flood source for calibration of gamma camera, with activity of 222MBq (6mCi) of 57 Co and impurity levels of 1.13 and 1.29% for 56 Co and 58 Co, respectively, at delivery time. In order to achieve these results, a chemical separation method was developed with a separation yield of 93% for 5 '7Co and a negligible loss of Ni. A composite target of Ni and Ag was prepared and a chemical separation method proposed to allow the separation between the targets and the products of interest, 57 Co and 109 Cd. The yields obtained in the irradiation of the composite target were: 947.94kBq/μA.h (25.62μCi/μA.h) of 57 Co - direct reaction, 259-00kBq/μA.h (7μCi/μA.h) of 57 Co - indirect reaction (11.31 days after EOB) and 71.41kBq/μA.h (1.93μCi/μA.h) of 109 Cd, which showed the efficiency of its use, as well as the chemical separation, with a yield of 80% for 57 Co and 109 Cd. 111 ln (t 1/2 =67.5 h) has appropriate characteristics for Diagnosis in Nuclear Medicine due to its decay mode (100% by electron capture) and its adequate half-life to slow biological studies, that makes it one of radioisotopes of interest of Brazilian Physicians. It can also be used in angular correlation studies in Nuclear Physics. 111 In was produced by the 112 Cd(p,2n) 111 ln reaction, that has the highest yield. The Cd targets were prepared by electroplating of CdSO 4 solution in copper and copper/nickel backings. After being irradiated, a chemical separation was performed by an acetic acid extraction method, with an overall recovery yield for 111 ln higher than 95%. The level of the chemical impurities of Cd, Ni and Cu were bellow than the permissible values. 117m Sn (t 1/2 =14 d) has suitable characteristics of decay to be used as a tracer of SnCl 2 in the labeling of organic molecules with 99m Tc and also in radiotherapeutical applications. It was prepared by the irradiation of natural tin through the nuclear reactions nat Sn(p,xn) 117 Sb→ 117m Sn. The production thick target yield of 117m Snnn was 784.4kBq/μA.h (21.20μCi/μA.h) and with the proper decay time of its precursor, 117 Sb, no radionuclidic impurities appeared in the final product. A chemical separation method was developed to separate first 117 Sb from the irradiated Tin and then 117m Sn from Sb with a good chemical yield. The quality control procedures showed the good quality of the final product, 117m Sn. (author)

  15. Study of the viability of the production of lutetium - 177 in the nuclear reactor IEA-R1 at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Silva, Giovana Pasqualini da

    2008-01-01

    The - emitter 177 Lu is a promising therapeutic radioisotope for the curative treatment of cancer using labelled proteins. It has a half - life of 6.71 day and maximum and average (3 energies of 421 and 133 keV, respectively, resulting in a short range of irradiation of tissue. The decay is accompanied by the emission of low energy -radiation of 208.3 keV (11%) and 113 keV (6.4%), suitable for simultaneous imaging. Lu can be produced by two different routes, namely, by irradiation of natural Lu 2 O 3 target ( 176 Lu, 2.6%) or enriched (in 176 Lu) Lu 2 O 3 target, and also by irradiation of Yb target (Yb 2 O 3 ) followed by radiochemical separation of Lu from Yb isotopes. The objective of this work is the development of a method of the production of 177 Lu through of the (n, gamma) nuclear reaction, by the direct and indirect method of production. Targets of lutetium oxide and ytterbium oxide were irradiated for evaluation of the activity produced and the chemical separation of lutetium and ytterbium was studied using different ion exchange resins. For the direct method, the best results were obtained using the target Lu 2 O 3 enriched in 39.6%. The best results for the indirect method were achieved with the process of separation using 0.25M - HlBA as eluent. The results showed that it is possible to produce 177 Lu of low specific activity for labeling molecules used for bone pain relief and in radiosynoviortesy. (author)

  16. Viability study of using the Laser-Induced Breakdown Spectroscopy technique for radioactive waste detection at IPEN-CNEN/SP, Brazil

    International Nuclear Information System (INIS)

    Tunes, Matheus A.; Schon, Claudio G.

    2013-01-01

    this work a viability study to apply the Laser-Induced Breakdown Spectroscopy (LIBS) technique for radioactive waste characterization was developed using a high power q-switched Nd:YAG rod-Laser, operating at 1064 nm with 9 ns of pulse-width and pulse-to-pulse energy around 10 to 20 mJ. When applied in a non-radioactive deionized water sample, our methodology exhibits a good potential to spectroscopy detection of Hydrogen species with resolution around 0.035 nm at full width at half maximum (FWHM). (author)

  17. Contribution of IPEN-CNEN/SP to the Seminar on Management Options for Low and Intermediate Level Wastes in Latin America

    International Nuclear Information System (INIS)

    1987-07-01

    The solutions adopted for management problems and radioactive wastes of nuclear installations and contamined materials generated in hospitals, research centers, laboratories in the countries of Latin America are presented. The criteria of site selection for radioactive waste installation and the methods for treating and storage are evaluated the results of inspections in installations which handle radioactive wastes are done (M.C.K.) [pt

  18. Relap4/SAS/Mod5 - A version of Relap4/Mod 5 adapted to IPEN/CNEN - SP computer center

    International Nuclear Information System (INIS)

    Sabundjian, G.

    1988-04-01

    In order to improve the safety of nuclear reactor power plants several computer codes have been developed in the area of thermal - hydraulics accident analysis. Among the public-available codes, RELAP4, developed by Aerojet Nuclear Company, has been the most popular one. RELAP4 has produced satisfactory results when compared to most of the available experimental data. The purposes of the present work are: optimization of RELAP4 output and messages by writing there information in temporary records, - display of RELAP4 results in graphical form through the printer. The sample problem consists on a simplified model of a 150 MW (e) PWR whose primary circuit is simulated by 6 volumes, 8 junctions and 1 heat slab. This new version of RELAP4 (named RELAP4/SAS/MOD5) have produced results which show that the above mentioned purposes have been reached. Obviously the graphical output by RELAP4/SAS/MOD5 favors the interpretation of results by the user. (author) [pt

  19. Current capabilities of the IRD-CNEN-RJ whole body counter for in vivo monitoring of internally deposited radionuclides in human body

    Energy Technology Data Exchange (ETDEWEB)

    Dantas, Bernando Maranhao; Dantas, Ana Leticia Almeida; Lucena, Eder Augusto, E-mail: bmdantas@ird.gov.br, E-mail: adantas@ird.gov.br, E-mail: eder@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. de Monitoracao In Vivo. Div. de Dosimetria

    2014-07-01

    Occupational exposure to radioactive materials may occur as a result of a variety of professional human activities, such as in nuclear industry; use of unsealed sources in nuclear medicine, biological research and agriculture; production of radiopharmaceuticals, as well as in mining and milling of minerals associated with naturally occurring radioactive materials. The IRD whole-body counter (UCCI) consists of a shielded room with internal dimensions of 2.5 m x 2.5 m x 2.5 m. The walls are made of steel and have a graded-Z interior lining made of 3 mm of lead, 1.5 mm of cadmium and 0.5 mm of copper. Such thin layers are aimed to reduce environmental sources of natural background radiation that would affect the measurements of radionuclides emitting low energy photons. An array of four HPGe detectors was used to perform low-energy measurements of radionuclides emitting photons in the energy range from 10 to 200 keV in the lungs, liver and bone tissue. Additionally, one NaI(Tl)8” x 4” and one NaI(Tl)3” x 3” scintillation detectors are used for measurements in the energy range from 100 up to 3000 keV. A configuration of detector supports allows setting up flexible counting geometries, i.e., whole body and specific organs such as head, lungs, liver and thyroid of an individual laid on a monitoring chair. The UCCI is able to perform in vivo measurement of a large variety of radionuclides emitting photons in the energy range from 10 to 3000 keV. The minimum detectable activities for most of the radionuclides of interest allow its application for occupational monitoring as well as in the case of accidental incorporations. (author)

  20. Country report: Brazil. Development of Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide Therapy at IPEN-CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    Osso, Jr., J. A.; Barrio, G.; Dias, C. R.B.R.; Brambilla, T. P.; Dantas, D. M.; Suzuki, K. N.; Barboza, M. F.S.; Bortoleti, E.; Fukumori, N. T.; Mengatti, J. [Radiopharmacy Center – Institute of Energetic and Nuclear Research – IPE N-CNEN/SP, São Paulo – Brazil (Brazil)

    2010-07-01

    The overall objective of this CRP is to develop radiopharmaceuticals for targeted therapy using {sup 188}Re and {sup 90}Y and to study the performance of generators with long lived parent radionuclides as well as to validate the QC control procedures for estimating the purity of generator eluents. The CRP is expected to enhance the capability in production of {sup 90}Y and {sup 188}Re radiopharmaceuticals to meet the increasing demand of therapeutic products for clinical applications, in particular in Brazil. In this period efforts were made towards the assembling of {sup 90}Sr-{sup 90}Y generators, quality control of {sup 90}Y, the labelling of DMSA(V) and anti-CD20 with {sup 188}Re and the labelling of Hydroxiapatite(HA) with {sup 90}Y. (author)

  1. Bituminization of simulated PWR type reactor wastes, boric evaporator bottons and ion exchange resins, carried out in CNEN/SP using commercial bitumen available in the Brazilian market

    International Nuclear Information System (INIS)

    Grosche Filho, C.E.; Chandra, U.

    1986-01-01

    The first results of the study of bituminization of simulated PWR wastes, boric evaporator bottons and spent ion-exclange resins (OH - , H + ) and incinerated ash-wates are presented and discussed. The study consisted of characterization of the commercial bitumen, locally available and bitumen wastes products of varying whight compositions. The characterization was carried out using standard analysis methods of ABNT and ASTM, and included measurement of, penetration, softening point and flash point. In addition, the bitumen samples were analized for their resin and asphaltene contents. For leaching studies, wastes products of bitumen and resin loaded with 134 Cs were utilized. The method used was according to the ISO norms. The simulation of the industrial process was carried out using an extruder-evaporator typically used in the plastic industries offered by Industria de Maquinas Miotto Ltda., Sao Bernardo do Campo - SP. (Author) [pt

  2. Study on routines and procedures of calibration of clinical dosemeter on gamma radiation beams at the IPEN-CNEN/SP, Brazil

    International Nuclear Information System (INIS)

    Damatto, Willian B.; Potiens, Maria da Penha A.; Santos, Gelson P.; Vivolo, Vitor

    2009-01-01

    The calibration consists in the comparison of the equipment to be calibrated with other equipment already calibrated by another standard, which means the equipment that will accomplish shall be considered secondary or tertiary, depending on the calibration that will be accomplished. As the clinical dosemeters are used for quality control services in the hospitals, these dosemeters need a reliable measurement precision. Therefore, this work intends to demonstrate the importance of the clinical dosemeter and the calibration, requiring special care face to all clinical set

  3. Quality control 201TlCl solution obtained at IPEN-CNEN/SP through the direct method of 201Tl preparation

    International Nuclear Information System (INIS)

    Fernandes, L.; Silva, C.P.G. da.

    1991-09-01

    The radiopharmaceutical 201 TlCl is used in Nuclear medicine for myocardial visualization. The solution of 201 TlCl was prepared using 201 Tl obtained by irradiating a natural mercury target with protons. This radionuclide was subjected to different quality control processes to verify the purity required for its use in Medicine. Some of these controls concerned the determination of 200 Tl, 201 Tl and 202 Tl; the chemical identification of 201 Tl +1 ; the hydrazine concentration, mercury contamination and the presence of phosphate. Furthermore, the biologic distribution in Wistar rats and tests for sterility, pyrogens and for toxicity were carried out. It was verified that the solution obtained was in the form of thallous chloride. This radiopharmaceutical can give a good heart image in animals but due to the contamination of 201 Tl with 200 Tl and 202 Tl its use in human beings is not possible unless enriched 202 Hg is used as target of irradiation. (author)

  4. Quality control of the solution sup(201)TlCl obtained at IPEN-CNEN/SP by sup(201)Tl direct preparation

    International Nuclear Information System (INIS)

    Fernandes, L.; Silva, C.P.G. da

    1991-01-01

    The radiopharmaceutical sup(201) TlCl is used in Nuclear Medicine for myocardial visualization. The solution of sup(201)TlCl was prepared using sup(201)Tl obtained by irradiating a natural mercury target with protons. This radionuclide was subjected to different quality control processes to verify the purity required for its use in Medicine. Some of these controls concerned the determination of sup(200)Tl, sup(201)Tl and sup(202)Tl; the chemical identification of sup(201)Tl sup(+1); the hydrazine concentration, mercury contamination and the presence of phosphate. Furthermore, the biologic distribution in Wistar rats and tests for sterility pyrogens and for toxicity were carried out. It was verified that the solution obtained was in the form of tallous chloride. This radiopharmaceutical can give a good heart image in animals but due to the contamination of sup(201)Tl with sup(200)Tl and sup(202)Tl its use in human beings is not possible unless enriched sup(202)Hg is used as target of irradiation. (author)

  5. Load and unload system optimization on H218 O irradiation target used for 18F- production at the cyclotron cyclone 30 from IPEN-CNEN/SP, Brazil

    International Nuclear Information System (INIS)

    Costa, Osvaldo Luiz da

    2009-01-01

    The demand growing in Brazil by the radiopharmaceutical [ 18 F] FDG in positron emission tomography (PET-CT) and the 109,7 minutes half life claim special attention to the productive chain of this radiopharmaceutical. Since the [ 18 O]water irradiation until the tomograph patient scanning, in sequential procedures that may spent about six hours, all the productive chain stages must be as reliable as possible, because any stage failed will be perceived in productive chain extremity. The position indication absence from Load and Unload 18 F - Target System valve in Cyclotron Accelerators Center resulted in 18 F - production loss, Irradiation Room contamination and the increase workers dose responsible by operation and maintenance of irradiation systems. This study tested the behaviour of three types of position sensors (micro switch, reed switch and inductive sensor), into Irradiation Room 1.2 environment of the Cyclotron Accelerators Center, where there are high gamma radiation and neutrons rates because the routine 18 F - and 123 I production, through this test was possible to discover the fitter position sensor to run on 18 F - Target, and after rewriting the programmable logic controller software was possible avoid this type of fail at 18 F - production time in Cyclotron Accelerators Center, and to grow up the reliability on [ 18 F]FDG productive chain. (author)

  6. Load unload system optimization on H218O irradiation target used for 18F- production at the cyclotron cyclone 30 from IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Costa, Osvaldo Luiz da

    2009-01-01

    The demand growing in Brazil by the radiopharmaceutical [ 18 F]FDG in positron emission tomography (PET-CT) and the 109,7 minutes half life claim special attention to the productive chain of this radiopharmaceutical. Since the [ 18 O]water irradiation until the tomograph patient scanning, in sequential procedures that may spent about six hours, all the productive chain stages must be as reliable as possible, because any stage failed will be perceived in productive chain extremity. The position indication absence from Load and Unload 18 F- Target System valve in Cyclotron Accelerators Center resulted in 18 F- production loss, Irradiation Room contamination and the increase workers' dose responsible by operation and maintenance of irradiation systems. This study tested the behaviour of three types of position sensors (micro switch, reed switch and inductive sensor), into Irradiation Room 1.2 environment of the Cyclotron Accelerators Center, where there are high gamma radiation and neutrons rates because the routine 18 F- and 1 '2 3 I production, through this test was possible to discover the fitter position sensor to run on 18 F- Target, and after rewriting the programmable logic controller software was possible avoid this type of fail at 18 F- production time in Cyclotron Accelerators Center, and to grow up the reliability on [ 18 F]FDG productive chain. (author)

  7. Analytical models for development of high performance metal targets irradiated in IPEN-CNEN/SP Cyclone 30 and Cyclone 18 cyclotrons

    International Nuclear Information System (INIS)

    Oliveira, Henrique Barcellos de

    2009-01-01

    Analytical models were developed that describe the basic elements for metal targets irradiation in cyclotrons. Important parameters such as maximum beam current value and thermal power deposited on target were obtained and compared with practical situations. In an unprecedented way, were determined analytically the features found in intense thermal transient situations, when high protons concentrations in a small region of the beam cause intense temperature gradients in small regions of the target. Comparing with results found in the literature showed that the developed models are satisfactory, in view of all limitations of the proposed model. (author)

  8. Radiometric survey of Radon-222 in Instituto de Engenharia Nuclear - IEN/CNEN-Brazil; Levantamento de radonio-222 no Instituto de Engenharia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gouvea, Vandir de Azevedo; Cardoso, Domingos d' Oliveira; Pedro, Carlos Roberto [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil). Div. de Seguranca e Radioprotecao]. E-mail: vandir@cnen.gov.br; Castro, Carlos Alberto Carvalho [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Dept. de Engenharia Nuclear

    2001-07-01

    The radioecological concentrations of Radon-222 indoor and outdoor nuclear facility of IEN, have been determined.The present study has established a radon investigation methodology in occupational areas, besides to suggest solutions for gas concentration minimization, in others work environment like to IEN.

  9. Logistics for evaluation of doses received by IOE due to handling 18FDG-radiopharmaceutical during processing (IEN/CNEN) and in radiodiagnostic (clinical)

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Osvaldir P. dos; Silva, Joao Carlos P.; Silva, Luiz Carlos Reina P.; Cortines, Geraldo, E-mail: osvaldir@ien.gov.br, E-mail: jcarlos@ien.gov.br, E-mail: reina@ien.gov.br, E-mail: gcortines@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The objective of this study is to propose an improvement in radiological practices involving production, transportation and application of radiopharmaceutical {sup 18}F, by tracking the radiation doses received by occupationally exposed individuals (OEI) that develop production practices, transportation and application of some patients in hospitals and clinics in Rio de Janeiro, the radiopharmaceutical {sup 18}FDG. In light of the results and observations of how these practices are developed, it's necessary to evaluate and suggest a logistics to minimize the doses received by OEI during these practices, seeking improvements in the actions and procedures for radiological protection. In practice the production of the radiopharmaceutical, the study focuses on the time of withdrawal of {sup 18}FDG cell processing, where the technician is exposed to higher dose rates. At this stage, we take to accomplish, yet two other reviews: the first is the placement of electronic dosimeters inside and outside the lead apron, whose objective is to assess the attenuation capacity of the apron. This last procedure refers to the use of a phantom cylindrical containing TLD 700 dosimeter in order to evaluate, using a mathematical model (MCNP), the doses ends (hand) of the technician, the process of removing the radiopharmaceutical of the cell and to compare the dosimetric dose recorded in the ring. Regarding the transport of {sup 18}FDG, we take into account the doses recorded in the cabin of the vehicle and the doses recorded in the dosimeter of the carrier. Finally, the doses received by health professionals who handle {sup 18}FDG are analyzed, since its withdrawal from the packing until administration to the patient. (author)

  10. Monitoring of the internal contamination through the in vivo measurements at the whole-body counting unity of the IRD-CNEN, Rio de Janeiro, Brazil; Monitoracao da contaminacao interna atraves de medicoes in vivo na unidade de contador de corpo inteiro do IRD-CNEN, Rio de Janeiro, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Dantas, Ana Leticia A.; Lucena, Eder A.; Dantas, Bernardo M., E-mail: adantas@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2009-07-01

    The present work approaches the capacity of Whole Body Counting Unity (WBCU) of IRD, Rio de Janeiro, Brazil, presenting the main parameters relative to the techniques of monitoring developed, and the available instrumentation for identification and quantification in vivo of radionuclides photon emitters with energies in the range of 10-3000 keV, incorporated by workers and public individuals

  11. Dosimetric quality of postal kit used for evaluation in IRD/CNEN of radiation protection parameters in dental radiology in the State of Rio de Janeiro; Qualidade dosimetrica do kit postal utilizado pelo IRD/CNEN para a avaliacao dos parametros de radioprotecao em radiologia odontologica no Estado do Rio de Janeiro

    Energy Technology Data Exchange (ETDEWEB)

    Coutinho, Soray Abbud; Mota, Helvecio C; Dovales, Ana Cristina M [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil). Dept. de Fisica Medica

    2001-07-01

    This work shows the results of a comparison between the skin entrance doses determined using an ionization chamber or a postal kit routinely used for the evaluation of radiation protection parameters in dental radiology in the state of Rio de Janeiro. By using the dosimetric kit, entrance skin dose is determined from two thermoluminescent dosimeters (TLDs) - previously calibrated in a {sup 137} Cs source - by using calibration factors determined in TLDs irradiated in air, on a water phantom and on an aluminium filter. The correspondence between the doses obtained with different methods was evaluated for three different X-ray spectra as radiation source. Results indicate that calibration factors used are adequate and that the kit has enough sensibility and reproducibility, measuring properly the skin entrance dose in dental X-rays. (author)

  12. Study of the viability of the production of lutetium - 177 in the nuclear reactor IEA-R1 at IPEN/CNEN-SP; Estudo da viabilidade de producao do lutecio - 177 no reator nuclear IEA-R1 do IPEN/CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Giovana Pasqualini da

    2008-07-01

    The {sup -} emitter {sup 177} Lu is a promising therapeutic radioisotope for the curative treatment of cancer using labelled proteins. It has a half - life of 6.71 day and maximum and average (3 energies of 421 and 133 keV, respectively, resulting in a short range of irradiation of tissue. The decay is accompanied by the emission of low energy -radiation of 208.3 keV (11%) and 113 keV (6.4%), suitable for simultaneous imaging. Lu can be produced by two different routes, namely, by irradiation of natural Lu{sub 2}O{sub 3} target ({sup 176}Lu, 2.6%) or enriched (in {sup 176}Lu) Lu{sub 2}O{sub 3} target, and also by irradiation of Yb target (Yb{sub 2}O{sub 3}) followed by radiochemical separation of Lu from Yb isotopes. The objective of this work is the development of a method of the production of {sup 177} Lu through of the (n, gamma) nuclear reaction, by the direct and indirect method of production. Targets of lutetium oxide and ytterbium oxide were irradiated for evaluation of the activity produced and the chemical separation of lutetium and ytterbium was studied using different ion exchange resins. For the direct method, the best results were obtained using the target Lu{sub 2}O{sub 3} enriched in 39.6%. The best results for the indirect method were achieved with the process of separation using 0.25M - HlBA as eluent. The results showed that it is possible to produce {sup 177} Lu of low specific activity for labeling molecules used for bone pain relief and in radiosynoviortesy. (author)

  13. Optimization of radiation protection for an electron accelerator used in paint cure in films approved by Brazilian Nuclear Energy Commission - CNEN, Rio de Janeiro, Brazil; Otimizacao da radioprotecao para um acelerador de eletrons usado em cura de tinta em filmes aprovado pela CNEN

    Energy Technology Data Exchange (ETDEWEB)

    Rios, Denise A. da S.; Sordi, Gian Maria A.A., E-mail: denise@inovafi.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2014-07-01

    This study aims to evaluate the radiological protection system in an installation where there is a self-shielded accelerator Category I, used for paint curing in polymer films, in order to optimize it in situations in which it is appropriate. For this a radiometric survey was conducted in the designated areas to check rate doses at different distances from the radiation focus, in which there is a possibility of presence or persons which can reliably detect any abnormality in the accelerator operation. The comparison of the obtained values related to the accelerator operating current with the natural background radiation showed that they are compatible, signaling that the principle of optimization is already being followed.

  14. Feasibility study of the implementation of a neutron beam from the cyclotron accelerator of the CRCN-NE/CNEN-PE; Estudo da viabilidade da implementação de um feixe neutrônico a partir do acelerador Cíclotron do CRCN-NE/CNEN-PE

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, W.G., E-mail: wellington.gandrade@gmail.com [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil). Dept. de Energia Nuclear; Vilela, E.C.; Lima, F.R.A., E-mail: ecvilela@cnen.gov.br, E-mail: falima@cnen.gov.br [Centro Regional de Ciências Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife-PE (Brazil)

    2017-07-01

    A cyclotron accelerator operating at the National Nuclear Energy Commission's facility is capable of accelerating protons up to 18 MeV and deuterons up to 9 MeV. This accelerator is equipped with channels used for the production of radiopharmaceuticals and an experimental research channel. This work studies the feasibility of implementing the neutron beam from this experimental channel, since other neutron generating sources are not able to provide a continuous and uniform flow of neutrons. Soon, a computational simulation with the code GEANT4 version 10.0.1.p03 was carried out using as data characteristics of this accelerator; primary beam of protons, energy in MeV and adopted as target Beryllium-9, which has a thickness of 2.5 mm. The generated neutrons were measured at a distance of 50 cm and under the angles of 0°, 15°, 30°, 45°, °, 70°, and 90°, with respect to the incident beam. The example was based on experimental studies and validated through the paired statistical method t as described in the literature. Thus, this work resulted in the assertion that it is possible to implement a monoenergetic neutron beam from an experimental channel of the cyclotron accelerator.

  15. Study of important parameters on the irradiation of {sup 124}Xe, to improve the production of {sup 123}I with high purity using the Cyclone-30 cyclotron at IPEN-CNEN/SP; Estudo de parametros relevantes na irradiacao de {sup 124}Xe, visando a otimizacao na obtencao de {sup 123}I ultra puro no ciclotron Cyclone-30 do IPEN-CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    Sumiya, Luiz Carlos do Amaral

    2006-07-01

    The development of diagnosis equipment and therapy procedures in nuclear medicine depends on the availability of commercial radioisotopes. IPEN is the most important institution that provides radioisotopes for national market. In order to achieve this function, IPEN had invested in the acquisition of a 30 MeV Cyclone-30 cyclotron to produce mainly {sup 18}F, {sup 67}Ga, {sup 201}Tl and {sup 123}I. The {sup 123}I production is the aim of the present work. With the {sup 123}I routine production data obtained by proton irradiation of Xe targets with an enrichment greater than 99.8%, it was possible to identify the important parameters that have direct influence on the production yield of high purity degree {sup 123}I. Even though the methodology for the commercial production of {sup 123}I, there are an scarcity of operational parameters data for this task. In this work the evaluated parameters were: {sup 124}Xe pressure, proton beam quality, irradiation time, operational temperature of the irradiation system under irradiation, waiting time to obtain {sup 123}I, temperature of washing solution and the impact of the internal Ni coating in the target. With the obtained results it was possible to modify the operational conditions for routine production and increasing the efficiency in about 30%. (author)

  16. Experiments by the Mexican NNEC on the Control of Airborne Radioactive Contamination; Experiencias Realizadas en la CNEN de Mexico Sobre El Control de Contaminaciones Radiactivas Arrastradas por el Aire

    Energy Technology Data Exchange (ETDEWEB)

    Bravo S, E. [Comision Nacional de Energia Nuclear, Mexico D.F. (Mexico)

    1968-12-15

    The installations of the Mexican National Nuclear Energy Commission have to deal with the problem of environmental contamination caused by dust and aerosols suspended in the air and originating mainly with such uranium-bearing ores as tyuyamunite, carnotite, betafite, technical-grade sodium uranate, ammonium uranate concentrate, uranium tetrafluoride and uranium dioxide. To prevent environmental contamination by these radioactive materials, the Commission has experimented with three different systems, based on the principle of extracting the dust from the environment, passing it through a cyclone system, separating the particles of larger size and controlling the small particles or aerosols by means of filtration, dilution in liquid columns and dilution in liquid curtains. On the basis of the results obtained, plans have been made for supplementing the systems with an adsorption column and an ion exchange column, depending on the specific requirements of each laboratory. (author) [Spanish] En las instalaciones de la Comision Nacional de Energia Nuclear de Mexico existe el problema de la contaminacion ambiental producida por polvos y aerosoles suspendidos en el aire, de minerales uraniferos tales como tyuyamunita, carnotita, betafita, uranato de sodio tecnico, concentrado de uranato de amonio, tetrafluoruro de uranio y bioxido de uranio fundamentalmente. Para evitar dicha contaminacion del medio ambiente con los materiales radiactivos mencionados, se han experimentado tres diferentes sistemas cuyo principio consiste en la extraccion de los polvos del medio ambiente, pasandolos a un sistema de ciclon, separando las particulas de mayor tamano y controlando las particulas pequenas o aerosoles por medio de filtracion, dilucion en columnas liquidas y dilucion en cortinas liquidas. Sobre la base de los resultados obtenidos se ha proyectado completar los sistemas de acuerdo a las necesidades especificas de cada laboratorio con una columna de adsorcion y otra de intercambio ionico. (author)

  17. Technical subsidies for the operation of IRD/CNEN emergency vehicles in the case of a nuclear accident at the Angra Nuclear Power Plant with associated radioactive releases to the atmosphere

    International Nuclear Information System (INIS)

    Leao, J.L.B.

    1982-03-01

    Technical support is provided for the operation of an emergency vehicle of Instituto de Radioprotecao e Dosimetria/Comissao Nacional de Energia Nuclear, Rio de Janeiro, Brazil, in the event of uncontrolled release of radioactivity from the Angra Nuclear Power Plant (NPP) to the atmosphere. It is based on internationally adopted emergency decision process philosophy, the concept of 'Protective Action Guide' (PAG), the exposure pathways relevant to nuclear accidents, the measuring systems to be used in obtaining the exposure rate in the effluent 'plume', the methods utilized to predict dose to the population, radioiodine suppression measures, the monitoring instrumentation available to the emergency group, some post-accident considerations and finally, the monitoring that may be carried out from an aircraft. Information is given about the NPP operator's responsabilities with respect to the prediction of the consequences of an accident, as well as methods for thyroid and whole body dose estimation based on exposure to the radioiodine and noble gases present in the effluent plume. The example of the Three Mile Island's incident is used to formulate some observations regarding collective dose to the public estimates derived from measurements made from a helicopter. (Author) [pt

  18. Assessment of the occupational exposure of the workers involved in the {sup 123}I production at the IEN/CNEN-RJ; Avaliacao da exposicao ocupacional dos trabalhadores envolvidos na producao de {sup 123}I no IEN

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Francisco de

    2005-07-01

    {sup 123}I is a gamma emitter used for diagnosis in Nuclear Medicine. Since 1998 it is produced in the Institute of Nuclear Energy (IEN) and supplied to the Clinics and Hospitals located in the city of Rio de Janeiro. The annual production is in the approximately of 0,74 TBq (20 Ci), which represents a risk of external and internal exposure to the workers involved in this activity. A survey of external doses in the period of 1994 to 2004 was carried out based on the individual registries available in the CONEXO Data Base operated by the Institute of Radiation Protection and Dosimetry (IRD). It was verified an increase of the external exposure associated to the production curve. However, the individual doses are all bellow the annual limits established by the regulatory board. On the other hand, the variation of doses among individuals involved in the same tasks suggests the possibility of optimization of procedures. Regarding internal exposure it was calculated a decision factor above 1mSv for the practice, which justifies the need for internal monitoring. An evaluation of the process based on the results of in vivo thyroid monitoring in the period of 2000 to 2004 was carried out to identify the steps which represent higher risk of internal exposure. The available data indicate that the laboratory of quality control is the critical step in terms of internal contamination. This conclusion can be justified by the high volatility of iodine which is manipulated in the form of a liquid open source during this step. With the aim of optimizing monitoring procedures for the control of occupationally exposed workers in the production of {sup 123}I, in vivo and in vitro bioassay methods were developed to identify and quantify internal contamination by such radionuclide, using the detection systems available at the Bioassay Laboratory and at the In Vivo Measurements Laboratory. The techniques developed present sensitivity compatible with the derived registry level associated to the committed effective dose equivalent of 1mSv. It was also established a methodology for the interpretation of bioassay data using the software AIDE. The methods developed in this work can be used to implement improvements in the radiation protection program of the IEN. It is suggested to increase the frequency of in vivo measurements and to include in vitro bioassay in the monitoring program, which will permit a better evaluation of the internal doses of the workers(author)

  19. Personnel dosimetry of extremities by using Harshaw rings XD-100 at Centro Regional de Ciencias Nucleares, CRCN, Brazilian CNEN; Dosimetria pessoal de extremidades utilizando aneis Harshaw XD-100 no Centro Regional de Ciencias Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Ricardo de Andrade; Vilela, Eudice; Nogueira, Maria do Socorro; Ferreira Filho, Alfredo Lopes; Castro, Walber Amorim [Centro Regional de Ciencias Nucleares (CRCN), Recife, PE (Brazil)]. E-mail: ral@elogica.com.br

    2000-07-01

    Data concerning calibration and type tests of an extremity system based on XD100 rings (Harshaw) are presented. Dosemeter used is a thermoluminescent chip inserted in a sealed pouch and was read out using a Harshaw 6600 reader. The dosimetric system complied with all ISO/DIS 12794-1 draft report suggested tests, in which this work was based on. This work obtained results point to the applicability of those recommendations to Brazilian institutes and suggest its adoption by the national regulatory commission. (author)

  20. Individual performance evaluation of the Brazilian Nuclear Energy Commission (CNEN): a meta-evaluative study; Avaliação de desempenho individual da Comissão Nacional de Energia Nuclear: um estudo meta-avaliativo

    Energy Technology Data Exchange (ETDEWEB)

    Bezerra, Leonardo Ferreira

    2017-07-01

    The present study is a summative meta-evaluation that had as objective to evaluate the quality of the process of evaluation of individual performance of the servers of the National Commission of Nuclear Energy, being guided by the scientific curiosity to know to what extent the evaluation of performance the National Commission for Nuclear Energy meets the quality standards disseminated by the Joint Committee on Standards for Educational Evaluation. The methodology chosen to be used was based on the management approach and had as a guiding principle of the study the elaboration of a framework of criteria considering the aforementioned standards. The criteria established in the criteria framework guided the preparation of the items of the questionnaire sent to the National Commission of Nuclear Energy servers. In addition to the questionnaire, the observation of this author was considered in the context where the phenomenon occurred, which allowed a better reflective analysis of the data collected by the questionnaire. Regarding the results, it can be inferred that the performance evaluation developed at the National Commission of Nuclear Energy can be considered of quality, highlighting the servers' trust for the data, the communication process of the program stages, the credibility of the evaluators, the process of negotiation of goals and adaptability of the instrument over the course of the cycle. However, there are some opportunities for improvement, considering the relevance of evaluation as a tool to improve the performance of the autarchy's servers. Among the points that need to be improved is that there is currently a lack of knowledge about the legal basis and justification of the process of evaluation process by the servers and the lack of clarity regarding the content of the final evaluation report. Among the recommendations of this study, one can consider as the most relevant the need to: disseminate the results of this meta-evaluation to the servers; promotion of meetings to raise awareness of the importance of evaluation, explaining its legal basis, justifications; and qualification of the National Commission of Nuclear Energy people management area evaluators in order to pass them through specialization processes in the field of individual performance appraisal. (author)

  1. The influence of the calibration standard and the chemical composition of the water samples residue in the counting efficiency of proportional detectors for gross alpha and beta counting. Application on the radiologic control of the IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Santos, Cecilia Martins

    2003-01-01

    In this work the efficiency calibration curves of thin-window and low background gas-flow proportional counters were determined for calibration standards with different energies and different absorber thicknesses. For the gross alpha counting we have used 241 Am and natural uranium standards and for the gross beta counting we have used 90 Sr/ 90 Y and 137 Cs standards in residue thicknesses ranging from 0 to approximately 18 mg/cm 2 . These sample thicknesses were increased with a previously determined salted solution prepared simulating the chemical composition of the underground water of IPEN The counting efficiency for alpha emitters ranged from 0,273 +- 0,038 for a weightless residue to only 0,015 +- 0,002 in a planchet containing 15 mg/cm 2 of residue for 241 Am standard. For natural uranium standard the efficiency ranged from 0,322 +- 0,030 for a weightless residue to 0,023 +- 0,003 in a planchet containing 14,5 mg/cm 2 of residue. The counting efficiency for beta emitters ranged from 0,430 +- 0,036 for a weightless residue to 0,247 +- 0,020 in a planchet containing 17 mg/cm 2 of residue for 137 Cs standard. For 90 Sr/ 90 Y standard the efficiency ranged from 0,489 +- 0,041 for a weightless residue to 0,323 +- 0,026 in a planchet containing 18 mg/cm 2 of residue. Results make evident the counting efficiency variation with the alpha or beta emitters energies and the thickness of the water samples residue. So, the calibration standard, the thickness and the chemical composition of the residue must always be considered in the gross alpha and beta radioactivity determination in water samples. (author)

  2. Study of important parameters on the irradiation of 124Xe, to improve the production of 123I with high purity using the Cyclone-30 cyclotron at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Sumiya, Luiz Carlos do Amaral

    2006-01-01

    The development of diagnosis equipment and therapy procedures in nuclear medicine depends on the availability of commercial radioisotopes. IPEN is the most important institution that provides radioisotopes for national market. In order to achieve this function, IPEN had invested in the acquisition of a 30 MeV Cyclone-30 cyclotron to produce mainly 18 F, 67 Ga, 201 Tl and 123 I. The 123 I production is the aim of the present work. With the 123 I routine production data obtained by proton irradiation of Xe targets with an enrichment greater than 99.8%, it was possible to identify the important parameters that have direct influence on the production yield of high purity degree 123 I. Even though the methodology for the commercial production of 123 I, there are an scarcity of operational parameters data for this task. In this work the evaluated parameters were: 124 Xe pressure, proton beam quality, irradiation time, operational temperature of the irradiation system under irradiation, waiting time to obtain 123 I, temperature of washing solution and the impact of the internal Ni coating in the target. With the obtained results it was possible to modify the operational conditions for routine production and increasing the efficiency in about 30%. (author)

  3. Health requirements for nuclear reactor operators

    International Nuclear Information System (INIS)

    1980-05-01

    The health prerequisites established for the qualification of nuclear reactor operators according to CNEN-NE-1.01 Guidelines Licensing of nuclear reactor operators, CNEN-12/79 Resolution, are described. (M.A.) [pt

  4. Law 5.877 of May 11, 1973

    International Nuclear Information System (INIS)

    1973-01-01

    Authorize the Brazilian Nuclear Energy Commission (CNEN) to pay up partially the subscribed authorized social capital of the Companhia Brasileira de Tecnologia Nuclear (CBTN) - Brazilian Nuclear Technology Company

  5. Law 5.877 of May 11, 1973; Lei no. 5.877 de 11 de Maio de 1973

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-05-11

    Authorize the Brazilian Nuclear Energy Commission (CNEN) to pay up partially the subscribed authorized social capital of the Companhia Brasileira de Tecnologia Nuclear (CBTN) - Brazilian Nuclear Technology Company.

  6. Law 5.740 of December 1, 1971; Lei no. 5.740 de 1 de Dezembro de 1971

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-12-01

    Authorizes the Brazilian Nuclear Energy Commission (CNEN) to create the joint stock company Companhia Brasileira de Tecnologia Nuclear (CBTN) - Brazilian Nuclear Technology Company -, and makes additional providence.

  7. Report to the 12th. Meeting of the Brazil-FRG Mixed Commission

    International Nuclear Information System (INIS)

    1983-01-01

    This report presents the main agreements between the Governments of the Federal Republic of Germany for Nuclear Research and Technology Development Cooperative Program, including the CNEN-FRG cooperation activities during 1982 and the CNEN-FRG proposed cooperation program for 1983. (E.O.)

  8. The radiological accident in Goiania 10 years later: an evaluation; 10 anos do acidente radiologico de Goiania: uma reflexao

    Energy Technology Data Exchange (ETDEWEB)

    Nouailhetas, Yannick; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle. Diretoria de Radioprotecao e Seguranca Nuclear

    1997-12-31

    This article presents a reflection on the impact on the population of the actions taken in the city of Goiania, following the 137-Cs accident and the biological fundamental on which this actions should be based upon. (author) 16 refs.; yannick at cnen.gov.br; axavier at cnen.gov.br

  9. Industrial radiation protection: what it is happening

    International Nuclear Information System (INIS)

    Endo, M.

    1988-01-01

    This paper presents the standard NE-06.04 of CNEN (Comissao Nacional de Energia Nuclear - Brazil) about open and close industrial radiography installations licensing. This review does not substitute CNEN-6/73 resolution, only specificy in details, how those installations must actuate with reference to the company radiation protection plan. (C.M.) [pt

  10. Model for the elaboration of program of environmental radiological monitoring reports

    International Nuclear Information System (INIS)

    2005-11-01

    This Regulation refers to the requirements of the Regulation CNEN-NN.3.01 'Basic Guidelines for Radiation Protection', expressed in the section 5.14, and its application related to the emission of reports of Environmental Radiological Monitoring Program to be submitted to CNEN evaluation

  11. Technology development for producing nickel metallic filters

    International Nuclear Information System (INIS)

    Hubler, C.H.

    1990-01-01

    A technology to produce metallic filters by Instituto de Engenharia Nuclear (IEN-Brazilian CNEN) providing the Instituto de Pesquisas Energeticas e Nucleares (IPEN-Brazilian CNEN) in obtaining nickel alloy filters used for filtration process of uranium hexafluoride, was developed. The experiences carried out for producing nickel conical trunk filters from powder metallurgy are related. (M.C.K.)

  12. Law no. 10.308 of 20th November, 2001 on radioactive waste repositories siting, construction, licensing, operation, inspection, costs, indemnity, civil liability and guarantees concerning to the radioactive wastes repositories and other provisions

    International Nuclear Information System (INIS)

    2001-01-01

    This Act was published on November 20, 2001 and set forth regulations on the final disposal of radioactive wastes produced in Brazil, including siting, construction, licensing, operation, inspection, costs, indemnities, civil liability and guarantees concerning to the radioactive wastes repositories. This act allows for installation and operation of initial, intermediary and final repositories in accordance with the criteria established by the Brazilian Nuclear Energy National Commission - CNEN. The person or organization granted with CNEN authorization for operation of the initial repositories shall be liable for personal, patrimony and environmental radiological damages. The civil liability of CNEN is concerned to the radioactive waste intermediary and final disposals and transportation

  13. Radiological risk associated with a fire scenario in a radioactive waste deposit

    Energy Technology Data Exchange (ETDEWEB)

    Domingos, E.N.; Lima, Z.R. de, E-mail: erica.ndomingos@gmail.com, E-mail: zelmolima@yahoo.com.br [Instituto de Engenharia Nuclear (PPGIEN/IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Aguiar, L.A., E-mail: aguiar.lais@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro-RJ (Brazil)

    2017-07-01

    A fire at the disposal of radioactive waste can result in significant damage, as well as serious risks to the environment and the health of the general public. The norms of CNEN (Comissão Nacional de Energia Nuclear), CNEN 2.03; CNEN 2.04 and CNEN 8.02 include fire protection regulations and have criteria and requirements that aim to prevent the occurrence, neutralize the action and minimize the effects of the fire on the radioactive and/or toxic mate-rial present in the installations. For decision making due to a fire scenario containing radioactive material, it is fundamental to have information that can allow the estimate of the dose to which the population will be submitted. This work proposes to identify the radiological risk of cancer in the respiratory system using the BEIR V model, associated with a fire scenario containing radioactive material generated in the Hotspot code. (author)

  14. The licensing of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    In Brazil the governmental organization responsible for the licensing of NPPs is the Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body. A description of CNEN's organization, responsabilities and working methods, as well as the present situation of the Brazilian NPPs undergoing licensing, has recently been presented. In this paper the experience gained by CNEN in the course of licensing Brazilian NPPs Units I and II is discussed. CNEN's present day technical competence and its future trends are analysed with regard to in-house capacity, foreign consultants and research contracts with Brazilian Universities. Finally, the immediate need for a Safety research programm in support of licensing is discussed. Manpower needs and major areas for such a programm are also indicated. (orig./RW)

  15. Technical standards in nuclear area

    International Nuclear Information System (INIS)

    Grimberg, M.

    1978-01-01

    The technical standardization in nuclear area is discussed. Also, the competence of CNEN in standardization pursuit is analysed. Moreover, the process of working up of technical standards is explained; in addition, some kinds of technical standards are discussed. (author) [pt

  16. Licensing for the construction of 'Almirante Alvaro Alberto' nuclear power plant

    International Nuclear Information System (INIS)

    1974-09-01

    The BRAZILIAN NUCLEAR ENERGIA COMMISSION (Comissao Nacional de Energia Nuclear - CNEN) presents in Report n 0 51 of its Reactors Department all the requirements for the construction permit of 'Almirante Alvaro Alberto' Nuclear Power Plant [pt

  17. Protection actions and intervention criteria at emergency situations

    International Nuclear Information System (INIS)

    2005-11-01

    This Regulation refers to the requirements of the Regulation CNEN-NN.3.01, 'Basic Act of Radiological Protection', as expressed in the section 6.3, and its application to the intervention on emergency situations

  18. I sup(123) target transfer system

    International Nuclear Information System (INIS)

    Almeida, G.L. de; Rautenberg, F.A.

    1986-01-01

    The construction of target transfer system using a robot into hot cell of IEN cyclotron (Brazilian-CNEN) for sup(123)I production is presented. The system operation is described, and the advantages are shown. (M.C.K.)

  19. Evaluation of tests for coastdown of reactor coolant flow and measure of primary circuit flow of Angra-1 nuclear power plant

    International Nuclear Information System (INIS)

    Galetti, M.R.S.; Camargo, C.T.M.; Pontedeiro, A.C.

    1987-05-01

    The Angra 1 Nuclear Power Plant first reload license was issued after several technical discussions among CNEN, FURNAS and KWU. During the license process CNEN has established that the plant could return to anormal operation if the requirements described in the letter CNEN-DExL-C 06/86 were satisfied. The requirements according to the CNEN Transient and Thermohydraulic Group Analysis were to do again the following tests: 'Primary Flow Measurement' to check if the excess flow measured in the first cycle was held; and Pump Coastdown' to check if the Westinghouse and KWU fuel elements are thermo-hydraulicaly compatibles during transients. The mixed core must keep at least the same safety margin presented on Angra 1 FSAR for the original core. The tests and the analysis of results are described. (Author) [pt

  20. Out-of-pile simulation experiments and theoretical analysis on sodium fuel interaction

    International Nuclear Information System (INIS)

    Conti, M.; Luigi, G. Di; Federico, A.; Mennini, G.; Scarano, G.; Tavano, F.

    1978-01-01

    Activities on fuel coolant interaction are being carried out since many years at C.N.E.N. in the frame of the Italian Fast Reactor Program. This paper describes the experimental and theoretical results recently obtained. (author)

  1. Nuclear Power Plant (NPP) safety in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    The multidisciplinary aspects of the activities involved in the nuclear power plant (NPP) licensing, are presented. The activities of CNEN's technical staff in the licensing of Angra-1 and Angra-2 power plants are shown. (E.G.) [pt

  2. Comparison between Brazilian radiation protection standard and the recommendation of the International Commission on Radiological Protection published in 2007

    International Nuclear Information System (INIS)

    Pereira, W.S.; Kelecom, A.; Pereira, J.R.S.

    2015-01-01

    This study aims to evaluate the differences between the CNEN's standard and the publication of ICRP-103, analyzing the philosophy for radiation protection, dose limits and other relevant aspects of radiation protection

  3. Comparison between Brazilian radiation protection standard and the recommendation of the International Commission on Radiological Protection published in 2007; Comparacao entre a norma brasileira de radioprotecao e a recomendacao da International Commission on Radiological Protection - ICRP, publicadas em 2007

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, W.S. [Industrias Nucleares do Brasil (INB), Itatiaia, RJ (Brazil). Fabrica do Combustivel Nuclear. Servico de Radioprotecao; Kelecom, A. [Universidade Federal Fluminense (LARARA-PLS/GETA/UFF), Niteroi, RJ (Brazil). Grupo de Estudos em Temas Ambientais. Lab. de Radiobiologia e Radiometria Pedro Lopes dos Santos; Pereira, J.R.S. [Universidade Veiga de Almeida (UVA), Rio de Janeiro, RJ (Brazil). Curso de Graduacao em Direito

    2015-07-01

    This study aims to evaluate the differences between the CNEN's standard and the publication of ICRP-103, analyzing the philosophy for radiation protection, dose limits and other relevant aspects of radiation protection.

  4. Control of nuclear material specified equipment and specified material

    International Nuclear Information System (INIS)

    1982-04-01

    The goal and application field of NE 2.02 regulatory guide of CNEN (Comissao Nacional de Energia Nuclear), are described. This regulatory guide is about nuclear material management, specified equipment and specified material. (E.G.) [pt

  5. Authorization for the functioning of service laboratories for personal monitoring

    International Nuclear Information System (INIS)

    1981-10-01

    The requirements of the Brazilian CNEN (Comissao Nacional de Energia Nuclear) are established for the construction licensing and operation authorization of laboratories offering personnel monitoring services for external exposures to X-and gamma radiation. (I.C.R.) [pt

  6. Radioactive wastes and residues: government participation in a control policy

    International Nuclear Information System (INIS)

    Gelli, Guido

    1993-01-01

    This paper discusses the politic aspects of the State participation in inspection and control of the radioactive wastes residues with the supervise of Brazilian Nuclear Energy Commission (CNEN), by a national program

  7. The function of specialized organization in work safety engineering for nuclear installations

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1989-01-01

    The attributions of Brazilian CNEN in the licensing procedures of any nuclear installation are discussed. It is shown that the work safety engineering and industrial safety constitute important functions for nuclear safety. (M.C.K.) [pt

  8. The protection and the preservation of the environment the Brazilian nuclear law

    International Nuclear Information System (INIS)

    Faria, N.M. de; Goes Fischer, M.D. de; Rocha, L.M.G. da; NUCLEBRAS, Rio de Janeiro; Associacao Brasileira de Direito Nuclear, Rio de Janeiro)

    1981-01-01

    A set of Brazilian rules governing the protection and the preservation of the environment in relation to nuclear activities is presented. The role of CNEN, as an institution that defends the environment is also mentioned. (A.L.) [pt

  9. Program of environmental radiological monitoring

    International Nuclear Information System (INIS)

    2005-11-01

    This Regulation refers to the requirement of the Regulation CNEN-NN.3.01, 'Basic Act of Radiological Protection', as expressed in the section 5.14, related to the Program of Environmental Radiological Monitoring (PMRA)

  10. Actualization of the Brazilian nuclear regulations

    International Nuclear Information System (INIS)

    Wieland, Patricia; Soares, Abner Duarte; Nogueira, Tindyua de Moraes; Monteiro, Iara Arraes; Pitta, Maria Adelia Rocha; Bruno, Natanael Carvalho; Pereira, Enneite Souza; Pinto, Marvio dos S.; Lidington, Regina Marcia Rocha; Rocha, Marco Aurelio Toledo

    2011-01-01

    The present work has the objective of making public the methodological approach adopted by the Brazilian Nuclear Energy Commission (CNEN) to create a nuclear normative structure up-dated and coherent. According to the Law 4118/62, 6189/74 and 7781/89, is the attribution the CNEN to establish specific guidelines for nuclear safety and radiological protection, and also do dictate safety norms through the emission of Resolutions

  11. Actualization of the Brazilian nuclear regulations; Atualizacao das normas nucleares brasileiras

    Energy Technology Data Exchange (ETDEWEB)

    Wieland, Patricia; Soares, Abner Duarte; Nogueira, Tindyua de Moraes; Monteiro, Iara Arraes; Pitta, Maria Adelia Rocha; Bruno, Natanael Carvalho; Pereira, Enneite Souza; Pinto, Marvio dos S.; Lidington, Regina Marcia Rocha; Rocha, Marco Aurelio Toledo, E-mail: pwieland@cnen.gov.b, E-mail: asoares@cnen.gov.b, E-mail: tnogueira@cnen.gov.b, E-mail: iara@cnen.gov.b, E-mail: mpitta@cnen.gov.b, E-mail: nbruno@cnen.gov.b, E-mail: espereira@cnen.gov.b, E-mail: marvio@cnen.gov.b, E-mail: , E-mail: rmliding@cnen.gov.b, E-mail: mtoledo@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Div. de Normas

    2011-10-26

    The present work has the objective of making public the methodological approach adopted by the Brazilian Nuclear Energy Commission (CNEN) to create a nuclear normative structure up-dated and coherent. According to the Law 4118/62, 6189/74 and 7781/89, is the attribution the CNEN to establish specific guidelines for nuclear safety and radiological protection, and also do dictate safety norms through the emission of Resolutions

  12. Labeling and quality control of 123I-MIBG

    International Nuclear Information System (INIS)

    Figols de Barboza, Marycel Rosa

    2002-01-01

    This report describes a method to facilitate routine production of 123 I-MIBG in Radiopharmacy Centre of IPEN-CNEN/SP. Iodine-123 radioisotope is produced in the form of sodium iodide in Cyclone-30 (IBA) at IPEN-CNEN/SP through proton irradiation of gaseous 124 Xe target. The labelling procedure uses MIBG-sulphate and leads to 123 I-MIBG with radiochemical purity at least 98% and specific activity of 300-380 MBq/mg

  13. Cheralite quartzides in Itiuba mountains-Bahia, Brazil

    International Nuclear Information System (INIS)

    Gorsky, E.; Gorsky, V.A.

    1974-01-01

    Quartzitic pebbles of anomalous radioactivity were found by the geologists of the 'Comissao Nacional de Energia Nuclear' of Brazil (CNEN) in November 1964 in the Vicinity of Santa Rosa, municipality of Jaguarari, Bahia. A radioactive anomaly of large extension was subsequently localized by scintilometric prospecting in February 1965 over precambrian quartzites on Morro do Barbosa (near Santa Rosa). Samples of the radioactive rocks were investigated by the Mineralogical-Petrographical Section of the CNEN. The results of the investigation are reported

  14. From Electron Beams to Photon Beams

    International Nuclear Information System (INIS)

    Ranieri, Alberto

    2015-01-01

    n this article I try to report at the best the events and the emotions I experienced, together with my colleagues, when I was a young researcher working at the Frascati Center of CNEN. In the middle of 70’s the high energy physics activities carried out in Frascati were transferred from CNEN to INFN (Istituto Nazionale Fisica Nucleare) and the personnel had the chance to chose to continue to work at the CNEN (obviously in a different research field) or to continue to work in high energy physics, but at the INFN. I decided to remain at the CNEN and, consequently, I had to change my research activity. I moved from the high energy accelerators research field to the lasers research field in which, at that time at the CNEN, a new interesting project on “uranium laser isotope separation” was just starting. This article is focused on the theoretical and experimental development activity, carried out in the years 70’s-80’s at the CNEN Frascati Center, on a quite particular kind of laser to be utilized in that project. In this laser the active medium is not made of atoms or molecules but is a beam of free electrons running along a spatially periodic magnetic structure: this laser is the “Free Electron Laser” [it

  15. Control of sealed sources and equipments used in gammagraphy

    International Nuclear Information System (INIS)

    Sahyun, A.; Sordi, G.-M.A.A.; Biazzini Filho, F.L.

    1988-01-01

    The Radiation Protection Department of the IPEN-CNEN/SP, in 1987, formed a section incharged to control all radioactive material: a) received by the IPEN-CNEN/SP; b) produced by the IPEN-CNEN/SP; c) delivered from the IPEN-CNEN/SP. The aim of this section is to maintain a permanent control of all radioactive sources movement got at the IPEN-CNEN/SP. This control is performed with a microcomputer, trademark MICRODIGITAL, model TK3000 //e, 256 KBytes of memory, utilizing the TOTALWORKS program. This program permits to have the origin, characteristics and address of the radioactive sources, its sites in the IPEN, its uses, etc. Already we have put in the microcomputer, the control of the sealed sources produced used in nondestructive test, the inspection control of the gamagraphy irradiator and the control of the depleted sources. The next step is to introduce in the computer the inspection of the remote control of the irradiator. The aim of this paper is to describe the control program that was already put on. This radioactive material control was started with the sealed sources used in gamagraphy because we believe that is the field with the most likelihood of accident in the population, and therefore it's that need the most hard control about the site and the performance of the irradiation facility. (author) [pt

  16. Study of virtual reality application in training programs on nuclear technology; Estudo da aplicacao de realidade virtual em programas de treinamento sobre tecnologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pastura, Valeria da Fonseca e Silva

    2016-07-01

    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master's thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the RV technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author)

  17. Study of the application of virtual reality in programs training on nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Pastura, Valéria da F. e S.; Mol, Antonio Carlos de A. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Siqueira, Ana Paula L. de, E-mail: vpastura@ien.gov.br, E-mail: mol@ien.gov.br, E-mail: analegey@hotmail.com [Centro Universitário Carioca (UniCarioca), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the VR technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author). (author)

  18. Study of the application of virtual reality in programs training on nuclear technology

    International Nuclear Information System (INIS)

    Pastura, Valéria da F. e S.; Mol, Antonio Carlos de A.; Siqueira, Ana Paula L. de

    2017-01-01

    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the VR technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author). (author)

  19. Study of virtual reality application in training programs on nuclear technology

    International Nuclear Information System (INIS)

    Pastura, Valeria da Fonseca e Silva

    2016-01-01

    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master's thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the RV technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author)

  20. Accreditation of professionals for radiological protection in medical and dental radiology at Minas Gerais, Brazil

    International Nuclear Information System (INIS)

    Silva, Teogenes A. da; Pereira, Elton G.; Alonso, Thessa C.; Guedes, Elton C.; Goncalves, Elaine C.; Nogueira, Maria Angela A.

    2000-01-01

    The role of the CDTN/CNEN as far as the radiological protection services in the medical and dental radiology has changed a lot due to the new Regulatory Directives. The CDTN/CNEN was recognized as the regional reference center for providing not only radiological survey services, but to coordinate an accreditation procedure for professional persons to be accepted by the State Regulatory Authorities to work at Minas Gerais. All the new activities were formalized in a Cooperation Agreement between the CDTN/CNEN and the Regulatory Authority. This paper describes the accreditation procedure for candidates, the adopted requirements, the intercomparison results among measuring instruments and the main achievements during the first year of the Agreement. (author)

  1. Assignment of Responsibilities in the Management of Scrap Metal in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Costa, E.L., E-mail: evaldo@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro (Brazil)

    2011-07-15

    This paper gives an overview of the activities of the National Commission of Nuclear Energy (CNEN), as the Brazilian regulatory authority responsible for licensing, inspecting, controlling and regulating all practices involving sources of ionizing radiation. The activities of the main departments of CNEN responsible for taking care of the practices and sources are described, especially those related to orphan sources and radioactive material in scrap metal. Finally, although Brazil does not yet have the necessary infrastructure to take care of the scrap metal issue, through the joint action of the relevant departments of CNEN it is hoped that the appropriate steps can be taken to build a national protocol, following the examples of other countries, especially Spain. (author)

  2. Act No 84 of 5 March 1982 amending Act No 1240 of 15 December 1971 concerning the restructuring of the Comitato Nazionale per l'Energia Nucleare

    International Nuclear Information System (INIS)

    1982-01-01

    This Act amended substantially Act No. 1240 of 1971 restructuring the Comitato Nazionale per l'Energia Nucleare - CNEN. The amendments concern the reorganisation of the CNEN into a new body, the National Commission for Research and Development of Nuclear and Alternative Energy Sources (ENEA), which in addition to nuclear energy, will also be responsible for R and D in alternative energy sources, with the exception of hydrocarbons. In order to facilitate the ENEA's tasks, the new Act gives it a great degree of flexibility and administrative autonomy. The staff of ENEA will also be granted a legal status closely related to that of the industrial sector. It will also retain temporarily the previous CNEN's regulatory tasks in nuclear safety and radiation protection. (NEA) [fr

  3. Evaluation of occupational radiation dose of extremities on hysterosalpingography

    International Nuclear Information System (INIS)

    Filipov, D.; Kotowski, S.T.A.

    2017-01-01

    In the Hysterosalpingography (HSG) exam there is always a professional present with their hands very close to the radiation field. Based on CNEN, individuals occupationally exposed to radiation have equivalent dose limit values for the extremities (500 mSv / year). The objective of the study was to verify the equivalent dose in the hand region of an IOE (Occupationally Exposed Individual) that performs the HSG test and to compare it with the CNEN limit and with similar studies. A humanoid phantom was used to simulate the patient and an ionization chamber, which was placed in the place commonly occupied by the professional. The equivalent hand dose result (∼ 30 mSv / year) equals 6% of the CNEN annual dose limit, but is close to most studies using fluoroscopes. Therefore, the optimization of radiological protection is necessary to reduce these results

  4. The experience on public consultation in the elaboration of nuclear regulations

    International Nuclear Information System (INIS)

    Monteiro, Iara A.; Pitta, Maria Adelia R.; Pereira, Enneite S.; Wieland, Patricia

    2009-01-01

    This paper presents and discusses the process of public consultation followed by the regulatory body, Nuclear Energy National Commission (CNEN), during the elaboration of nuclear regulations. In this paper, the due legislation on federal administration, law n. 9784/99, is referred to and the procedures established by CNEN for the elaboration of a nuclear regulation are described. The public consultation has the objective of improving the democratization of nuclear regulations elaboration process, allowing the participation of interested parties such as professional associations directly involved, organizations interested in its application and the general public. During the process of elaboration of a nuclear regulation, the basic text is, first of all, discussed and improved by a task group. This group is composed by CNEN's officials and representatives of organizations, enterprises and public agencies involved in the related area. Once the first version of the proposed regulation is ready, it is formally open to consultation and posted at CNEN website for a period of time. The suggestions, therein presented on-line, are analyzed by the task group and the conclusions are also posted at the site; those considered pertinent are incorporated to proposed regulation. As an example, the public consultation results obtained in 2008 with the revision of the CNEN-NN-6.02: Licensing of Radioactive Facilities regulation, are presented. Such results cover two aspects: the analysis of the participants profile and the analysis of the contributions. Public participation in the elaboration of nuclear regulations is a new way for CNEN to know the licensees and public demands, doubts and needs. This tool has demonstrated usefulness and therefore must be maintained by the regulatory body. (author)

  5. Evaluation of the BPW34 photodiode response in quality of RQR radiation of the regulation IEC 61267 implanted at the IPEN and CRCN-NE, Brazil; Avaliacao da resposta do fotodiodo BPW34 em qualidades de radiacao RQR da norma IEC 61267 implantadas no IPEN e no CRCN-NE

    Energy Technology Data Exchange (ETDEWEB)

    Magalhaes, Cinthia M.S. de; Santos, Luiz A.P. dos; Santos, Marcus A.P. dos, E-mail: lasantos@cnen.gov.b, E-mail: masantos@cnen.gov.b [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil); Caldas, Linda V.E., E-mail: lcaldas@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Souza, Divanizia do N., E-mail: divanizi@ufs.b [Universidade Federal de Sergipe (UFS), Aracaju, SE (Brazil). Dept. de Fisica

    2011-10-26

    This paper evaluated the answer of two commercial BPW34 photodiodes in four RQR radiation qualities implanted, in accordance with the regulation IEC 61267, at the laboratory of the instrument calibrations of the Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN) and radiation metrology laboratory of Northeastern Centro Regional de Ciencias Nucleares (CRCN-NE/CNEN). The results have shown that is possible to relate the qualities implanted at those laboratories and that the BPW34 photodiode can be useful for comparative evaluations of distinct qualities of radiodiagnostic beams

  6. Historical survey of the qualifying process of Furnas calculus methodology in the areas of rods, neutronics, thermohydraulic accidents and transients

    International Nuclear Information System (INIS)

    Conti, C.F.S.; Silva Galetti, M.R. da.

    1990-02-01

    As Furnas intends to assume in the future the responsibility of performing Safety Analyses associated to Reload and Operation questions to Angra 1, it was figured out the necessity of qualifying its methodology by CNEN. The Methodology Qualification Process is based on guidelines proposed by CNEN at NT-DR-N o 02/87, where it was divided in four steps. This Technical Note aims to present the follow up of FURNAS Methodology Qualification Process and to bring it up to date in the areas of Core Physics (Neutronics), Core Thermal-Hydraulics, Fuel Rod Behaviour, Transient and Large Break Loss of Coolant Accident Analyses (LBLOCA). (author)

  7. The founders of the ININ

    International Nuclear Information System (INIS)

    Bulbulian, S.

    2006-01-01

    The Mexican government sent the constituent law of the National Commission of Nuclear Energy (CNEN) at December 31, 1955. This classification enters in validity the January 1, 1956. However the Commission began to work in the last months 1956. This institution development two main activities: 1. A program of training on techniques with radioisotopes and nuclear instrumentation and 2. The creation of specialized programs and laboratories. Very important persons in the CNEN were the members of the Commission, the Dr. Manuel Sandoval Vallarta, the Dr. Nabor Carrillo Flores and the Atty. Jose Maria Ortiz Tirado, President of this institution. (Author)

  8. Waste management of the Nuclear Technology Development Center - CDTN

    International Nuclear Information System (INIS)

    Miaw, S.T.W.; Oliveira Lopes, M.J. de; Tello, C.C.O. de; Silva, E.M.P. da; Guzella, M.F.R.; Reis, L.C.A.; Menezes Cussiol, N.A. de

    1993-01-01

    Liquid and solid wastes of low radiation level are produced at the Nuclear Technology Development Centre (CDTN). Trying to minimise the waste volume and to give proper treatment, the wastes, are segregated at their origin according their radiological, chemistry and physical characteristics. The Radioactive Waste Program was established in 1983 based on CNEN resolution 6/73 and more recently modernized following CNEN Norm NE-6.05. This paper describes all activities involved in CDTN's Program. (B.C.A.). 6 refs, 02 tabs, 01 fig

  9. Triennial technical report - 1986, 1987, 1988 - Instituto de Engenharia Nuclear (IEN) -Dept. of Reactors (DERE)

    International Nuclear Information System (INIS)

    1989-01-01

    The research activities developed during the period 1986, 1987 and 1988 by the Reactor Department of Brazilian Nuclear Energy Commission (CNEN-DERE) are summarized. The principal aim of the Department of Reactors is concerned to the study and development of fast reactors and research thermal reactors. The DERE also assists the CNEN in the areas related to analysis of power reactor structure; to teach Reactor Physics and Engineering at the University, and professional training to the Nuclear Engineering Institute. To develop its research activity the DERE has three big facilities: Argonauta reactor, CTS-1 sodium circuit, and water circuit. (M.I.)

  10. The founders of the ININ; Los fundadores del ININ

    Energy Technology Data Exchange (ETDEWEB)

    Bulbulian, S [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2006-07-01

    The Mexican government sent the constituent law of the National Commission of Nuclear Energy (CNEN) at December 31, 1955. This classification enters in validity the January 1, 1956. However the Commission began to work in the last months 1956. This institution development two main activities: 1. A program of training on techniques with radioisotopes and nuclear instrumentation and 2. The creation of specialized programs and laboratories. Very important persons in the CNEN were the members of the Commission, the Dr. Manuel Sandoval Vallarta, the Dr. Nabor Carrillo Flores and the Atty. Jose Maria Ortiz Tirado, President of this institution. (Author)

  11. Reminiscences of Goiania ten years later: the psychological effects

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, A B [Rio de Janeiro (Brazil)

    1998-12-01

    The author recalls her experiences during the follow-up of the radiological accident in Goiania, Brazil, in 1987, when a {sup 137}Cs capsule was removed from an abandoned radiotherapy clinic. At the time of the accident she was employed by the Brazilian Nuclear Energy Commission`s (CNEN) Department of Human Resources Management as a psychologist. She describes the emotional impact suffered by the victims, the population, the medical care team and the staff of emergency responders of CNEN as they decontaminated the city and cared for the victims. The author puts forward proposals for psychological preparedness for radiological emergencies and nuclear accidents. (author)

  12. Reminiscences of Goiania ten years later: the psychological effects

    International Nuclear Information System (INIS)

    Carvalho, A.B.

    1998-01-01

    The author recalls her experiences during the follow-up of the radiological accident in Goiania, Brazil, in 1987, when a 137 Cs capsule was removed from an abandoned radiotherapy clinic. At the time of the accident she was employed by the Brazilian Nuclear Energy Commission's (CNEN) Department of Human Resources Management as a psychologist. She describes the emotional impact suffered by the victims, the population, the medical care team and the staff of emergency responders of CNEN as they decontaminated the city and cared for the victims. The author puts forward proposals for psychological preparedness for radiological emergencies and nuclear accidents. (author)

  13. Proceedings of the 28 sup(th) congress

    International Nuclear Information System (INIS)

    1974-10-01

    The occurrence of geologic deposits of uranium and other radioactive minerals in different regions of Brazil, and the state of prospecting in such areas are discussed. Projects carried out or to be developed by CNEN (Brazilian Nuclear Energy Commission) in this field, are also mentioned [pt

  14. Standard model for safety analysis report of hexafluoride power plants from natural uranium

    International Nuclear Information System (INIS)

    1983-01-01

    The standard model for safety analysis report for hexafluoride production power plants from natural uranium is presented, showing the presentation form, the nature and the degree of detail, of the minimal information required by the Brazilian Nuclear Energy Commission - CNEN. (E.G.) [pt

  15. Standard model for safety analysis report of fuel fabrication plants

    International Nuclear Information System (INIS)

    1980-09-01

    A standard model for a safety analysis report of fuel fabrication plants is established. This model shows the presentation format, the origin, and the details of the minimal information required by CNEN (Comissao Nacional de Energia Nuclear) aiming to evaluate the requests of construction permits and operation licenses made according to the legislation in force. (E.G.) [pt

  16. Standard model for safety analysis report of fuel reprocessing plants

    International Nuclear Information System (INIS)

    1979-12-01

    A standard model for a safety analysis report of fuel reprocessing plants is established. This model shows the presentation format, the origin, and the details of the minimal information required by CNEN (Comissao Nacional de Energia Nuclear) aiming to evaluate the requests of construction permits and operation licenses made according to the legislation in force. (E.G.) [pt

  17. Conception of the Instrument Calibration Laboratory of Ionizing Radiation Measurement (LACIMRI) of CTMSP - Sao Paulo, SP

    International Nuclear Information System (INIS)

    Silva, Raimundo Dias da; Kibrit, Eduardo

    2009-01-01

    The present work describes the phases of implantation of calibration laboratory of ionizing radiation measurement instruments at the CTMSP, Sao Paulo, in a priory approved by CNEN, Brazil. That laboratory will allow and enhance the present metrological capacity for the attendance to the growing demand for calibration services of the instruments

  18. Considerations on radiation protection and accidents in nuclear medicine

    International Nuclear Information System (INIS)

    Lima, Carla Flavia de; Avelar, Artur Canella; Campos, Tarcisio P.R.

    2001-01-01

    The present study presents the radiation protection in the services of nuclear medicine in relation to the design of the services, manipulation of sources, cares with the patient, accomplishment of procedures and definition of accidents and incidents; besides approaching the CNEN requirements

  19. Evaluation of the environmental equivalent dose rate using area monitors for neutrons in clinical linear accelerators; Avaliacao da taxa de equivalente de dose ambiente utilizando monitores de area para neutrons em aceleradores lineares clinicos

    Energy Technology Data Exchange (ETDEWEB)

    Salgado, Ana Paula; Pereira, Walsan Wagner; Patrao, Karla C. de Souza; Fonseca, Evaldo S. da, E-mail: asalgado@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Batista, Delano V.S. [Instituto Nacional do Cancer (INCa), Rio de Janeiro, RJ (Brazil)

    2009-07-01

    The Neutron Laboratory of the Radioprotection and Dosimetry Institute - IRD/CNEN, Rio de Janeiro, Brazil, initiated studies on the process of calibration of neutron area monitors and the results of the measurements performed at radiotherapy treatment rooms, containing clinical accelerators

  20. Maintenance of medical nuclear equipment. A proposal for quality control in radiotherapy

    International Nuclear Information System (INIS)

    Becker, Paulo H.B.

    1996-01-01

    A project of quality control in radiotherapy that is been implemented by Instituto de Radioprotecao e Dosimetria from Brazilian National Energy Commission (CNEN) in cooperation with International Atomic Energy Agency is described. The establishment of a laboratory for the maintenance of medical dosemeters is proposed

  1. Room for iodo therapy

    International Nuclear Information System (INIS)

    Pinto, A.L.A.; Derivi, A.; Bacelar, A.; Ramos, F.R.; Dias, T.M.; Baptista, I.S.

    1996-01-01

    A description of rules to assemble, to install and to maintain a room for iodo therapy is presented. The necessities of the patients and procedures to meet the norms of radiologic protection established by the Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil) are highlighted

  2. Safety and radiation protection in mining and milling facilities

    Energy Technology Data Exchange (ETDEWEB)

    Magalhaes, Maisa H.; Schenato, Flavia; Cruz, Paulo R., E-mail: maisahm@cnen.gov.br, E-mail: schenato@cnen.gov.br, E-mail: pcruz@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Xavier, Ana M., E-mail: axavier@cnen.gov.br [Comissao Nacional de Energia Nuclear (ESPOA/CNEN-RS), Porto Alegre, RS (Brazil). Escritorio de Porto Alegre

    2011-07-01

    Federal Legislation in Brazil establishes that the Brazilian Nuclear Energy Commission - CNEN - is responsible for the surveillance of the industrialization of nuclear ores and the production and commerce of nuclear materials in such way that activities such as buying, selling, import and export, are subject to previous licensing and surveillance. Regulation CNEN-NN-4.01 on Safety and Radiation Protection in Mining and Milling Facilities of conventional ores containing naturally occurring radioactive materials, NORM, was issued in 2004 establishing both a methodology for classification of these facilities into three Categories, taking into account both the contents of uranium and thorium in the ores and the applicable radiation and safety requirements based on a graded approach. Although the lack of a licensing process in the above mentioned Regulation made its implementation a difficult task, CNEN, by means of an initial survey, identified ca. 30 mining and milling industries of conventional ores containing uranium and thorium with concentrations above 10 Bq/g. More recently, a new juridical understanding of the legislation concluded that CNEN must issue licences and authorizations for the possession and storage of all ores with uranium and thorium concentrations above exemption levels. A proper surveillance programme encompassing 13 of these mining facilities was then put forward aiming at the improvement of their safety and radiation protection. This article presents an overview of NORM exploitation in Brazil and put forward suggestions for achieving viable solutions for the protection of workers, general public and environment from the effects of ionizing radiation. (author)

  3. IEN Low-level-radioactive waste Management

    International Nuclear Information System (INIS)

    Rocha, A.C.S. da; Pina, J.L.S.; Silva, S. da; Silva, J.J.G.

    1986-01-01

    The control, treatment and disposal of the low-level radioactive waste produced in the units of IEN-CNEN, in Brazil are presented, in details. These wastes are generated from a particle accelerator (CV-28 cyclotron), radiochemistry laboratories and a nuclear research reactor (Argonaut type). (Author) [pt

  4. Proposal of a research and development program for cerebral tumor treatment by neutron capture

    International Nuclear Information System (INIS)

    Silva, M.M. da

    1992-01-01

    The researches related to the Boron Neutron Capture Therapy, that were developed at Nuclear Energetic Institute (IPEN/CNEN-SP) and the Coordination for Special Projects (COPESP) are described. A coordinate development program is presented for constructing of an installation, with the purpose of routine utilization of this technique. (C.G.C.)

  5. French position paper on sodium fires, design and testing

    International Nuclear Information System (INIS)

    Malet, J.C.; Casselman, C.; Charpenel, J.; Duverger de Cuy, G.; Rzekiecki, R.; Dufresne, J.; Lo Pinto, P.; Montaignac de; Herault, A.

    1983-01-01

    This document gives an up-to-date account of studies carried out in France in the fields of sodium fires, extinction, filtration and prefiltration of aerosols originating from a sodium fire, and of sodium concrete reactions. It also indicates how the CEA, in collaboration with the CNEN, intends to deal with scale effects. (author)

  6. Nuclear energy: Brazilian Nuclear Program behind the scenes and the reflections in the national society and economy

    International Nuclear Information System (INIS)

    Grippi, Sidney

    2006-01-01

    The nuclear energy in the world, the Brazilian nuclear program, the industrial and social risks of nuclear segment, 20th century and the radiation accidents, the ionizing radiation effects in living beings, radioactive wastes, the Earth Letter and a list of CNEN regulations are presented

  7. Act no. 933 of 11 August 1960. Establishment of the National Nuclear Energy Commission

    International Nuclear Information System (INIS)

    1960-01-01

    This Act which sets up the Comitato Nazionale per l'Energia Nucleare (CNEN) abolishes at the same time the National Committee for Nuclear Research (Comitato nazionale per le ricerche nucleari). This present Act No. 933 was subsequently annulled by Act No. 1240 of 15 December 1971 with the exception of Sections 12 to 16 which remained valid. (NEA) [fr

  8. Radiation protection and safety for final disposal of radioactive wastes stored in Abadia de Goias, Brazil

    International Nuclear Information System (INIS)

    1991-01-01

    This standard aims to satisfy the radiation protection and safety conditions required by Brazilian Nuclear Energy Commission (CNEN) for final disposal of radioactive wastes stored in Abadia de Goias. These wastes are products of the accident happened in 1987 caused by the Cs-137 source violation. (M.V.M.)

  9. Metrology Department - DEMET

    International Nuclear Information System (INIS)

    1989-01-01

    In this report are presented the activities and purposes of the Metrology Dept. of the Institute of Radioprotection and Dosimetry of Brazilian CNEN. It is also presented a list of services rendered by that Dept., the projects in course, personnel and publications.(J.A.M.M.)

  10. Environmental and Radiological Protection Department - DEPRA

    International Nuclear Information System (INIS)

    1989-01-01

    The activities and purposes of the Environmental and Radiological Protection Dept. of the Institute of Radioprotection and Dosimetry form Brazilian CNEN are presented. It is also presented an historical review of its activities, its personnel and its sections. (J.A.M.M.)

  11. Uranium prospecting in the State of Bahia, Brazil

    International Nuclear Information System (INIS)

    Cenachi, N.C.

    1974-01-01

    A brief description is made of the program established by CNEN (Brazilian Nuclear Energy Commission) - Brazil, for the radiogeological survey of a large area in the state of Bahia. Details of the projects carried out since 1971 are also given. Projects of aerogeophysical surveys are also mentioned [pt

  12. Survey of legal aspects, regulations, standards and guidelines applicable to radioactive waste management of the Brazilian Multipurpose Reactor - RMB

    International Nuclear Information System (INIS)

    Salvetti, T.C.; Marumo, J.T.

    2017-01-01

    In Brazil, the Brazilian Nuclear Energy Commission (CNEN) and Brazilian Institute of Environment and Renewable Natural Resources (IBAMA) are the agencies responsible for the execution, regulation and control of nuclear and environmental policies, respectively. Such regulatory activities are very comprehensive (IBAMA) or too specific (CNEN), revealing other aspects that would, also, need to be observed so that the management could be carried out efficiently (quality) and effectively (safety), including the three governmental administrative levels: Federal, State and Municipal. In addition to laws, regulations, decrees and resolutions, there are also national and international standards and guides that provide guidelines for structuring the current management and the use of best regulatory practices. The Brazilian Multipurpose Reactor Enterprise (RMB) is a CNEN project, complying with a Multi-Year Plan of the Brazilian Ministry of Planning, Development and Management (MPDG). The Enterprise is being developed under the responsibility of the Directorate of Research and Development - DPD of CNEN and will have a facility for treatment and initial temporary storage of the radioactive waste generated by the operation of the research reactor and the activities carried out in the associated laboratories. The RMB will be built in the city of IPERÓ, located in the state of São Paulo, near ARAMAR Experimental Center of the Brazilian Navy. This work aims to present the research results regarding the various aspects that regulate, legislate and standardize the practices proposed to the Radioactive Waste Management of the RMB project. (author)

  13. Radiation quantities and units

    International Nuclear Information System (INIS)

    2013-01-01

    This fifth chapter presents the conceptual evolution, the definition procedures, the radiological quantities themselves, the relation between them, the new operational quantities and the new quantities defined in the ICRP 60 that replaced ICRP 26 and was included in the CNEN-NN-3.01 standard of 2011

  14. Evolution of nuclear security regulatory activities in Brazil

    International Nuclear Information System (INIS)

    Mello, Luiz A. de; Monteiro Filho, Joselio S.; Belem, Lilia M.J.; Torres, Luiz F.B.

    2009-01-01

    The changing of the world scenario in the last 15 years has increased worldwide the concerns about overall security and, as a consequence, about the nuclear and radioactive material as well as their associated facilities. Considering the new situation, in February 2004, the Brazilian National Nuclear Energy Commission (CNEN), decided to create the Nuclear Security Office. This Office is under the Coordination of Nuclear Safeguards and Security, in the Directorate for Safety, Security and Safeguards (Regulatory Directorate). Before that, security regulation issues were dealt in a decentralized manner, within that Directorate, by different licensing groups in specific areas (power reactors, fuel cycle facilities, radioactive facilities, transport of nuclear material, etc.). This decision was made in order to allow a coordinated approach on the subject, to strengthen the regulation in nuclear/radioactive security, and to provide support to management in the definition of institutional security policies. The CNEN Security Office develops its work based in the CNEN Physical Protection Regulation for Nuclear Operational Units - NE-2.01, 1996, the Convention on the Physical Protection of Nuclear Material and the IAEA Nuclear Security Series . This paper aims at presenting the activities developed and the achievements obtained by this new CNEN office, as well as identifying the issues and directions for future efforts. (author)

  15. User manual of FRAPCON-I computer code

    International Nuclear Information System (INIS)

    Chia, C.T.

    1985-11-01

    The manual for using the FRAPCON-I code implanted by Reactor Department of Brazilian-CNEN to convert IBM FORTRAN in FORTRAN 77 of Honeywell Bull computer is presented. The FRAPCON-I code describes the behaviour of fuel rods of PWR type reactors at stationary state during long periods of burnup. (M.C.K.)

  16. Transport of radioactive materials

    International Nuclear Information System (INIS)

    2013-01-01

    This ninth chapter presents de CNEN-NE--5.01 norm 'Transport of radioactive material'; the specifications of the radioactive materials for transport; the tests of the packages; the requests for controlling the transport and the responsibilities during the transport of radioactive material

  17. Law 6.189 of December 16, 1974

    International Nuclear Information System (INIS)

    1974-01-01

    Modifies Law 4.118 of Aug 27, 1962 and Law 5.740 of Dec 1, 1971, which create respectively, Brazilian Nuclear Energy Commission (CNEN) and Brazilian Company of Nuclear Technology (CBTN), henceforth designated by Empresas Nucleares Brasileiras Sociedade Anonima (NUCLEBRAS) - Brazilian Nuclear Technology Corporation - and makes additional providence

  18. Numerical investigation of the High Temperature Reactor (VHTR) using computational fluid dynamics; Investigacao numerica do Reator de Alta Temperatura (VHTR) utilizando fluidodinamica computacional

    Energy Technology Data Exchange (ETDEWEB)

    Pinto, Joao Pedro C.T.A.; Santos, Andre A. Campagnole dos; Mesquita, Amir Z., E-mail: jpctap@cdtn.br, E-mail: aacs@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG),Belo Horizonte, MG (Brazil). Lab. de Termo-Hidraulica

    2013-07-01

    This work consists to evaluate and continue the study that is being developed in the Laboratory of Thermo-Hydraulics of the CNEN/CDTN (Centro de Desenvolvimento da Tecnologia Nuclear), aiming to validate the methods and procedures used in the numerical calculations of fluid flow in fuel elements of the core of the VHTR.

  19. Bruno Touschek e l'arte della fisica

    CERN Document Server

    Agapito, Enrico

    2007-01-01

    Bruno Touschek, nato a Vienna nel 1921 e morto a Igls, in Austria, nel 1978, fu il fisico che nel 1960 progettò e portò a compimento, la costruzione di AdA, il primo Anello di Accumulazione di materia e antimateria (elettroni e positroni), presso i Laboratori del CNEN di Frascati.

  20. Environmental aspects at radiological protection in ArcelorMittal Monlevade

    International Nuclear Information System (INIS)

    Silva Filho, Cleber Marques; Soares Filho, Mauricio; Franco, Jose Otavio Andrade; Leite, Roberto Paulo; Goncalves, Breno Cunha; Costa, Jose Gustavo de Souza

    2010-01-01

    ArcelorMittal Monlevade Environmental Management of Radiological Protection is based on radiological protection team training, start up of radioactivity materials detection equipment in several steps of industrial processes and internal procedures according to CNEN - Nuclear Energy National Commission guidelines. At this way ArcelorMittal Monlevade seeks to guarantee the safety of employees, community, customers, equipment and the environment and their business. (author)

  1. Distribution of nuclear medicine service in Brazil

    International Nuclear Information System (INIS)

    Silva, Ana Carolina Costa da; Duarte, Alessandro; Santos, Bianca Maciel dos

    2011-01-01

    The Brazil does not posses a good distribution of nuclear medicine service por all his territory. This paper shows the difference among country regions as far the number of clinics of nuclear medicine as is concerning, and also doctors licensed in the area and radioprotection supervisors, both licensed by the Brazilian Nuclear Energy Commission (CNEN)

  2. Conception of the Instrument Calibration Laboratory of Ionizing Radiation Measurement (LACIMRI) of CTMSP - Sao Paulo, SP; Concepcao do Laboratorio de Calibracao de Instrumentos de Medicao de Radiacao Ionizante (LACIMRI) do CTMSP, Sao Paulo, SP

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Raimundo Dias da; Kibrit, Eduardo, E-mail: raimundo@ctmsp.mar.mil.b, E-mail: kibrit@ctmsp.mar.mil.b [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil)

    2009-07-01

    The present work describes the phases of implantation of calibration laboratory of ionizing radiation measurement instruments at the CTMSP, Sao Paulo, in a priory approved by CNEN, Brazil. That laboratory will allow and enhance the present metrological capacity for the attendance to the growing demand for calibration services of the instruments

  3. Regulatory activities in reactor safety

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1987-01-01

    The safety phylosophy in designs and operation of nuclear power plants and, the steps for evaluating the safety and quality assurance, in the licensing procedure are described. The CNEN organization structure and the licensing procedure for nuclear power plants in Brazil are presented. (M.C.K.) [pt

  4. Personnel Monitoring Department - DEMIN

    International Nuclear Information System (INIS)

    1989-01-01

    The activities and purposes of the Personnel Monitoring Dept. of the Institute of Radioprotection and Dosimetry of the Brazilian CNEN are presented. A summary of the personnel monitoring service is given, such as dosemeters supply, laboratorial inspections, and so on. The programs of working, publishing, courses and personnel interchange are also presented. (J.A.M.M.)

  5. Activities of Brazilian Nuclear Energy Commission in the field of nuclear power plant licesing

    International Nuclear Information System (INIS)

    Alves, R.N.

    1986-01-01

    The objectives, the procedures and the ways of implementation of measures aiming at safety use of nuclear energy are presented. The juridical aspects in the licensing area and the regulatory activities used by CNEN. The description of nuclear power plants and the methodology used in studies of environmental protection and radiation protection are presented [pt

  6. Radiography with neutrons: use in inspection of hydrogenated materials

    International Nuclear Information System (INIS)

    Pugliesi, R.; Assuncao, M.P.M.

    1989-01-01

    Neutron radiography technique is used for showing the viability of inspecting hydrogenated materials. The experimental disposition is installed in irradiation radial channel n. 10 from IEA-R1 (IPEN-CNEN-SP). The inspetionated materials were munitions for gun and rifle. (C.G.C.)

  7. Operation reports of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    The requirements aiming to standardize the program of nuclear power plant operation report, required by Brazilian Energy Commission - CNEN - to evaluate the activities related to the nuclear technical safety and to the radiation protection during the units operational phase, are showed. (E.G.) [pt

  8. Industrial irradiators and its radioprotection. 1. ed.; Irradiadores industriais e sua radioprotecao

    Energy Technology Data Exchange (ETDEWEB)

    Rodrigues Junior, Ary de Araujo

    2014-06-01

    The book contains 9 chapters and an appendix section related to: 1) A little bit of radiation physics and radiation protection. 2) Radiators. 3) Safety. 4) Maintenance. 5) Training. 6) Accidents. 7) Transport and load of radioactive material. 8) Final thinking about safety. 9) Issues specific tests of the Brazilian Nuclear Energy Commission - CNEN.

  9. Inspection of the brazilian nuclear regulatory body in the area of radiotherapy. A critical analysis

    International Nuclear Information System (INIS)

    Brito, Ricardo Roberto de Azevedo

    2005-01-01

    The National Commission of Nuclear Energy (CNEN) is responsible in Brazil for the activities of licensing and control of radioactive installations in the radiotherapy medical area. The majority of these activities are developed by CNEN Co-ordination of Radioactive Installations (CORAD). One of the necessary stages for the development of licensing and control activities is the inspection of radiotherapy services (clinics and hospitals). Almost all of these inspections are carried out by CNEN Inst. of Radiation Protection and Dosimetry (IRD), through its Service of Medical Physics in Radiotherapy and Nuclear Medicine (SEFME). This work makes a survey of the main nonconformities found during ten years of inspections in radiotherapy services (1995 - 2004) and analyses the efficiency of these inspections in making the radiotherapy services develop their activities according to the norms in vigour in the country and adopt corrective actions against, at least, the nonconformities evidenced by CNEN inspectors. Additionally, it analyses the possibility of improvement and / or the optimisation of the process, through a procedure able to be unified and controlled, aiming a prompt communication to those involved in the licensing process (SEFME and CORAD) about the attendance by the radiotherapy services to the non-conformity items observed during the inspection. (author)

  10. Survey of legal aspects, regulations, standards and guidelines applicable to radioactive waste management of the Brazilian Multipurpose Reactor - RMB

    Energy Technology Data Exchange (ETDEWEB)

    Salvetti, T.C.; Marumo, J.T., E-mail: salvetti@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    In Brazil, the Brazilian Nuclear Energy Commission (CNEN) and Brazilian Institute of Environment and Renewable Natural Resources (IBAMA) are the agencies responsible for the execution, regulation and control of nuclear and environmental policies, respectively. Such regulatory activities are very comprehensive (IBAMA) or too specific (CNEN), revealing other aspects that would, also, need to be observed so that the management could be carried out efficiently (quality) and effectively (safety), including the three governmental administrative levels: Federal, State and Municipal. In addition to laws, regulations, decrees and resolutions, there are also national and international standards and guides that provide guidelines for structuring the current management and the use of best regulatory practices. The Brazilian Multipurpose Reactor Enterprise (RMB) is a CNEN project, complying with a Multi-Year Plan of the Brazilian Ministry of Planning, Development and Management (MPDG). The Enterprise is being developed under the responsibility of the Directorate of Research and Development - DPD of CNEN and will have a facility for treatment and initial temporary storage of the radioactive waste generated by the operation of the research reactor and the activities carried out in the associated laboratories. The RMB will be built in the city of IPERÓ, located in the state of São Paulo, near ARAMAR Experimental Center of the Brazilian Navy. This work aims to present the research results regarding the various aspects that regulate, legislate and standardize the practices proposed to the Radioactive Waste Management of the RMB project. (author)

  11. Dose coefficients for public exposition; Coeficientes de dose para exposicao ao publico

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This Regulation refers to the requirements of the Regulation CNEN-NN.3.01 'Basic Guidelines for Radiation Protection', to be applied to the dose calculus with the objective of verification according to the limits and restrictions of dose and reference levels of the public individuals, expressed in its section 5

  12. Management of radioactive wastes at nuclear power plants

    International Nuclear Information System (INIS)

    2008-03-01

    This Regulation refers to the requirements of the Regulation CNEN-NE.1.26, 'Safety Operation of Nuclear Power Plants', as expressed in the section 13, specifically in the subsection 13.4, relatives to the management of radioactive wastes at nuclear power plants

  13. Criteria for calculation of effective dose from the individual monitoring; Criterios para calculo de dose efetiva a partir da monitoracao individual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-11-15

    This Regulation refers to the requirements of the Regulation CNEN-NN.3.01. 'Basic Act of Radiological Protection', as expressed in the section 5.9, and its application to the effective dose calculation for individual occupationally exposed. from the internal and external individual monitoring data

  14. Clear up the rule for the exporter (at the Resolution 04/69), whether it is not possible the acquisition at the market abroad

    International Nuclear Information System (INIS)

    1977-09-01

    Define rules for acquisition at the abroad market of the concentrates of uranium chemical compounds. When this impossibility is corroborated by a quarterly consultation, the exporter will have an acquittance after proving the withdrawal, in a special account in the name oc Comissao Nacional De Energia Nuclear (CNEN), and maintain the limit of exception for 0.20 % of ThO 2

  15. PPR: a database for radiologic protection plan elaboration

    International Nuclear Information System (INIS)

    Goncalves, M.; Farias, J.T. de; Batista, D.V.

    2001-01-01

    The Plan of Radiation Protection is a document demanded for Licensing of the Radioactive Installations. It establishes the system of Radioprotection to be implemented by the Service of Radiation Protection. Its main objective is to achieve the requirements of Radiation Protection and Safety constants in the regulations CNEN-NE-3.01 - Basic Guidelines of Radiation Protection and CNEN-NE-3.06 - Requirements of Radiation Protection and Safety for Services of Radiotherapy. The proposal presented here has the aim to easy the development and the uniformity of the elaboration of the Plan of Radiation Protection. Considering the difficulties found by the physicists responsible for the services in developing a Plan of Radiation Protection that contemplate all the necessary requirements, as well as the final analysis accomplished by CNEN, the present project was elaborated. This consists of a software of easy use, developed according to the most modern patterns of programming, allowing to the user to elaborate the Plan of Radiation Protection in agreement with to basic needs of the Installation. Soon the software will be available in the page web of CNEN for download. (author)

  16. Sodium separation from the cover gas system of the PEC reactor

    International Nuclear Information System (INIS)

    Antoni, R.; Picone, G.; Valentini, P.; Bandiera, P.G.; Barilli, L.

    1977-01-01

    The problem of separation of sodium vapours and aerosols from argon was studied. The study generally dealt with the realisation and application on the CNEN sodium loops of sodium vapour traps, which normally have a discontinuous working and treat limited argon flow. Those experiences were utilised for NIRA industrial applications. A possible application of these type of traps was shown for the PEC reactor

  17. Evaluation of the environmental equivalent dose rate using area monitors for neutrons in clinical linear accelerators

    International Nuclear Information System (INIS)

    Salgado, Ana Paula; Pereira, Walsan Wagner; Patrao, Karla C. de Souza; Fonseca, Evaldo S. da; Batista, Delano V.S.

    2009-01-01

    The Neutron Laboratory of the Radioprotection and Dosimetry Institute - IRD/CNEN, Rio de Janeiro, Brazil, initiated studies on the process of calibration of neutron area monitors and the results of the measurements performed at radiotherapy treatment rooms, containing clinical accelerators

  18. Servir: an automated document delivery system

    International Nuclear Information System (INIS)

    Lima, E.C.; Azevedo Coutinho, O.C. de

    1986-01-01

    SERVIR, an automated document delivery system developed by CIN/CNEN, is described. Parametric procedures for reading bibliographic data bases and requesting documents from libraries through computer are specified. Statistical procedures, accounting system and the on-line fulfillment of requests are presented. (Author) [pt

  19. Radioactive materials transportation by motorbike in entire Brazil territory

    International Nuclear Information System (INIS)

    2006-09-01

    This Regulation refers to the interpretation of the term vehicle in the Chapter 3 of the CNEN-NE.5.01 'Vehicle: road vehicle (including articulated vehicle, i.e., combination of tractor and semi-trailer), car or railway wagon. Each wagon should be considered a separate vehicle'. This definition does not include the possibility of radioactive material transportation by motorbike

  20. Dose coefficients for individual occupationally exposed

    International Nuclear Information System (INIS)

    2005-11-01

    This Regulation refers to the requirements of the Regulation CNEN-NN.3.01, 'Basic Act of Radiological Protection', aiming its application to the dose calculation, with purposes of conformity verification with limits and restrictions of doses and level of reference for individual occupationally exposed, according to the express in its section 5

  1. IEN project - Fluidized bed burner

    International Nuclear Information System (INIS)

    1985-08-01

    Due to difficulties inherent to the organic waste storage from laboratories and institutes which use radioactive materials for scientific researches, the Nuclear Facilities Division (DIN/CNEN); elaborated a project for constructing a fluidized burner, in laboratory scale, for burning the low level organic radioactive wastes. The burning system of organic wastes is described. (M.C.K.) [pt

  2. Computer systems for nuclear installation data control

    International Nuclear Information System (INIS)

    1987-09-01

    The computer programs developed by Divisao de Instalacoes Nucleares (DIN) from Brazilian CNEN for data control on nuclear installations in Brazil are presented. The following computer programs are described: control of registered companies, control of industrial sources, irradiators and monitors; control of liable person; control of industry irregularities; for elaborating credence tests; for shielding analysis; control of waste refuge [pt

  3. Regulatory and legal aspects in industrial mining industries

    International Nuclear Information System (INIS)

    Magalhaes, Maisa Haiidamus

    2016-01-01

    The regulation between the Brazilian Nuclear Energy Commission - CNEN performance and the mineral industries that produces NORM is presented. Besides the legal aspects, some comments from the point of view of the supervisory and licensing body about their performance in the radiation protection area are pointed out

  4. Numerical investigation of the High Temperature Reactor (VHTR) using computational fluid dynamics

    International Nuclear Information System (INIS)

    Pinto, Joao Pedro C.T.A.; Santos, Andre A. Campagnole dos; Mesquita, Amir Z.

    2013-01-01

    This work consists to evaluate and continue the study that is being developed in the Laboratory of Thermo-Hydraulics of the CNEN/CDTN (Centro de Desenvolvimento da Tecnologia Nuclear), aiming to validate the methods and procedures used in the numerical calculations of fluid flow in fuel elements of the core of the VHTR

  5. Use of microcomputers in the environmental analysis of research nuclear reactors

    International Nuclear Information System (INIS)

    Molnary, L. de

    1988-01-01

    An automatic meteorological monitoring system developed by Department of Reactor Technology of IPEN/CNEN-SP, is described. The system integrates an environmental analysis program of research reactors. The basic characteristic of this system is the utilization of personal computers to control all meteorological data aquisition in a several levels instrumented tower. (author) [pt

  6. Occupational and Radiological Protection Department - DEPRO

    International Nuclear Information System (INIS)

    1989-01-01

    This report presents the activities and purposes of the Occupational and Radiological Dept. of the Institute of Radioprotection and Dosimetry of Brazilian CNEN. A critical analysis of its situation and expectations are also presented, besides personnel list. (J.A.M.M.)

  7. Control board and utility system for cell complex

    International Nuclear Information System (INIS)

    Almeida, G.L. de; Silva, A.C.; Souza, A.S.F. de; Souza, M.L.M. de; Rautenberg, F.A.

    1986-01-01

    To attend necessities of hot cells operation and process control for isotope production in IEN cyclotron (Brazilian-CNEN) a utility system, such as, electricity, water, vacuum, air, and gas, and control board was constructed, which advantages are presented. (M.C.K.)

  8. Control rod experiments in Racine

    International Nuclear Information System (INIS)

    Stanculescu, A.; Humbert, G.

    1981-09-01

    A survey of the control-rod experiments planned within the joint CEA/CNEN-DeBeNe critical experiment RACINE is given. The applicability to both heterogeneous and homogeneous large power LMFBR-cores is discussed. Finally, the most significant results of the provisional design calculations performed on behalf of the RACINE control-rod programme are presented

  9. Proposal of a national system to supervise nuclear installations out of international safeguards

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1990-01-01

    It is proposed a national system to safeguard, supervise and inspect nuclear facilities in Brazil, apart from international safeguards. It discusses also the military nuclear activities and the uranium enrichment plants. The system should be controlled by Brazilian CNEN. (A.C.A.S.)

  10. Standard 'Principle guides of radioprotection': introduced concepts and future forecasting

    International Nuclear Information System (INIS)

    Dagnino, R.

    1989-01-01

    The main topics introduced by the new CNEN standard NE 3.01 - Basic Directrix of Radioprotection directly associated to the field work in industrial radiography are presented. It's showed a practical example which evidences the need of information exchange among the industrial security, radiological safety and quality control staffs for the continuity of works in this area. (author)

  11. Safety of systems for the retention of wastes containing radionuclides

    International Nuclear Information System (INIS)

    1980-11-01

    Information and minimal requirements demanded by CNEN for the emission of the Approval Certificate of the Safety Analysis Report related to system for the retention of wastes containing radionuclide, are established, aiming to assure low radioactivity levels to the environment. (E.G.) [pt

  12. Model of a Generic Natural Uranium Conversion Plant ? Suggested Measures to Strengthen International Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Raffo-Caiado, Ana Claudia [ORNL; Begovich, John M [ORNL; Ferrada, Juan J [ORNL

    2009-11-01

    This is the final report that closed a joint collaboration effort between DOE and the National Nuclear Energy Commission of Brazil (CNEN). In 2005, DOE and CNEN started a collaborative effort to evaluate measures that can strengthen the effectiveness of international safeguards at a natural uranium conversion plant (NUCP). The work was performed by DOE s Oak Ridge National Laboratory and CNEN. A generic model of a NUCP was developed and typical processing steps were defined. Advanced instrumentation and techniques for verification purposes were identified and investigated. The scope of the work was triggered by the International Atomic Energy Agency s 2003 revised policy concerning the starting point of safeguards at uranium conversion facilities. Prior to this policy only the final products of the uranium conversion plant were considered to be of composition and purity suitable for use in the nuclear fuel cycle and therefore, subject to the IAEA safeguards control. DOE and CNEN have explored options for implementing the IAEA policy, although Brazil understands that the new policy established by the IAEA is beyond the framework of the Quadripartite Agreement of which it is one of the parties, together with Argentina, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) and the IAEA. Two technical papers on this subject were published at the 2005 and 2008 INMM Annual Meetings.

  13. Analysis of the results obtained by optical measurements in plasma focus equipments

    International Nuclear Information System (INIS)

    Bilbao, L.; Bruzzone, H.

    1982-01-01

    The results obtained by shadow and Schlieren photographies and interferometry in a 1MJ plasma focus device of Frascati (CNEN-EURATOM, Italy) are compared with a great number of similar measurement results in several devices of the world. A critical analysis of the above results is presented. (L.C.) [pt

  14. Determination of alternative conditions for instruments calibration with beta radiation

    International Nuclear Information System (INIS)

    Rocha, F.D.G.; Caldas, L.V.E.

    1992-01-01

    The influence of homogenization filter in the determination of chamber calibration factors and transmission factors of beta radiation in air, for obtaining different alternative conditions for beta-gamma portable monitors calibration was studied, using an extrapolation chamber and the beta secondary system at IPEN-CNEN-Brazil. (C.G.C.)

  15. Sonar: a multibase and parametric interface software for SDI

    International Nuclear Information System (INIS)

    Fonseca Passos, M.C.J. da

    1986-01-01

    Sonar - an automated service for selective dissemination of information (SDI) - developed by the Centro de Informacoes Nucleares (CIN) of the Comissao Nacional de Energia Nuclear (CNEN) is described. Emphasis is given to the multibase feature of the system based on the parametric interface between the system and an external data base reading subroutine. (Author) [pt

  16. PROIMRAD X.01: a new code for management of radioactive wastes

    International Nuclear Information System (INIS)

    Velo, Alexandre Franca; Hormaza, Joel M.

    2009-01-01

    The Center for Nuclear Energy in the Agriculture (CENA) is an institution of the Sao Paulo University making use of ionizing radiation under The form of sealed and non sealed sources for research. In the non sealed source there are a large production of contaminated waste. The system used by the CENA was conceived by the CENA-Radiation Protection Service. The calculation follows the regulation for radioactive wastes (CNEN-NE-6.05) which regulates the limits for release, and the regulatory position number 001 of the new regulation CNEN-NN-3.01, which treats of the exemption levels, both regulations from the Brazilian Nuclear Energy Commission (CNEN). The process is not standardized, and each user makes in a manner that he founds to be more convenient. So this work presents a software developed in the Microsoft Office Excel 2007 platform, obeying the CNEN regulations. This program calculates the time of the waste release, and filling up the register with more important data, making it easier and optimizing the management. In that register is mentioned the physical state of the waste, the radioactive isotope which is contained, the activity and the unity, the volume for the liquid case, and weight if solid, and the date of the contamination. Based on those data, the program calculates the release date and fill up the record with data supplied by the user. With that elements possible human errors are minimized and environment contamination risks are reduced

  17. The problem of licensing and safety of nuclear power plants

    International Nuclear Information System (INIS)

    Silva, R.A. da.

    1987-01-01

    The historical evolution of licensing process of nuclear power plants is presented. The designs carried out by FURNAS for constructing Angra-1 reactor and its contribution to the Brazilian CNEN in de licensing process, are evaluated. The aims of FURNAS Research Programs are determined and the safety goals are established. (M.C.K.) [pt

  18. Suprir - multibase system for retrospective search

    International Nuclear Information System (INIS)

    Lovisi, A.L.M.; Fernandes, C.C.

    1986-01-01

    SUPRIR - a Retrospective Search System developed at the Centro de Informacoes Nucleares (CIN) of the Comissao Nacional de Energia Nuclear (CNEN) is described. The multi-base software structure and the bibliographic data bases in operation under SUPRIR are presented. The utilization of the system, means of access and query formulation are shown. (Author) [pt

  19. The operational and logistic experience on transportation of Brazilian spent fuel to USA

    International Nuclear Information System (INIS)

    Maiorino, Jose Rubens; Frajndlich, Roberto; Mandlae, Martin; Bensberg, Werner; Renger, August; Grabow, Karsten

    2000-01-01

    A shipment of 127 spent MTR fuel assemblies was made from IEA-R1 Research Reactor located at the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), Sao Paulo, Brazil to Savannah River Site Laboratory in the United States. This paper describes the operational and logistic experience on this transportation made by IPEN staff and the Consortium NCS/GNS. (author)

  20. Inspection of the brazilian nuclear regulatory body in the area of radiotherapy. A critical analysis; Inspecao do orgao regulador nuclear brasileiro na area de radioterapia. Uma analise critica

    Energy Technology Data Exchange (ETDEWEB)

    Brito, Ricardo Roberto de Azevedo

    2005-07-01

    The National Commission of Nuclear Energy (CNEN) is responsible in Brazil for the activities of licensing and control of radioactive installations in the radiotherapy medical area. The majority of these activities are developed by CNEN Co-ordination of Radioactive Installations (CORAD). One of the necessary stages for the development of licensing and control activities is the inspection of radiotherapy services (clinics and hospitals). Almost all of these inspections are carried out by CNEN Inst. of Radiation Protection and Dosimetry (IRD), through its Service of Medical Physics in Radiotherapy and Nuclear Medicine (SEFME). This work makes a survey of the main nonconformities found during ten years of inspections in radiotherapy services (1995 - 2004) and analyses the efficiency of these inspections in making the radiotherapy services develop their activities according to the norms in vigour in the country and adopt corrective actions against, at least, the nonconformities evidenced by CNEN inspectors. Additionally, it analyses the possibility of improvement and / or the optimisation of the process, through a procedure able to be unified and controlled, aiming a prompt communication to those involved in the licensing process (SEFME and CORAD) about the attendance by the radiotherapy services to the non-conformity items observed during the inspection. (author)

  1. How to prepare a calibration laboratory for ionizing radiation using X rays

    International Nuclear Information System (INIS)

    Bossio, Francisco; Cardoso, Ricardo de Souza; Quaresma, Daniel da Silva; Batista Filha, Luzianete do Amaral; Peixoto, Jose Guilherme Pereira

    2013-01-01

    This work shows the main features of a system for calibration and testing of radiation detectors used in low and medium energy. It is based on pre-assembly System Laboratory of Metrology Division (DIMET) Institute of Radiation Protection and Dosimetry (IRD) of the National Commission of Nuclear Energy (CNEN). (author)

  2. A medical follow-up of 137 Cs Goiania radiation accident: un update (1990-1992)

    International Nuclear Information System (INIS)

    Brandao-Mello, Carlos Eduardo; Oliveira, Alexandre Rodrigues de; Farina, Rosana

    1995-01-01

    The aim of this paper is to describe the main aftereffects of the 137 Cs accident in the last two years, giving emphasis on clinical, hematological, radiological and psychological aspects. A medical follow-up protocol was established by CNEN and the Leide das Neves Ferreira Foundation of the State of Goias, in order to prospectively follow more than 150 victims. (author). 6 refs

  3. Annual Technical Report - Nuclear Engineering Institute/ Dept. of Physics (IEN/DEFI) 1988

    International Nuclear Information System (INIS)

    Silva, A.G. da; Cabral, S.C.; Osso Junior, J.A.

    1988-01-01

    The researches carried out by physics department of Nuclear Engineering Institute(IEN)/Brazilian CNEN are presented. The researches in nuclear physics, isotope production and irradiation damages using CV-28 cyclotron which accelerates protons, deuterons, helium and alpha particles with maximum energies of 24, 14, 36 and 28 MeV, respectively are described. (M.C.K.)

  4. Annual technical report - 1987 - Nuclear Engineering Institute - Dept. of Physics

    International Nuclear Information System (INIS)

    Silva, A.G. da; Cabral, S.C.; Bastos, M.A.V.

    1987-01-01

    The research reports carried out in the Physics Department of Nuclear Engineering Institute/Brazilian CNEN, in nuclear physics, isotope production and hazards by irradiation using the CV-28 cyclotron capable to accelerate protons, deuterons, helium and alpha particles with maximum energies of 24, 14, 36 and 28 MeV, respectively, are presented. (M.C.K.) [pt

  5. Technical bases used in Italy for the licensing of the nuclear power plant

    International Nuclear Information System (INIS)

    Ferreli, A.; Paribelli, S.; Valeri, A.

    1979-01-01

    The criteria and the set of standards used by C.N.E.N. in the regulatory process for the NPS licensing activities are presented. Emphasis is placed in the recent trend which includes to some extent probabilistic techniques in the NPS safety evaluation. (author)

  6. Program for analysis and evaluation of operational data in nuclear power plants - statistical of operational incident of 1984 to 1985 from Angra-1

    International Nuclear Information System (INIS)

    Soares, H.V.; Ambros, P.C.; Araujo, J.B.

    1987-01-01

    The reports of CNEN in the years of 1984 - 1985 regarding reactor accidents. These reports are divided into five classes: reactor shutdown, operator of the core emergency cooling system, power plant operating at limit conditions, radioactivity contamination and super exposition is presented. (A.C.A.S.)

  7. A review of the Italian fast reactor programme, March 1979

    Energy Technology Data Exchange (ETDEWEB)

    Pierantoni, F

    1979-07-01

    Year 1978 in Italy was marked by a standstill in the nuclear energy field. The decisions previously made for the installation of eight 1000 MWe LWR-type reactors could not be acted upon because of the opposition of local authorities and lack of Government power. The construction site at Montalto di Castro (two BWR reactors) was ope ned with difficulty, whereas the decision to install a plant in Mo use equipped with two PWR reactor was postponed. The new presidents of ENEL and CNEN were appointed in January this year and the appointments of the new Boards of Directors are underway. With regard to CNEN, many political bodies are in agreement on an institutional change which would widen field of activity to include new energy sources, solar energy in particular. This will open a big problem: if CNEN will be no more a 'nuclear body, it could be necessary to transfer all the activities connected to the Regulatory Commission to another separate body to be instituted. In this context, the fast reactor programme has continued to develop under the directives of CIPE, and has concentrated its effort on the following three objectives: the PEC-Reactor, the Creys-Malville Power Plant and research and development, and industrial promotion. These objectives are being pursued with the participation of CNEN, ENEL and Italian industry. CNEN has the role of committing and operating the PEC reactor; it is also charged to perform part of the R and D Italian-French programme and to promote industrial development. ENEL participates in the NERSA Company, owner of the Creys-Malville Plant. Italian industry, with its activities of architect-engineering, designing and manufacturing will participate in the construction of the PEC and of the Italian part (33%) of the Creys-Malville Plant. During the last months of 1978 a consortium (COREY) was set up by CNEN and NIRA which has the purpose of integrating and ensuring the smooth running of Italian efforts in the field of long-term research and

  8. A review of the Italian fast reactor programme, March 1979

    International Nuclear Information System (INIS)

    Pierantoni, F.

    1979-01-01

    Year 1978 in Italy was marked by a standstill in the nuclear energy field. The decisions previously made for the installation of eight 1000 MWe LWR-type reactors could not be acted upon because of the opposition of local authorities and lack of Government power. The construction site at Montalto di Castro (two BWR reactors) was ope ned with difficulty, whereas the decision to install a plant in Mo use equipped with two PWR reactor was postponed. The new presidents of ENEL and CNEN were appointed in January this year and the appointments of the new Boards of Directors are underway. With regard to CNEN, many political bodies are in agreement on an institutional change which would widen field of activity to include new energy sources, solar energy in particular. This will open a big problem: if CNEN will be no more a 'nuclear body, it could be necessary to transfer all the activities connected to the Regulatory Commission to another separate body to be instituted. In this context, the fast reactor programme has continued to develop under the directives of CIPE, and has concentrated its effort on the following three objectives: the PEC-Reactor, the Creys-Malville Power Plant and research and development, and industrial promotion. These objectives are being pursued with the participation of CNEN, ENEL and Italian industry. CNEN has the role of committing and operating the PEC reactor; it is also charged to perform part of the R and D Italian-French programme and to promote industrial development. ENEL participates in the NERSA Company, owner of the Creys-Malville Plant. Italian industry, with its activities of architect-engineering, designing and manufacturing will participate in the construction of the PEC and of the Italian part (33%) of the Creys-Malville Plant. During the last months of 1978 a consortium (COREY) was set up by CNEN and NIRA which has the purpose of integrating and ensuring the smooth running of Italian efforts in the field of long-term research and

  9. Paradox place: discourse line of nuclear sector

    International Nuclear Information System (INIS)

    Ponce, Iona

    2002-05-01

    This thesis examines the relationship between the public acceptance and image of nuclear energy and the discourse and arguments commonly employed by the nuclear institutions. In doing so, the Critical Discourse Analysis, the French Discourse Analysis and Pragmatics theories were used to evaluate important variables involved in the construction of the nuclear discourse such as social memory, intertextualilty and image construction. The analysis performed shows that the discourse in favor of the nuclear energy is in fact imbedded by the anti-nuclear discourse. As a consequence, the negative image of the nuclear sector is being reinforced at the same time that its public acceptance becomes more difficult. The core of this analysis consists of two sets of information. The first one is the Internet site of the Brazilian National Nuclear Energy Commission (CNEN). CNEN is the federal nuclear regulatory and research and development agency of Brazil. In this analysis it represents the discourse in favor of nuclear energy. The second set of information used in this thesis is composed by a number of texts displayed in the open literature such as newspapers, magazines and Internet sites, all of them expressing anti-nuclear positions. A careful comparison of both sets shows that the discourse of CNEN, instead of showing new ideas and issues related to nuclear energy, in fact, stays mainly in a reactive position as if it were trying to defend itself from the arguments posed by the anti-nuclear discourse. It was concluded that the discourse of CNEN is constrained within a complex field of non positive expressions, arguments and ideas mostly encountered in the anti-nuclear discourse which brings obvious difficulties to explain the benefits of nuclear energy as a whole. To overcome such situation a more detailed study of the CNEN discourse is suggested. (author)

  10. e-Gamma: Nuclear Material Accountancy and Control System in Brazil

    International Nuclear Information System (INIS)

    Negri Ferreira, S.; Souza Dunley, L.

    2015-01-01

    The Brazilian Nuclear Energy Commission (CNEN) is the government organization responsible for regulating all nuclear activities in Brazil and for ensuring that international safeguards are implemented according to the international agreements. In 2006 CNEN initiated a project aiming at the development and implementation of a web based system (e-Gamma) for on line nuclear material accountancy and control. In January-2014, after three years of beta testing, e-Gamma finally became the official nuclear material accountancy system in Brazil. e-Gamma is a web system hosted in a dedicated server under a secure environment maintained at CNEN headquarters. Secure access is provided by the use of Digital Client Certificate and internal user pre-authorization for login as well as multiple access profiles each one with specific function menus. The System operation is based on source documents for each inventory change prepared and updated by the MBA operators with the help of specific forms with strong validations. After the document conclusion the System records the inventory change in a general ledger. Monthly the officers of CNEN analyzes the general ledgers of each MBA and generates the applicable reports through the System [Inventory Change Reports (ICR), Physical Inventory List (PIL), and Material Balance Report (MBR)]. The System allows the running of managerial queries and has brought to CNEN much more control and traceability of the inventory changes and significant reduction in typing errors, costs and inspection efforts. Therefore, more efficient accountancy verification procedures at national and international levels are expected, as well as remote accountancy verification previous to an inspection. The proposed paper will describe the e-Gamma System, its main features and the oral presentation will contain a brief demonstration of some functionalities through the use of a local version installed on a notebook. (author)

  11. Paradox place: discourse line of nuclear sector; Lugar de paradoxos: pelos caminhos discursivos do setor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ponce, Iona

    2002-05-15

    This thesis examines the relationship between the public acceptance and image of nuclear energy and the discourse and arguments commonly employed by the nuclear institutions. In doing so, the Critical Discourse Analysis, the French Discourse Analysis and Pragmatics theories were used to evaluate important variables involved in the construction of the nuclear discourse such as social memory, intertextualilty and image construction. The analysis performed shows that the discourse in favor of the nuclear energy is in fact imbedded by the anti-nuclear discourse. As a consequence, the negative image of the nuclear sector is being reinforced at the same time that its public acceptance becomes more difficult. The core of this analysis consists of two sets of information. The first one is the Internet site of the Brazilian National Nuclear Energy Commission (CNEN). CNEN is the federal nuclear regulatory and research and development agency of Brazil. In this analysis it represents the discourse in favor of nuclear energy. The second set of information used in this thesis is composed by a number of texts displayed in the open literature such as newspapers, magazines and Internet sites, all of them expressing anti-nuclear positions. A careful comparison of both sets shows that the discourse of CNEN, instead of showing new ideas and issues related to nuclear energy, in fact, stays mainly in a reactive position as if it were trying to defend itself from the arguments posed by the anti-nuclear discourse. It was concluded that the discourse of CNEN is constrained within a complex field of non positive expressions, arguments and ideas mostly encountered in the anti-nuclear discourse which brings obvious difficulties to explain the benefits of nuclear energy as a whole. To overcome such situation a more detailed study of the CNEN discourse is suggested. (author)

  12. Control of Radioactive Lightning-Conductor

    International Nuclear Information System (INIS)

    Esposito, E.

    2004-01-01

    The radioactive lightning-conductor production in Brazil was started in 1970 and after a period of 19 years of commercialization of these devices, the National Nuclear Energy Commission (CNEN), based in studies done in Brazil and abroad, proved that the radioactive lightning-conductor performance wasn't superior to the conventional one, so the use of radioactive source is not justified. Thence, the authorization for its production was suspended and the installation of this type of lightning-conductor was forbidden. The radioactive material that results from the dismount of these devices must be immediately sent to CNEN, for treatment and temporary storage. After this prohibition and its publication in several specialized magazines, CNEN was searched for several institutions, factories, churches, etc, interested in obtaining information about the handling and shipment procedures of radioactive lightning-conductors that are inoperative and that must be sent to CNEN's Institutes, in a correct and secure form. From this moment CNEN technicians realize that the owners of radioactive lightning-conductors didn't have any knowledge and training in radiation protection, neither in equipment to monitoring the radiation. The radioactive material from these sources is, in almost all cases, the radioisotope 241Am which has a maximum activity of an order of 5 mCi (1,85 x 10-2 TBq); as the radiation emitted by 241Am is of alpha type, whose range in the air, is just few centimeters and the gamma rays are of low energy, an irradiation offer small risk. However, there is a contamination risk on someone hands, by the contact with the source. Aiming to attend, in an objective way, the users' interests in obtaining some pertinent technical information about the shipping of radioactive lightning-conductor that is inoperative or is being replaced and also to optimize its receipt in CNEN's Institutes, because there still has a great number of these lightning-conductors installed and still

  13. Radioactive waste management of health services

    International Nuclear Information System (INIS)

    Silva, Eliane Magalhaes Pereira da; Miaw, Sophia Teh Whei

    2001-01-01

    In health care establishment, radioactive waste is generated from the use of radioactive materials in medical applications such as diagnosis, therapy and research. Disused sealed sources are also considered as waste. To get the license to operate from Comissao Nacional de Energia Nuclear - CNEN, the installation has to present a Radiation Protection Plan, in which the Waste Management Programme should be included. The Waste Management Programme should contain detailed description on methodologies and information on technical and administrative control of generated waste. This paper presents the basic guidelines for the implementation of a safe waste management by health care establishments, taking into account the regulations from CNEN and recommendations from the International Atomic Energy Agency - IAEA. (author)

  14. Decommissioning of an uranium hexafluoride pilot plant

    International Nuclear Information System (INIS)

    Santos, Ivan; Abrao, Alcidio; Carvalho, Fatima M.S.; Ayoub, Jamil M.S.

    2009-01-01

    The Institute of Nuclear and Energetic Researches has completed fifty years of operation, belongs to the National Commission for Nuclear Energy, it is situated inside the city of Sao Paulo. The IPEN-CNEN/SP is a Brazilian reference in the nuclear fuel cycle, researches in this field began in 1970, having dominance in the cycle steps from Yellow Cake to Uranium Hexafluoride technology. The plant of Uranium Hexafluoride produced 35 metric tonnes of this gas by year, had been closed in 1992, due to domain and total transference of know-how for industrial scale, demand of new facilities for the improvement of recent researches projects. The Institute initiates decommissioning in 2002. Then, the Uranium Hexafluoride pilot plant, no doubt the most important unit of the fuel cycle installed at IPEN-CNEN/SP, beginning decommissioning and dismantlement (D and D) in 2005. Such D and D strategies, planning, assessment and execution are described, presented and evaluated in this paper. (author)

  15. Studies on the radioactive contamination of the sea

    International Nuclear Information System (INIS)

    Bernhard, M.

    1974-12-01

    The annual Report of the CNEN-Euratom Association Contract is presented. The program laid down in this contract calls for the studies of the factors which influence the uptake, accumulation and loss of radioisotopes by different inorganic and organic constituents of the marine environment. The program is divided into two parts: a) the investigation of relevant radioecological and ecological factors in nature and under laboratory conditions; b) the investigation of the outfall area off-shore of the CNEN-Trisaia Centre in the Gulf of Taranto (fuel-reprocessing plant). The task of carrying out this program has been divided between six groups: Chemistry, Botany, Zooplankton, Fisheries biology, Microbiology and Special developments. An account is given of the results obtained in 1972

  16. Management of radioactive wastes of iodine therapy

    International Nuclear Information System (INIS)

    Silva, Andre R.M.; Santos, Helena C.

    2015-01-01

    The main objective of waste radioactive management is to ensure the protection of man and the preservation of the environment. The regulation that established the basis for the good radioactive waste management was elaborated by the Comissao Nacional de Energia Nuclear (CNEN), in 1985. It is the CNEN-NE-6:05: 'Management radioactive waste in radioactive facilities', which although it an important standard related to radioactive waste management and help largely in the design of a management system in radioactive facilities of radioisotope users, covers the topics in a general way and does not consider individuals aspects of the different plants, as is the case of nuclear medicine units. The main objective of this study is to show the segregation and safe packaging, avoiding unnecessary exposure of professionals involved and public individuals in general

  17. Basic information to improve public acceptance to nuclear energy in Brazil; Subsidios para a melhoria da aceitacao da energia nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Gibelli, Sonia M.O.; Lima e Silva, Pedro Paulo de; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    In Brazil, the current production of nuclear energy is restricted to Angra I plant, a 657 MW pressurized water reactor, in operation since 1982. Among the eight units predicted in 1975 within the Brazil Germany nuclear agreement, only two have been effectively contracted, namely Angra 2 and 3. The nuclear alternative, likewise all other energy sources, is very much dependable on the assessment of their own benefits compared to the associated risks posed to the population and the environment. The main goal of this article is to provide information to enable the improvement of public acceptance of the use of nuclear energy in the country, by comparing risks associated with different sources as well as pointing out aspects related to risk perception by the public. (author) 18 refs., 5 figs.; e-mail: sonia at cnen.gov.br; lima-e-silva at pobox.com; axavier at cnen.gov.br

  18. Single-Phase Bundle Flows Including Macroscopic Turbulence Model

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Jun; Yoon, Han Young [KAERI, Daejeon (Korea, Republic of); Yoon, Seok Jong; Cho, Hyoung Kyu [Seoul National University, Seoul (Korea, Republic of)

    2016-05-15

    To deal with various thermal hydraulic phenomena due to rapid change of fluid properties when an accident happens, securing mechanistic approaches as much as possible may reduce the uncertainty arising from improper applications of the experimental models. In this study, the turbulence mixing model, which is well defined in the subchannel analysis code such as VIPRE, COBRA, and MATRA by experiments, is replaced by a macroscopic k-e turbulence model, which represents the aspect of mathematical derivation. The performance of CUPID with macroscopic turbulence model is validated against several bundle experiments: CNEN 4x4 and PNL 7x7 rod bundle tests. In this study, the macroscopic k-e model has been validated for the application to subchannel analysis. It has been implemented in the CUPID code and validated against CNEN 4x4 and PNL 7x7 rod bundle tests. The results showed that the macroscopic k-e turbulence model can estimate the experiments properly.

  19. Description of the TREBIL, CRESSEX and STREUSL computer programs, that belongs to RALLY computer code pack for the analysis of reliability systems

    International Nuclear Information System (INIS)

    Fernandes Filho, T.L.

    1982-11-01

    The RALLY computer code pack (RALLY pack) is a set of computer codes destinate to the reliability of complex systems, aiming to a risk analysis. Three of the six codes, are commented, presenting their purpose, input description, calculation methods and results obtained with each one of those computer codes. The computer codes are: TREBIL, to obtain the fault tree logical equivalent; CRESSEX, to obtain the minimal cut and the punctual values of the non-reliability and non-availability of the system; and STREUSL, for the dispersion calculation of those values around the media. In spite of the CRESSEX, in its version available at CNEN, uses a little long method to obtain the minimal cut in an HB-CNEN system, the three computer programs show good results, mainly the STREUSL, which permits the simulation of various components. (E.G.) [pt

  20. Calibration of radon-222 detectors using closed circuit radium-226 sources

    International Nuclear Information System (INIS)

    Perna, Allan Felipe Nunes; Paschuk, Sergei Anatolyevich; Correa, Janine Nicolosi; Del Claro, Flavia

    2012-01-01

    This paper presents the results of the calibration of the Radon-222 detectors used by the Laboratories specializing in measuring natural radiation from this gas. The research was conducted in collaboration between UTFPR, CDTN/CNEN, UFRN and IRD/CNEN. During the calibration the detectors were exposed in isolated chambers with radioactive calibrated sources. The calibration procedure was supported with four instant radon monitors AlphaGUARD (SAPHYMO Co.) responsible for radon activity measurements in the experimental chamber. The calibration procedure resulted an equation that relates the number of tracks found in solid-state detector CR-39 (Track-Etch detector) with the concentration of radon in the atmosphere. Obtained results are compatible with previously performed calibration at the National Institute of Radiological Sciences (NIRS, Japan) using high activity levels of radon in air. Present results of calibration give the possibility to expand the calibration curve of CR-39 for medium and low activity levels of radon. (author)

  1. Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Nelson Luiz Dias [Centro Tecnologico da Marinha em Sao Paulo (CTMSP) Sao Paulo, SP (Brazil)

    2011-07-01

    The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

  2. Radiation protection and dosimetry: basis. 9. ed.

    International Nuclear Information System (INIS)

    Tauhata, Luiz; Salati, Ivan; Di Prinzio, Renato; Di Prinzio, Antonieta R.

    2013-11-01

    A revised book 'Radiation Protection and Dosimetry: Fundamentals , prepared to meet the training courses offered by the Instituto de Radioprotecao e Dosimetria - IRD, Rio de Janeiro, RJ, Brazil and people interested in the subject, is presented. Concepts have been updated, especially the chapter on Radiological Magnitudes, due to upgrade of Standard CNEN-NN-3.01-Basic Guidelines on Radiological Protection, published in the Diario Oficial da Uniao on September 1, 2011. A chapter related to Waste Management, another on the Transport of Radioactive Materials and three annexes on: Standards of CNEN, Ionizing Radiation and Personnel Legislation and Determination of shields in Radiotherapy were included. Were also added several tables for use in radiological protection, to facilitate consultation

  3. Implantation of a new certification systematic of external individual monitoring services in Brazil

    International Nuclear Information System (INIS)

    Salati, Ivan P.A.; Cunha, Paulo G. da; Mauricio, Claudia L.P.; Mota, Helvecio C.; Ramos, Manoel M.O.; Silva, Teogenes A. da

    1996-01-01

    Brazilian regulations for External Individual Monitoring Services (SMIE) were established since 1981 and they weren't able to accomplish that these services reached the standards of quality assurance programs appointed for both national and international recommendations. Intercomparisons and audits took in course in 80's showed the necessity of improving the quality of services operating in Brazil. These services are responsible for monitoring more than 40.000 workers in this country. In 1992, the Committee of Assessment of External Individual Monitoring (named CASMIE) was created in the Instituto de Radioprotecao e Dosimetria (IRD/CNEN) in the aim of developing technical standards and to propose new procedures of SMIEs accreditation by Comissao Nacional de Energia Nuclear (CNEN). The new procedures are implemented in 1995. In this work, the relevant aspects of this process are presented, as well as a summary of the technical documents that were developed by CASMIE. (author)

  4. Brazil: Increasing the Reach of the INIS Database by using Social Media

    International Nuclear Information System (INIS)

    Braga, Fabiane; Gama das Neves, Teodora Marly; Pereira, Diogo

    2015-01-01

    INIS began its activities in 1970 to collect and share scientific and technical information about the peaceful uses of nuclear science and technology, with participating nations collaborating to build a centralized database. In the same year, the Nuclear Information Center of the Brazilian Nuclear Energy Commission (CIN/CNEN) was created with the mission of representing Brazil in the INIS system. Since then it has played an important role in the context of Brazilian scientific and technological development as a database cooperative producer, a scientific and technical information service provider, and a knowledge generator, utilizing the INIS database. Since the 1970’s, CIN/CNEN has developed new information products and services based on the INIS database and produced in cooperation with other INIS Members, in order to support research in nuclear and related fields and to keep researchers updated on the newest publications in their areas of interest

  5. Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

    International Nuclear Information System (INIS)

    Ferreira, Nelson Luiz Dias

    2011-01-01

    The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

  6. Fabrication procedures for manufacturing high uranium concentration dispersion fuel elements

    OpenAIRE

    SOUZA, JOSE A.B. de

    2014-01-01

    O IPEN-CNEN/SP desenvolveu e disponibilizou para produção rotineira a tecnologia de fabricação de elementos combustíveis tipo dispersão, para uso em reatores nucleares de pesquisas. O combustível fabricado no IPEN-CNEN/SP está limitado à concentração de urânio de 3,0gU/cm3, para dispersões a base de U3Si2-Al, e de 2,3gU/cm3, para dispersões a base de U3O8-Al. O aumento da concentração de urânio nas placas combustíveis possibilita aumentar a reatividade do núcleo do reator e a vida útil do com...

  7. Citham a computer code for calculating fuel depletion-description, tests, modifications and evaluation

    International Nuclear Information System (INIS)

    Alvarenga, M.A.B.

    1984-12-01

    The CITHAN computer code was developed at IPEN (Instituto de Pesquisas Energeticas e Nucleares) to link the HAMMER computer code with a fuel depletion routine and to provide neutron cross sections to be read with the appropriate format of the CITATION code. The problem arised due to the efforts to addapt the new version denomined HAMMER-TECHION with the routine refered. The HAMMER-TECHION computer code was elaborated by Haifa Institute, Israel within a project with EPRI. This version is at CNEN to be used in multigroup constant generation for neutron diffusion calculation in the scope of the new methodology to be adopted by CNEN. The theoretical formulation of CITHAM computer code, tests and modificatins are described. (Author) [pt

  8. Neutronic studies in the enrichment reduction of research reactor IEAR-1

    International Nuclear Information System (INIS)

    Maiorino, J.R.; Fanaro, L.C.B.; Mai, L.A.; Ferreira, P.S.B.; Garone, J.G.M.

    1987-01-01

    In the present work the codes used by the Reactor Physics Division of IPEN-CNEN-SP in calculations for plate-type reactors are described analyzing research reactor IEAR-1. The IAEA model problem for a plate-type reactor 10 MW with high, medium and low enrichment is solved through different methodologies now in use at the RTF/IPEN-CNEN-SP (HAMMER and HAMMER-TECH-CITATION and LEO4-2DBP-UM) looking into the calculation capability for high to low enrichment conversion within the contract held with the IAEA (BRA-4661). Finally, present reactor configuration calculations are compared with experimental measurements with the aim to validate the calculation method. (Author)

  9. Reproducibility and calibration studies of TLD 600, TLD 700 and TLD 400

    International Nuclear Information System (INIS)

    Cavalieri, T.A.; Castro, V.A.; Siqueira, P.T.D.

    2013-01-01

    A new method to study of reproducibility of the thermoluminescent dosimeters (TLDs) and their calibration was carried on and compared with the method previously used by the BNCT research group of IPEN/CNEN. In this new method, aimed to identify the relations between the individual response of certain types of TLDs with their average response, it was observed a relation approximately constant even at different irradiations. From these relations, normalization of TLDs responses were made, and this method was compared with the method previously adopted by BNCT research group of IPEN/CNEN given better responses. With this new method, the dose response calibration o were made for two gamma sources, with different energies, 60 Co and 137 Cs, for doses ranging from 20 mGy to 1 Gy, and it has been possible to observe the response dependence of these TLDs on energy. (author)

  10. Activity determination of the Am-241 radioactive lightning rods

    International Nuclear Information System (INIS)

    Dellamano, Jose C.; Minematsu, Denise; Potiens Jr, Ademar J.

    2008-01-01

    Full text: The radioactive lightning rods had been manufactured in Brazil up to 1989, when the Comissao Nacional de Energia Nuclear (CNEN) lifted the license for manufacture, commerce and installation of these devices. Since this date, the radioactive lightning rods have been replaced for conventional protection systems against electric discharges and have been sent to the institutes subordinated to the CNEN, amongst them the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP). The radioactive lightning rods are constituted in its majority for a central metallic rod where the plates are mounted. Am-241 radioactive sources are fixed in these plates. The treatment of these devices is made in a glove box, where mechanically the sources are separate of the plates and connecting rods, placed in a metallic package and stored for posterior characterization, final packaging, intermediate storage and final disposal. In accordance with manufacturers information had been installed in Brazil, approximately 75,000 units with activities varying between 25 and 92 MBq. Preliminary studies were carried out in some of the 16,000 lightning rods received by the Laboratorio de Rejeitos Radioativos (LRR) of the IPEN-CNEN/SP, and demonstrated that the variation of the values of activity is very bigger. The implantation of a methodology for the radioisotope characterization of the Am-241 removed sources of the radioactive lightning rods is important because the isotope inventory is necessary for the certification of the processes considered for packaging and storage, besides being indispensable data for the final disposal. It is convenient mentioning that one is not about the determination of activity of a radioactive source with geometry and defined characteristics, but the implantation of a measure protocol for groups of sources that will be used in the routine tasks of the LRR. The current work presents the methodology developed for the radioisotope characterization of the Am

  11. The determination of thermal neutron cross section of 81Br

    International Nuclear Information System (INIS)

    Kovacs, Luciana; Zamboni, Cibele B.; Dalaqua Junior, Leonardo

    2009-01-01

    In this investigation several standard materials were used to determine the thermal neutron cross section of 81 Br. This nuclear parameter is an important data to perform several quantitative investigations, mainly in medical area. In other to confirm and to reduce the uncertainty, a new measurement was preformed using thermal neutron at IEA-R1 nuclear reactor of IPEN/CNEN-SP. The result obtained is compatible with the tabulated value and present small uncertainly. (author)

  12. The Brazilian emergency response system

    International Nuclear Information System (INIS)

    Santos, Raul dos

    1997-01-01

    With the objective of improving the response actions to potential or real emergency situations generated by radiological or nuclear accidents, the Brazilian National Nuclear Energy Commission (CNEN) installed an integrated response system on a 24 hours basis. All the natiowide notifications on events that may start an emergency situation are converged to this system. Established since July 1990, this system has received around 300 notifications in which 5% were classified as potential emergency situation. (author)

  13. Evaluation of sensitivity evaluation of a contamination monitor for use in monitoring of internal exposure of workers in nuclear medicine

    International Nuclear Information System (INIS)

    Dantas, Bernando Maranhao; Assis, Janima Cruz de; Oliveira, Salomao Marques de; Dantas, Ana Leticia Almeida

    2014-01-01

    In practice of nuclear medicine, expert personnel routinely handle radiopharmaceuticals for diagnosis and radiotherapy. The control of intakes of radionuclides by workers can be performed through internal dosimetry techniques, as an integral part of the radiation protection program of the installation. The use of radiopharmaceuticals for diagnostic and therapeutic purposes in vivo and in vitro in Brazil is regulated by CNEN-NE Standards and 3:05 CNEN-NN 3.01. The International Atomic Energy Agency (IAEA) recommends the establishment of an internal monitoring program on workers, especially those subject to possible exposure to annual effective doses greater than 1 mSv. Note that, currently, in Brazil, are not available qualified laboratories to provide internal monitoring services in all regions in the country, if it were applied by CNEN, the requirement for internal monitoring of workers. This paper presents the development of a simple and low-cost methodology for in vivo monitoring of 131 I in the thyroid. The proposed methodology is the use of portable monitor of surface contamination, equipment available and routinely used in all nuclear medicine services in Brazil. The monitor is calibrated with neck-thyroid simulator developed at the Laboratory of In Vivo Monitoring of IRD/CNEN-RJ. The equipment tested is suitable for application in in vivo occupational monitoring thyroid. This conclusion is based on the fact that the detection system has sufficient sensitivity for monitoring up to seven days after the incorporation of the radionuclide and guarantees 131 I detection in values that result in effective doses below 1 mSv for the exposure scenarios adopted

  14. Conception of CTMSP ionizing radiation calibration laboratory

    International Nuclear Information System (INIS)

    Silva, Raimundo Dias da; Kibrit, Eduardo

    2009-01-01

    The present paper describes the implantation process of an ionizing radiation calibration laboratory in a preexistent installation in CTMSP (bunker) approved by CNEN to operate with gamma-ray for non destructive testing. This laboratory will extend and improve the current metrological capacity for the attendance to the increasing demand for services of calibration of ionizing radiation measuring instruments. Statutory and regulatory requirements for the licensing of the installation are presented and deeply reviewed. (author)

  15. Implementation of radioactive wastes management system in nuclear medicine service of Hospital das Clinicas of Universidade de Campinas - UNICAMP, in Sao Paulo State, Brazil

    International Nuclear Information System (INIS)

    Rinaldi Neto, A.; Coelho, R.F.; Brunetto, S.Q.

    2001-01-01

    This work reports the experience acquired at the Servico de Medicina Nuclear of the Hospital de Clinicas/UNICAMP (SMN/HC) in planning and implementing the management system of radioactive waste. This system respects the Comissao Nacional de Energia Nuclear' (CNEN) standards and has been of relatively easy and simple performance, without disturbing the SMN/HC's routine. It has also proof to keep its quality along the time. (author)

  16. Laboratory for Calibration of Gamma Radiation Measurement Instruments (LabCal) of Institute of Chemical, Biological, Radiological and Nuclear Defense (IDQBRN) from Brazilian Army Technology Center (CTEx); Laboratorio de Calibracao de Instrumentode Medicao de Radiacao Gama (LabCal) do IDQBRN do CTEx

    Energy Technology Data Exchange (ETDEWEB)

    Amorim, Aneuri de; Balthar, Mario Cesar V.; Santos, Avelino; Vilela, Paulo Ricardo T. de; Oliveira, Luciano Santa Rita; Penha, Paulo Eduardo C. de Oliveira; Gonzaga, Roberto Neves; Andrade, Edson Ramos de; Oliveira, Celio Jorge Vasques de; Fagundes, Luiz Cesar S., E-mail: aneurideamorim@gmail.com [Centro Tecnologico do Exercito (DQBRN/CTEx), Rio de Janeiro, RJ (Brazil). Instituto de Defesa Quimica, Biologica, Radiologica e Nuclear

    2016-07-01

    This paper describes the calibration laboratory deployment steps (LABCAL) gamma ionizing radiation measuring instruments in the Army Technology Center, CTEx. Initially the calibration of radiation monitors will be held in the dosimetric quantity air kerma and operational quantity ambient dose equivalent H*(d). The LABCAL / CTEx has not yet authorized by CASEC / CNEN. This laboratory aims to calibrate the ionizing radiation instruments used by the Brazilian Army. (author)

  17. Apparatus of hot cell for iodine-123 production

    International Nuclear Information System (INIS)

    Almeida, G.L. de; Rautenberg, F.A.; Souza, A.S.F. de.

    1986-01-01

    The hot cell installation at IEN cyclotron (Brazilian-CNEN) for sup(123)I production is presented. Several devices, such as, tube furnace coupling system, tube furnace driving system, sup(123)I target transfer system, product extraction system, furnace control system, and effluent systems, were constructed and modified for implanting process engineering. The requirements of safety engineering for operation process were based on ALARA concept. (M.C.K.)

  18. Utilization of ''RASO'' for a historical survey of Angra-1 power from 26.10.88 for updating the inventory calculation

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.; Goes, A.G.

    1988-12-01

    The ''RASO'', an activity and operational situation report for Angra 1, is transmitted daily by phone to CNEN by inspectors living at Angra 1 site, anal shows the parameters about the operational status of the nuclear power plant. In the period of 26.10.88 to 04.12.88 a discretized power serie was determined for greater time intervals than the original serie, and then new concentrations were calculated using origem 2 computer code. (author) [pt

  19. Fission track dating method: I. Study of neutron flux uniformity in some irradiation positions of IEA-R1 reactor

    International Nuclear Information System (INIS)

    Osorio, A.M.; Hadler, J.C.; Iunes, P.J.; Paulo, S.R. de

    1993-06-01

    In order to use the fission track dating method the flux gradient was verified within the sample holder, in some irradiation positions of the IEA-R1 reactor at IPEN/CNEN, Sao Paulo. The fission track dating method considers only the thermal neutron fission tracks, to subtract the other contributions sample irradiations with a cadmium cover was performed. The neutron flux cadmium influence was studied. (author)

  20. A comparative neutron activation analysis study of common generic manipulated and reference medicines commercialized in Brazil

    International Nuclear Information System (INIS)

    Leal, A.S.; Menezes, M.A.B.C.; Rodrigues, R.R.; Andonie, O.; Vermaercke, P.; Sneyers, L.

    2008-01-01

    In this work, a comparative study of neutron activation analysis (NAA) was performed by the nuclear institutes: CDTN/CNEN-Brazil, CCHEN-Chile and the SCK.CEN-Belgium aiming to investigate some generic, manipulated and reference medicines largely commercialized in Brazil. Some impurities such as: As, Ba, Br, Ce, Co, Cr, Eu, Fe, Hf, Sb, Sc, Sm, Ti and Zn were found, and the heterogeneity of the samples pointed out the lack of an efficient public system of quality control

  1. Heterogeneous computation tests of both substitution and reactivity worth experiments in the RB-3 reactor

    International Nuclear Information System (INIS)

    Broccoli, U.; Cambi, G.; Vanossi, A.; Zapellini, G.

    1977-01-01

    This report presents the results of several experiments carried out in the D 2 O-moderated RB-3 reactors at the CNEN's Laboratory of Montecuccolino, Bologna. The experiments referred to are either fuel-element substitution experiments or interstitial absorber experiments and were performed during the period 1972-1974. The results of measurements are compared with those obtained by means of computational procedure based on some ''cell'' codes coupled with heterogeneous codes. (authors)

  2. Determination of efficiency curves for HPGE detector in different counting geometries

    International Nuclear Information System (INIS)

    Rodrigues, Josianne L.; Kastner, Geraldo F.; Ferreira, Andrea V.

    2011-01-01

    This paper presents the first experimental results related to determination of efficiency curves for HPGe detector in different counting geometries. The detector is a GX2520 Canberra belonging to CDTN/CNEN. Efficiency curves for punctual were determined by using a certified set of gamma sources. These curves were determined for three counting geometries. Following that, efficiency curves for non punctual samples were determined by using standard solutions of radionuclides in 500 ml and 1000 ml wash bottle Marinelli

  3. Arc melting in inert gas atmosphere of zirconium sponge

    International Nuclear Information System (INIS)

    Julio Junior, O.; Andrade, A.H.P. de

    1991-01-01

    The obtainment of metallic zirconium in laboratory scale with commercial and nuclear quality is the objective of the Metallurgy Department of IEN/CNEN - Brazil, so a melting procedure of zirconium sponge in laboratory scale using an arc furnace in inert atmosphere is developed. The effects of atmosphere operation, and the use of gas absorber and the sponge characteristics over the quality of button in as-cast reporting with hardness measures are described. (C.G.C.)

  4. Organization of the individual monitoring in Brazil

    International Nuclear Information System (INIS)

    Cunha, P.

    1991-01-01

    There are about 35,000 workers monitored in Brazil. Most of them are employed onhealth and non-nuclear industrial areas. The external individual monitoring is done by 10 laboratories accredited by the Brazilian Nuclear Energy Commission, CNEN, applying specific regulation. The personal date and doses of the monitored workers are stored in a data bank. In this paper, future improvements are also discussed. (orig.)

  5. Report about the radiological accident in Goiania; Documentario do acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Schrimer, H.P.; Gomes, C.A.; Recio, J.C.A. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Rejeitos Radioativos

    1997-12-31

    This work reports the activities developed by the technical groups who worked during the radiological accident in Goiania, held on September 1997. Several aspects of the accident are described. The final solution for the disposal of the radioactive wastes generated during the accident is presented, according to the Brazilian waste management policy. (author) 7 refs., 6 figs., 2 tabs.; hebe at cnen.gov.br

  6. Radioactive waste facility as environmental preservation factor; Deposito de rejeitos radioativos como agente de preservacao ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Heilbron Filho, P.F.L.; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    The objective of this article is to show, in a resumed way, the many aspects involved in the selection, licensing and construction of a repository for the safe disposal of low and intermediate radioactive level wastes in Brazil where from we conclude that a repository is for sure an agent of environmental preservation. (author) 22 refs., 9 figs., 9 tabs.; e-mail: paulo at cnen.gov.br

  7. Evaluation of the nuclear and radiological emergency response system in Brazil; Visao critica do sistema de atendimento a emergencia radiologica e nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Estrada, Julio J.S.; Azevedo, Eduardo M.; Knoefel, Tom M.J. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Brazilian Nuclear Energy Commission (CNEN) has made outstanding efforts to improve its nuclear and radiological accident response system since the tragic accident in Goiania, Brazil. Most of these efforts are related to nuclear emergency although radiological accidents are also considered. Several topics are discussed involving those related to planning and preparedness. Some deficiencies that need to be corrected or improved are pointed out 8 refs.

  8. Soil sampling in emergency situations; Amostragem de solos em situacoes de emergencia

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Zenildo Lara de [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil); Ramos Junior, Anthenor Costa [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle

    1997-12-31

    The soil sampling methods used in Goiania`s accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author) 15 refs.

  9. General catalogue of products and services - geology. AERO data base; 2. ed; Catalogo geral de produtos e servicos - geologia. Base de dados AERO

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The catalogue in the second edition aims at presenting to the user a general idea on the aerogeophysical projects of Brazil database (AERO) which belongs to SIGA (Brazilian geological information system). The 151 documents (projects) are listed as follows: 52 projects performed by CPRM/DNPM - Departamento Nacional de Producao Mineral; 33 projects performed by CNEN - Commissao Nacional de Energia Nuclear and NUCLEBRAS; 7 projects executed by State government and private companies; and 59 projects executed for PETROBRAS 159 figs., 5 tabs.

  10. Fluid velocity in outer channels of tube bundle of PGV-1 steam generator prototype

    International Nuclear Information System (INIS)

    Salgo, C.

    1979-01-01

    This paper deals with the determination of the fluid velocity and pressure in every channel outside the tube bundle of the prototype model of the steam generator PGV-1, designed jointly by CNEN and NIRA. The results are obtained by the numerical solution of a system of algebraic and differential equations deduced by a mathematical ''channel'' model. Such results agree with the experiments performed on a model of the prototype PGV-1 by Alsthom Technique des Fluides

  11. Investigation of Fe and Ca in non-stimulated human saliva using NAA

    Science.gov (United States)

    de Medeiros, J. A. G.; Zamboni, C. B.; Kovacs, L.; Lewgoy, H. R.

    2015-07-01

    In this study we investigated non-stimulated human whole saliva of healthy subjects and patients with periodontal disease using Neutron Activation Analysis technique (NAA). The measurements were performed in the IEA-R1 nuclear reactor at IPEN-CNEN/SP. We found considerable metabolic changes mainly in Fe and Ca concentration in whole saliva of periodontal patients. These data are useful for identifying or preventing this oral disease in the Brazilian population.

  12. Comparative study of the second antibody for radioimmunoassay totally produced in the country to a similar imported one (sheep serum anti-rabbit IgG)

    International Nuclear Information System (INIS)

    Silva, S.R. da; Borghi, V.C.; Wajchenberg, B.L.

    1992-01-01

    This work compares a second antibody for radioimmunoassay (RIA) produced at IPEN-CNEN/SP with a commercial one of known quality, produced by Radioassay Systems Laboratories, U.S.A.. This antiserum, sheep serum anti-rabbit IgG produced in its totality in the country, presented title and precipitation characteristics similar to those exhibited by the commercial product, being as suitable for the RIA separation as its imported similar. (author)

  13. Activity determination of the Am-241 sources from radioactive lightning rods

    International Nuclear Information System (INIS)

    Minematsu, Denise; Dellamano, Jose Claudio; Ferreira, Robson de Jesus

    2009-01-01

    The authorization for manufacture commerce and installation of radioactive lightning rods, in Brazil, was lifted in 1989 by the National Nuclear Energy Commission - CNEN (Resolution no 4/89). Since this date, these devices have been replaced and have been sent to the Institutes subordinated to the CNEN, amongst them the Nuclear and Energy Research Institute - IPEN-CNEN/SP. Radioactive Waste Management Laboratory - RWML of the IPEN - CNEN/SP had received, approximately, 16,000 units up to the end of 2008. The radioactive lightning rod is constituted in its majority, for a central metallic rod, where two or three metallic plates are mounted. In these plates, on average, six Am-241 sources are fixed. The process used for the radioactive lightning rods treatment is the dismantling of the device and the withdrawal of the sources from the metallic plates. The activity values of the lightning rods sources, supplied by the manufacturers, vary from two to three orders of magnitude and therefore it is necessary to characterize these sources. This paper describes the methodology used to measure the actual activity of each Am-241 sources extracted from the radioactive lightning rods. The first step was to sample tens of Am-241 sources and carry out the activity measurements for further use in the system calibration. The equipment used in this first stage was a gamma spectrometer, previously calibrated with an Am-241 standard source, in agreement with the same arrangement and same geometry in the measures of the sources. Results show that there are sources with similar activity values of those supplied by the manufacturers, but there are also sources with no activity - or also activity very low compared with the expected value -, as well as sources contend other radionuclides. (author)

  14. Development of an alternative reactivity meter for nuclear reactor control

    International Nuclear Information System (INIS)

    Ferreira, P.S.B.

    1991-01-01

    This work describes an alternative version of the IPEN-CNEN/SP reactivity-meter. This new version utilizes a programmable electrometer (to realize the data acquisition) and a IBM-PC microcomputer to process the reactivity calculation. The aim of development of this alternative reactivity-meter is to have available a equipment of measurements of reactivity in the case of the later version show any problem during an experiment. (author)

  15. Laboratory for Calibration of Gamma Radiation Measurement Instruments (LabCal) of Institute of Chemical, Biological, Radiological and Nuclear Defense (IDQBRN) from Brazilian Army Technology Center (CTEx)

    International Nuclear Information System (INIS)

    Amorim, Aneuri de; Balthar, Mario Cesar V.; Santos, Avelino; Vilela, Paulo Ricardo T. de; Oliveira, Luciano Santa Rita; Penha, Paulo Eduardo C. de Oliveira; Gonzaga, Roberto Neves; Andrade, Edson Ramos de; Oliveira, Celio Jorge Vasques de; Fagundes, Luiz Cesar S.

    2016-01-01

    This paper describes the calibration laboratory deployment steps (LABCAL) gamma ionizing radiation measuring instruments in the Army Technology Center, CTEx. Initially the calibration of radiation monitors will be held in the dosimetric quantity air kerma and operational quantity ambient dose equivalent H*(d). The LABCAL / CTEx has not yet authorized by CASEC / CNEN. This laboratory aims to calibrate the ionizing radiation instruments used by the Brazilian Army. (author)

  16. Presentation of reports for licensing of industrial irradiators

    International Nuclear Information System (INIS)

    2000-04-01

    This Regulation refers to the requirements of the Regulation CNEN-NE.6.02. 'Licensing of Radioactive Facilities', expressed in the section 6 related to the information for Previous Approval, in the subsection 7.2 related to the information for the Construction Licensing and in the subsection 9.2, related to the information for the Authorization for operation, for the specific case of industrial irradiators

  17. A measurement evaluation program to support nuclear material control and accountability measurements in Brazilian laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Fabio C., E-mail: fabio@ird.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil); Mason, Peter, E-mail: peter.mason@ch.doe.gov [New Brunswick Laboratory (DOE/NBL), Argonne, IL (United States)

    2013-07-01

    A measurement evaluation program (MEP) is one of a number of valuable tools that analytical chemists can use to ensure that the data produced in the laboratory are fit for their intended purpose and consistent with expected performance values at a given time. As such, participation in a MEP is an important indicator of the quality of analytical data, and is recognized as such by independent regulatory and/or accreditation bodies. With the intent to implement such a program in Brazil, in November 2012 the Nuclear Energy Commission of Brazil (CNEN), with support from the Department of Energy of the United States' (US-DOE International Safeguards and Engagement Program), decided to initiate a technical cooperation project aiming at organizing a Safeguards Measurement Evaluation Program (SMEP) for Brazilian facilities. The project, entitled Action Sheet 23, was formalized under the terms of the Agreement between the US-DOE and the CNEN concerning research and development in nuclear material control, accountancy, verification, physical protection, and advanced containment and surveillance technologies for International Safeguards Applications. The work, jointly performed by the CNEN's Safeguards Laboratory (LASAL) and the New Brunswick Laboratory (NBL), has the objective to strengthen the traceability of accountability measurements and ensure adequate quality of safeguards measurements for facilities within Brazil, utilizing test samples characterized and provided by NBL. Recommendations to participants included measurement frequency, number of results per sample and format for reporting results using ISO methods for calculating and expressing measurement uncertainties. In this paper, we discuss the main steps taken by CNEN and NBL aiming at implementing such a program and the expected results, in particular the impact of uncertainty estimation on the evaluation of performance of each participant laboratory. The program is considered by Brazilian safeguards

  18. Application impact of internal monitoring criteria in radiological protection programs of nuclear medicine services

    International Nuclear Information System (INIS)

    Dantas, Bernardo M.; Dantas, Ana Leticia A.; Juliao, Ligia Q.C.; Lourenco, Maria Cristina; Melo, Dunstana R.

    2005-01-01

    This work presents the simulation of the internal monitoring criteria application for the most used radionuclides by the area of nuclear medicine, taking into consideration the usual conditions of usual source handling and the activity bands authorized by the CNEN. It is concluded that the handling of Iodine 131 for therapeutical purposes is the practice which presents the most risk of internal exposure for the works, requiring the adoption of a program for internal monitoring by the nuclear medicine services

  19. Evaluation of internal dose of handlers of radioisotopes and radiopharmaceuticals for medical use

    International Nuclear Information System (INIS)

    Cesar, R.B.P.; Mesquita, C.H. de

    1987-01-01

    The internal dose of workers from IPEN/CNEN-SP (Brazil) is evaluated according to models described by the ICPR-30 (International Comission on Radiological Protection). The workers, monitored by a whole-body counter, are divided into six groups: research and development, routine production, quality control, packaging, radiological protection and maintenance. The results of 970 counting, done in three years, are presented. (M.C.A.) [pt

  20. Aspects of uranium mineralization in Figueira-PR, Brazil

    International Nuclear Information System (INIS)

    Saad, S.

    1974-01-01

    CNEN has been drilling in the Parana Basin since 1970. The data in the form of eletric, gama ray and stratigrafic logs and chemical analysis or core and cutting samples have been studied. These data show that the uranium deposition is in a paleochannel in the lower part of the Rio Bonito Formation and is due to an epigenetic process. The concentrations encountered indicate the possibility of an economic deposit

  1. Core calculations for the upgrading of the IEA-R1 research reactor

    International Nuclear Information System (INIS)

    Santos, Adimir dos; Perrotta, Jose A.; Bastos, Jose Luis F.; Yamaguchi, Mitsuo; Umbehaun, Pedro E.

    1998-01-01

    The IEA-R1 Research Reactor is a multipurpose reactor. It has been used for basic and applied research in the nuclear area, training and radioisotopes production since 1957. In 1995, the Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP) took the decision to modernize and upgrade the power from 2 to 5 MW and increase the operational cycle. This work presents the design requirements and the calculations effectuated to reach this goal. (author)

  2. Control of occupational exposure in nuclear facilities for terrestrial support to marine vessels; Controle de exposição dos indivíduos em instalações nucleares de apoio terrestre a embarcações marítimas

    Energy Technology Data Exchange (ETDEWEB)

    Lara, E.G., E-mail: evelise.lara@gmail.com [Universidade Federal de Minas Gerais - UFMG, Belo Horizonte-MG (Brazil); Pinheiro, A.R.M.; Borsoi, S.S.; Silva, T.P., E-mail: andrericardopinheiro@gmail.com, E-mail: sadborsoi@usp.br, E-mail: thiago_padilhasilva@poli.ufrj.br [Escola Politécnica, Universidade de São Paulo - POLI-USP, São Paulo-SP (Brazil); Baroni, D.B.; Santos, F.C., E-mail: dbbaroni@gmail.com, E-mail: felipecruz.santos1@gmail.com [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo-SP (Brazil)

    2017-07-01

    This study addresses some basic requirements for exposure control of occupational exposure during the design phase of ground-based nuclear facilities for marine vessels. US regulatory guidelines, CNEN standards and experiences acquired in conventional nuclear installations were used. The installation design should consider the provision of mobile devices for monitoring and decontamination. Finally, it is observed that the establishment of additional exposure control criteria can directly impact the civil, architectural and electromechanical projects of the facility, from the conceptual phase.

  3. Today's attitudes and future prospects of fast reactors in Italy

    International Nuclear Information System (INIS)

    Barabaschi, S.; Cicognani, G.; Pierantoni, F.

    1982-01-01

    The Italian fast reactor programme is reviewed. The 15 year collaboration with France has resulted in the construction of the PEC reactor, development of the Superphenix-1 and a common R and D programme for future large fast reactors. The CNEN 4th five year (1980-84) plan is outlined. The budget breakdown for different areas shows the importance attached to the fast reactor. (U.K.)

  4. 40 years of peaceful uses of nuclear energy in Mexico: historical pamphlet

    International Nuclear Information System (INIS)

    Instituto Nacional de Investigaciones Nucleares.

    1996-01-01

    A historical review of the research activities related to nuclear energy that were carried out in Mexico, during the 50'Th, is presented. It is also given a semblance of the main personalities of the scientific and governmental scope that were involved in the creation of the former Comision Nacional de Energia Nuclear (CNEN), in 1956, which was the predecessor of the Instituto Nacional de Investigaciones Nucleares (ININ), as well as some of the first applications of nuclear energy in Mexico. (Author)

  5. Development of austenitic stainless steel tubes for nuclear reactor cladding

    International Nuclear Information System (INIS)

    Padilha, A.F.; Ferreira, P.I.; Andrade, P.I.; Andrade, A.H.P. de; Meyerhof, S.; Mauricio, J.

    1984-01-01

    In the development of thin wall tubes for nuclear reactor fuel cladding applications, a great number of activities, related to the fabrication process as the qualification are involved. A test program was envisaged to verify the quality of seam welded stainless steel tubes (AISI 304), obtained as a result of an effort by the IPEN-CNEN/SP and the brazilian industry. The relevant aspects involved in the preparation of the tubes and some preliminary test results are presented. (Author) [pt

  6. Applications of artificial intelligence and expert systems in ANGRA-I emergency preparedness - The Brazilian case

    International Nuclear Information System (INIS)

    Alvarenga, M.A.B.; Guimaraes, A.C.F.

    1991-01-01

    This study describes a system to follow a nuclear accident and points the areas where the presence of artificial intelligence could be necessary: diagnostics systems, emergency classification, accident management strategies and protective actions. Logical rules could be combined with deterministic equations to provide an expert system prototype to manage a nuclear emergency preparedness for nuclear reactors (fast or thermal) in the Brazilian Nuclear Energy National Commission. (CNEN). (author)

  7. Ideal storage conditions study of the second antibody for radioimmunoassay (RIA) totality produced in the country (sheep serum anti-IgG of rabbit)

    International Nuclear Information System (INIS)

    Silva, S.R.; Borghi, V.C.; Mesquita, C.M.; Wajchenberg, B.L.

    1994-01-01

    This work has been carried out to establishing the ideal storage conditions of the second RIA antibody produced at IPEN-CNEN/SP. Small samples of these antisera were submitted to two kinds of freezing forms (slow and fast), both followed by lyophilization. The interference of the frozen and lyophilization processes were compared through the antibody dilution curve. The obtained values showed that no significant difference between the freezing forms occurred. (author). 9 refs, 2 figs, 3 tabs

  8. Some applications of nuclear techniques in the petroleum industry

    International Nuclear Information System (INIS)

    Moreira, Rubens Martins; Castro, Jose Olympio Nardelli Monteiro de; Nadvorny, Jerson; Melo, Maria Aparecida de; Lemos, Walter Petroni

    1995-01-01

    This paper presents some studies carried out jointly by Petroleo Brasileiro S.A. - PETROBRAS and Centro de Desenvolvimento da Tecnologia Nuclear - CDTN, of the Comissao Nacional de Energia Nuclear - CNEN, using radioactive tracers in secondary oil recovery operations as well as in process studies of fluidized catalyst cracking units. Some features of tracer selection and radiological safety are discussed. Preliminary results of laboratory and field work are presented. (author). 5 refs., 4 figs., 1 tab

  9. Soil sampling in emergency situations

    International Nuclear Information System (INIS)

    Carvalho, Zenildo Lara de; Ramos Junior, Anthenor Costa

    1997-01-01

    The soil sampling methods used in Goiania's accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author)

  10. A measurement evaluation program to support nuclear material control and accountability measurements in Brazilian laboratories

    International Nuclear Information System (INIS)

    Dias, Fabio C.; Mason, Peter

    2013-01-01

    A measurement evaluation program (MEP) is one of a number of valuable tools that analytical chemists can use to ensure that the data produced in the laboratory are fit for their intended purpose and consistent with expected performance values at a given time. As such, participation in a MEP is an important indicator of the quality of analytical data, and is recognized as such by independent regulatory and/or accreditation bodies. With the intent to implement such a program in Brazil, in November 2012 the Nuclear Energy Commission of Brazil (CNEN), with support from the Department of Energy of the United States' (US-DOE International Safeguards and Engagement Program), decided to initiate a technical cooperation project aiming at organizing a Safeguards Measurement Evaluation Program (SMEP) for Brazilian facilities. The project, entitled Action Sheet 23, was formalized under the terms of the Agreement between the US-DOE and the CNEN concerning research and development in nuclear material control, accountancy, verification, physical protection, and advanced containment and surveillance technologies for International Safeguards Applications. The work, jointly performed by the CNEN's Safeguards Laboratory (LASAL) and the New Brunswick Laboratory (NBL), has the objective to strengthen the traceability of accountability measurements and ensure adequate quality of safeguards measurements for facilities within Brazil, utilizing test samples characterized and provided by NBL. Recommendations to participants included measurement frequency, number of results per sample and format for reporting results using ISO methods for calculating and expressing measurement uncertainties. In this paper, we discuss the main steps taken by CNEN and NBL aiming at implementing such a program and the expected results, in particular the impact of uncertainty estimation on the evaluation of performance of each participant laboratory. The program is considered by Brazilian safeguards authorities

  11. Circular no. 166 F. on the licencing procedure for construction and operation of nuclear installations indicated in the Ministerial Decree of 4.1.1977 subject to the provisions of Section 55 of Decree no.185 of the President of the Republic of 13.2.1964

    International Nuclear Information System (INIS)

    1978-01-01

    This 1978 Circular by the Minister of Industry, Commerce and Crafts lays down the licensing procedure to be complied with for construction and operation of nuclear installations, determined by a Ministerial Decree of 4 January 1977 subjecting certain installations to Section 55 of Presidential Decree no.185 of 13 February 1964. It lists the documents to be supplied by applicants for a licence and describes the technical enquiry to be undertaken by the Comitato Nazionale per l'Energia Nucleare (CNEN). (NEA) [fr

  12. GOSPEG-1 a program for routine analysis of γ-ray spectra by an in line IBM S/7 computer

    International Nuclear Information System (INIS)

    Godio, G.P.; Gozzellino, F.

    1977-01-01

    In this paper a program for routine analysis of γ-ray spectra of samples coming from irradiated nuclear fuel reprocessing plant is described. An IBM S/7 computer (SK words of memory) which is installed at the CNEN-EUREX reprocessing plant and which is in-line connected with a multichannel analyzer and Ge(Li) detector, has been utilized for this work. The program has been written in Assembler S/7 language

  13. Profile updating for information systems

    International Nuclear Information System (INIS)

    Abrantes, J.F.

    1983-02-01

    Profiles updating methods were analysed. A method suitable to the characteristics of the system used in the research (SDI/CIN/CNEN) that uses as the selection criterio the threshold and weights criterion, was determined. Relevance weighting theory was described and experiments to verify precision were carried out. The improvements obtained were good nevertheless more significant tests are required to attain more reliable results. (Author) [pt

  14. Leaching of nuclear power reactor wastes forms

    International Nuclear Information System (INIS)

    Endo, L.S.; Villalobos, J.P.; Miyamoto, H.

    1986-01-01

    The leaching tests for power reactor wastes carried out at IPEN/CNEN-SP are described. These waste forms consist mainly of spent resins and boric acid concentrates solidified in ordinary Portland cement. All tests were conducted according to the ISO and IAEA recommendations. 3 years leaching results are reported, determining cesium and strontium diffusivity coefficients for boric acid waste form and ion-exchange resins. (Author) [pt

  15. General view about reactor safety nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Gasparian, A.E.; Silva, D.E.; Salvatore, J.E.L.; Lima, J.M. de

    1991-01-01

    In this paper the authors describe the principles and goals that have guided, as well as the methods that have been used by the National Commission of Nuclear Energy (CNEN) to set forth measures aiming at providing safety to the Brazilian nuclear power plants. The status of the licensing process of these power plants is shown. The performance and the results obtained so far in relation to the nuclear safety are also described. (author)

  16. Bibliographic survey on methodologies for development of health database of the population in case of cancer occurrences; Levantamento bibliografico sobre metodologias para elaboracao de um banco de dados da saude da populacao em casos de ocorrencias de cancer

    Energy Technology Data Exchange (ETDEWEB)

    Cavinato, Christianne C.; Andrade, Delvonei A. de; Sabundjian, Gaiane, E-mail: christiannecobellocavinato@gmail.com, E-mail: delvonei@ipen.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Diz, Maria Del Pilar E., E-mail: maria.pilar@icesp.org.br [Instituto do Cancer do Estado de Sao Paulo (ICESP), Sao Paulo, SP (Brazil)

    2014-07-01

    The objective is to make a survey of existing methodologies and for the development of public health database, focusing on health (fatal and nonfatal cancer) of the population surrounding a nuclear facility, for purposes of calculating the environmental cost of the same. From methodologies found to develop this type of database, a methodology will be developed to be applied to the internal public of IPEN/CNEN-SP, Brazil, as a pre-test for the acquisition of health information desired.

  17. Italian experience with pilot reprocessing plants

    International Nuclear Information System (INIS)

    Cao, S.; Dworschak, H.; Rolandi, G.; Simonetta, R.

    1977-01-01

    Problems and difficulties recently experienced in the reprocessing technology of high burnup power reactor fuel elements have shown the importance of pilot plant experiments to optimize the separation processes and to test advanced equipment on a representative scale. The CNEN Eurex plant, in Saluggia (Vercelli), with a 50 kg/d thruput, in operation since '71, has completed several reprocessing campaigns on MTR type fuel elements. Two different chemical flowsheets based respectively on TBP and tertiary amines were thoroughly tested and compared: a concise comparative evaluation of the results obtained with the two schemes is given. Extensive modifications have then been introduced (namely a new headend cell equipped with a shear) to make the plant suitable to reprocess power reactor fuels. The experimental program of the plant includes a joint CNEN-AECL reprocessing experiment on CANDU (Pickering) type fuel elements to demonstrate a two cycle, amine based recovery of the plutonium. Later, a stock of high burnup fuel elements from the PWR Trino power station will be reprocessed to recover Pu and U with a Purex type flowsheet. ITREC, the second CNEN experimental reprocessing plant located at Trisaia Nuclear Center (Matera), started active operation two years ago. In the first campaign Th-U mixed oxide fuel elements irradiated in the Elk River reactor were processed. Results of this experiment are reported. ITREC special design features confer a high degree of versability to the plant allowing for substantial equipment modification under remote control conditions. For this reason the plant will be principally devoted in the near future to advanced equipment testing. Along this line high speed centrifugal contactor of a new type developed in Poland will be tested in the plant in the frame of a joint experiment between CNEN and the Polish AEC. Later on the plant program will include experimental campaign on fast reactor fuels; a detailed study on this program is in

  18. Performance evaluation of activimeter for PET radiopharmaceutical measuring based on 18F

    International Nuclear Information System (INIS)

    Fragoso, Maria da Conceicao de Farias; Oliveira, Mercia Liane de; Lima, Fernando Roberto de Andrade

    2014-01-01

    Proficiency test is an essential tool to assess the reliability and accuracy of measurements. In this work, proficiency tests (Z-score, accuracy and relative deviation) were applied to evaluate the performance of the activimeter used at Radiopharmaceuticals Production Division of the Regional Center for Nuclear Sciences of the Northeast (CRCN-NE/CNEN). The results were evaluated in compliance with ISO/IEC Guide 43-1. Additionally, correction factors for different measurement geometries were determined experimentally for those devices. (author)

  19. Knowledge basis in safety culture for researchers and practitioners

    International Nuclear Information System (INIS)

    Vieira Neto, Antonio S.; Barroso, Antonio C.O.; Goncalves, Adriana

    2009-01-01

    This paper presents the main characteristics of the knowledge basis in safety culture which is being developed at the IPEN-CNEN/SP, one of the Brazilian nuclear institutes of research. The main objective of this basis is to organize the information about safety culture found in the literature and to make it available to researchers and practitioners. The first stage of the development of this basis is already finished being the subject of this work. (author)

  20. Quality control of the structural design of Angra 2 and 3 power reactor

    International Nuclear Information System (INIS)

    Merino, J.L.E.; Carvalho, S.R.B. de

    1985-01-01

    The quality control requirements for nuclear power plants are done by CNEN and might be followed by the organizations that are responsible for those activities, such as: design, suppliers, construction, fabrication, mounting, installation, commissioning, operation, maintenance, modification and decommissioning. The Promon's experience for using a quality control program in the structural design of Angra 2 and 3, and the verification system adopted, are presented. (E.G.) [pt

  1. Radioactive waste facility as environmental preservation factor; Deposito de rejeitos radioativos como agente de preservacao ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Loes, Rosa Helena Zago [Instituto Nacional de Meio Ambiente e dos Recursos Naturais Renovaveis (IBAMA), Brasilia, DF (Brazil)

    1997-12-31

    When the capsule of cesium was open ten years ago, in Goiania/GO, provoked a radiologic accident of great consequences for the population. After that, the government, the Comissao Nacional de Energia Nuclear Energy, Brazilian CNEN, the non-governmental organizations and the population began a big mobilization to solve this problem. The result was the construction of the Final Deposit for Radioactive Wastes. (author) 2 refs.; e-mail: rloes at ibama.gov.br

  2. Radioactive waste facility as environmental preservation factor

    International Nuclear Information System (INIS)

    Loes, Rosa Helena Zago

    1997-01-01

    When the capsule of cesium was open ten years ago, in Goiania/GO, provoked a radiologic accident of great consequences for the population. After that, the government, the Comissao Nacional de Energia Nuclear Energy, Brazilian CNEN, the non-governmental organizations and the population began a big mobilization to solve this problem. The result was the construction of the Final Deposit for Radioactive Wastes. (author)

  3. Mechanical behaviour of neutron irradiated Nb monocrystalline

    International Nuclear Information System (INIS)

    Otero, M.P.; Lucki, G.

    1986-01-01

    Nb [941] - oriented single crystal was irradiated to a fluence of 1,1 x 10 19 n/cm 2 in the IEA-R1 reactor at IPEN-CNEN/SP. Tensile-Stress experiments showed an irradiation induced hardening, characterized by an increase in the yield stress of about 16%. This result was interpreted using the 'lattice hardening' model. The observed slip systems are attributed to the gliding of the anomalous slip planes. (Author) [pt

  4. Control of occupational exposure in nuclear facilities for terrestrial support to marine vessels

    International Nuclear Information System (INIS)

    Lara, E.G.; Pinheiro, A.R.M.; Borsoi, S.S.; Silva, T.P.; Baroni, D.B.; Santos, F.C.

    2017-01-01

    This study addresses some basic requirements for exposure control of occupational exposure during the design phase of ground-based nuclear facilities for marine vessels. US regulatory guidelines, CNEN standards and experiences acquired in conventional nuclear installations were used. The installation design should consider the provision of mobile devices for monitoring and decontamination. Finally, it is observed that the establishment of additional exposure control criteria can directly impact the civil, architectural and electromechanical projects of the facility, from the conceptual phase

  5. 137 Cs and 90 Sr in marine samples from Brazilian southern coast

    International Nuclear Information System (INIS)

    Godoy, Jose Marcus; Carvalho, Zenildo L.; Pereira, Jose Carlos A.; Pereira, Wagner S.; Ferreira, Ana Cristina M.; Fernandes, Flavio C.; Danelon, Olga M.

    2000-01-01

    In this paper are presented the results related to monitoring program of Cs-137 and Sr-90 distribution in marine ecosystem from Brazilian southern coast. This program is performed together Instituto de Radioprotecao e Dosimetria (IRD/CNEN/MCT) and the Instituto de Estudos do Mar Almirante Paulo Moreira, aiming the evaluation of artificial radionuclide contents present in marine samples. The program, have started in experimental character in 1996 and became a routine program, carried out yearly

  6. Environmental monitoring in the vicinity of nuclear facilities

    International Nuclear Information System (INIS)

    Jacomino, V.M.F.; Maduar, M.F.

    1992-02-01

    The purpose of this manual is to provide guidance for setting up programmes of environmental monitoring in the vicinity of establishments in a normal condition of operation. It intends to contribute for trainning of technicians working in the nuclear field. In order to illustrate the application of the basic principles described in this manual, the routine environmental monitoring programme carried out in the IPEN-CNEN/SP is presented. (author)

  7. General catalogue of products and services - geology. AERO data base; 2. ed; Catalogo geral de produtos e servicos - geologia. Base de dados AERO

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The catalogue in the second edition aims at presenting to the user a general idea on the aerogeophysical projects of Brazil database (AERO) which belongs to SIGA (Brazilian geological information system). The 151 documents (projects) are listed as follows: 52 projects performed by CPRM/DNPM - Departamento Nacional de Producao Mineral; 33 projects performed by CNEN - Commissao Nacional de Energia Nuclear and NUCLEBRAS; 7 projects executed by State government and private companies; and 59 projects executed for PETROBRAS 159 figs., 5 tabs.

  8. Implementation of the INSPECT software package for statistical calculation in nuclear material accountability

    International Nuclear Information System (INIS)

    Marzo, M.A.S.

    1986-01-01

    The INSPECT software package was developed in the Pacific Northwest Laboratory for statistical calculations in nuclear material accountability. The programs apply the inspection and evaluation methodology described in Part of the Safeguards Technical Manual. In this paper the implementation of INSPECT at the Safeguards Division of CNEN, and the main characteristics of INSPECT are described. The potential applications of INSPECT to the nuclear material accountability is presented. (Author) [pt

  9. General catalogue of products and services - geology. AERO data base. 2. ed.

    International Nuclear Information System (INIS)

    1995-01-01

    The catalogue in the second edition aims at presenting to the user a general idea on the aerogeophysical projects of Brazil database (AERO) which belongs to SIGA (Brazilian geological information system). The 151 documents (projects) are listed as follows: 52 projects performed by CPRM/DNPM - Departamento Nacional de Producao Mineral; 33 projects performed by CNEN - Commissao Nacional de Energia Nuclear and NUCLEBRAS; 7 projects executed by State government and private companies; and 59 projects executed for PETROBRAS

  10. Bibliographic survey on methodologies for development of health database of the population in case of cancer occurrences

    International Nuclear Information System (INIS)

    Cavinato, Christianne C.; Andrade, Delvonei A. de; Sabundjian, Gaiane; Diz, Maria Del Pilar E.

    2014-01-01

    The objective is to make a survey of existing methodologies and for the development of public health database, focusing on health (fatal and nonfatal cancer) of the population surrounding a nuclear facility, for purposes of calculating the environmental cost of the same. From methodologies found to develop this type of database, a methodology will be developed to be applied to the internal public of IPEN/CNEN-SP, Brazil, as a pre-test for the acquisition of health information desired

  11. Benchmarks solutions of the coupled systems NJOY/AMPX-II/HAMMER-TECHNION and the library JENDL-3

    International Nuclear Information System (INIS)

    Santos, A. dos

    1991-01-01

    Benchmarks calculations were performed with the newest released japanese nuclear data library JENDL-3. The calculations were performed with the methodology developed at IPEN/CNEN-SP based on a coupled NJOY/AMPX-II/HAMMER-TECHNION system. The analyses show that the long-standing problem of the overprediction of the epithermal U-238 neutron capture still remains. Besides that there is an indication that the fission cross section of U-238 might be underestimated. (author)

  12. Irradiation experience of IPEN fuel at IEA-R1 research reactor

    International Nuclear Information System (INIS)

    Perrotta, Jose A.; Neto, Adolfo; Durazzo, Michelangelo; Souza, Jose A.B. de; Frajndlich, Roberto

    1998-01-01

    IPEN/CNEN-SP produces, for its IEA-R1 Research Reactor, MTR fuel assemblies based on U 3 O 8 -Al dispersion fuel type. Since 1985 a qualification program on these fuel assemblies has been performed. Average 235 U burnup of 30% and peak burnup of 50% was already achieved by these fuel assemblies. This paper presents some results acquire, by these fuel assemblies, under irradiation at IEA-R1 Research Reactor. (author)

  13. Proposal for implanting a magnetic stable isotope separator

    International Nuclear Information System (INIS)

    Lemos, O.F.

    1988-07-01

    The implantation of an electromagnetic isotope separator able to separate elements of mass from 20 to 250 a.m.u., with an enrichment factor from 10 to 200 times the initial concentration, depending on the elements, is proposed. The most suitable separator type for Brazilian CNEN, considering building installations and minimum conditions for the equipment facilities, the retinue chronogram, the infrastructure, and the personnel training for operation is defined. (M.C.K.) [pt

  14. Reactor parameters and constants determination by using measurements in subcritical and exponential assembly

    International Nuclear Information System (INIS)

    Voi, Dante Luiz; Santos Bastos, Wilma dos

    1995-01-01

    Subcritical and exponential experiments are important for Reactor Physics integral parameter determinations both to validate and confirm theoretical models for reactor calculations. An exponential and subcritical facility has been constructed to be used on the internal thermal column of the Argonauta reactor at IEN-CNEN- Rio de Janeiro. An experimental research program has been developed for the determination of fundamental reactor constants as buckling, migration areas, resonance escape probabilities, thermal utilization, fast fission and fuel eta factors. (author) 23 refs

  15. Quality control tests in dose calibrators used in research laboratories of IPEN

    International Nuclear Information System (INIS)

    Kuahara, Lilian T.; Junior, Amaury C.R.; Martins, Elaine W.; Dias, Carla R.; Correa, Eduardo de L.; Potiens, Maria da Penha A.

    2013-01-01

    The aim of this study was to do the intercomparison between two dose calibrators used in research laboratories at IPEN-CNEN / SP, one being the Capinted NPL-CRC, of the Laboratorio de Calibracao de Instrumentos (LCI) do IPEN, and the other Capintec CRC-15R of the Centro de Radiofarmacia (CR). The standard sources used for carrying out the comparing tests between the two laboratories were 57 Co, 133 Ba and the 13 7 C s

  16. Environmental Education in Brazil: Preventive Measures to Avoid Contamination with U and Th

    Science.gov (United States)

    da Silva Pastura, Valéria Fonseca; Wieland, Patricia

    2008-08-01

    Aiming at increasing awareness of radiation health effects, environmental issues and preventive measures, the Nuclear Energy National Commission (CNEN) launched in 2004 an education and public outreach programme for mine workers, students, teachers, governmental leaders, labor representatives and members of communities nearby small mining sites at the North and Northeast regions. Many Brazilian conventional mines present a significant risk of exposure to radiation due to Uranium and Thorium. CNEN inspects the mines but there are several small mining sites dedicated to open pit short term mineral extraction, called "garimpagem", that are of difficult control. Therefore, information at large about preventive measures to avoid contamination during exploration, transportation and storage is necessary. CNEN developed an educational campaign which includes a series of open seminars, talks, folders, booklets and posters. The objective of this paper is to present the Brazilian educational campaign to avoid contamination risks at those small mineral exploration sites and its results. This campaign is a joint task that receives collaboration of other organizations such as federal police, schools and universities.

  17. Constancy tests and quality assurance of the activimeters used in a radiopharmaceutical production unit

    International Nuclear Information System (INIS)

    Gontijo, Rodrigo M.G.; Mamede, Marcelo; Ferreira, Andréa V.; Nascimento, Leonardo T.C.; Costa, Flávia M.; Silva, Juliana B.

    2017-01-01

    Activimeters (or dose calibrators) are essential instruments to verify activity of radiopharmaceutical after production and also before the dose administration in humans or animals for molecular imaging. The efficiency and safety measurements depend on, beside other factors, constancy tests and quality assurance. Thereby, the aim of this work was to perform constancy tests and quality assurance in the activimeters of the UPPR/CDTN, based on the CNEN-NN 3.05 Brazilian standard and the manufacturer's manual. Physical inspection, auto zero, background check, camera voltage, data check and constancy test were done. In addition, accuracy and precision tests were performed using a set of standard certified radioactive sources ( 57 Co, 133 Ba and 137 Cs), according to the CNEN NN 3.05 Brazilian standard. Linearity test was also performed to evaluate the response of the equipment in over the entire range of activities used in routine. The equipment are periodically submitted to the quality control tests and the results were compared. After performing the proposed tests it is possible to conclude that activimeters are in accordance with the requirements of the CNEN standard and manufacturer's manual. A quality control checklist was prepared to guide users and to record the results of quality assurance testing to monitor the equipment performance. This initiative is part of the quality assurance program implemented at UPPR. (author)

  18. Management of radioactive disused lightning rods

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Paulo de Oliveira; Silva, Fabio, E-mail: pos@cdtn.br, E-mail: silvaf@cdtn.br [Centro de Desenvolvimento da Energia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2013-07-01

    The manufacture of radioactive lightning rod was allowed from 1970 to 1989. This authorization was based on state-of-the art science of that time that verified that radioactive lightning rods had efficiency superior to the conventional lightning rods, denominated Franklin. However, the experience showed that their efficiency was not superior enough to justify the use of radioactive sources. Consequently, in 1989, the National Commission or Nuclear Energy - CNEN, issued the Resolution 04/89 from 04-19-1989, that forbidden the importation of {sup 241}Am tapes, assembling and commercialization of radioactive lightning-rods. The institutes of CNEN are responsible for receiving these lightning-rods and sending to the users procedures for removing and dispatch to the institutes. Therewith, these devices are kept away from the human being and environment. The Nuclear technology Development Center - CDTN and Institute for Energy and Nuclear Research - IPEN of CNEN, has built laboratories appropriate for dismantling such devices and store the {sup 241}Am tapes safely. Nowadays are being researched methodologies to evaluate the contamination levels of the frame for possible recycling and become better the management of these devices. (author)

  19. Constancy tests and quality assurance of the activimeters used in a radiopharmaceutical production unit

    Energy Technology Data Exchange (ETDEWEB)

    Gontijo, Rodrigo M.G.; Mamede, Marcelo [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Ferreira, Andréa V.; Nascimento, Leonardo T.C.; Costa, Flávia M.; Silva, Juliana B., E-mail: rodrigo.gontijo@cdtn.br, E-mail: mamede.mm@gmail.com [Universidade Federal de Minas Gerais (IMA/FM/UFMG), Belo Horizonte, MG (Brazil). Departamento de Anatomia e Imagem

    2017-07-01

    Activimeters (or dose calibrators) are essential instruments to verify activity of radiopharmaceutical after production and also before the dose administration in humans or animals for molecular imaging. The efficiency and safety measurements depend on, beside other factors, constancy tests and quality assurance. Thereby, the aim of this work was to perform constancy tests and quality assurance in the activimeters of the UPPR/CDTN, based on the CNEN-NN 3.05 Brazilian standard and the manufacturer's manual. Physical inspection, auto zero, background check, camera voltage, data check and constancy test were done. In addition, accuracy and precision tests were performed using a set of standard certified radioactive sources ({sup 57}Co, {sup 133}Ba and {sup 137}Cs), according to the CNEN NN 3.05 Brazilian standard. Linearity test was also performed to evaluate the response of the equipment in over the entire range of activities used in routine. The equipment are periodically submitted to the quality control tests and the results were compared. After performing the proposed tests it is possible to conclude that activimeters are in accordance with the requirements of the CNEN standard and manufacturer's manual. A quality control checklist was prepared to guide users and to record the results of quality assurance testing to monitor the equipment performance. This initiative is part of the quality assurance program implemented at UPPR. (author)

  20. Estimative of core damage frequency in IPEN'S IEA-R1 research reactor due to the initiating event of loss of coolant caused by large rupture in the pipe of the primary circuit

    International Nuclear Information System (INIS)

    Hirata, Daniel Massami; Sabundjian, Gaiane; Cabral, Eduardo Lobo Lustosa

    2009-01-01

    The National Commission of Nuclear Energy (CNEN), which is the Brazilian nuclear regulatory commission, imposes safety and licensing standards in order to ensure that the nuclear power plants operate in a safe way. For licensing a nuclear reactor one of the demands of CNEN is the simulation of some accidents and thermalhydraulic transients considered as design base to verify the integrity of the plant when submitted to adverse conditions. The accidents that must be simulated are those that present large probability to occur or those that can cause more serious consequences. According to the FSAR (Final Safety Analysis Report) the initiating event that can cause the largest damage in the core, of the IEA-R1 research reactor at IPEN-CNEN/SP, is the LOCA (Loss of Coolant Accident). The objective of this paper is estimate the frequency of the IEA-R1 core damage, caused by this initiating event. In this paper we analyze the accident evolution and performance of the systems which should mitigate this event: the Emergency Coolant Core System (ECCS) and the isolated pool system. They will be analyzed by means of the event tree. In this work the reliability of these systems are also quantified using the fault tree. (author)

  1. Establishment of cementation parameters of dried waste from evaporation coming from NPP operation

    International Nuclear Information System (INIS)

    Faria, Érica R.; Tello, Clédola C.O.; Costa, Bruna S.

    2017-01-01

    The radioactive wastes generated in Brazil are treated and sent to initial and intermediate storages. The 'Project RBMN' proposes the implantation of the Brazilian repository to receive and permanently dispose the low and intermediate level radioactive wastes. The CNEN NN 6.09 standard - Acceptance Criteria for Disposal of Low and Intermediate Radioactive Wastes (LIRW) - establishes the fundamental requirements to accept the wastes packages in the repository. The evaporator concentrate is one of liquid wastes generated in a Nuclear Power Plant (NPP) operation and usually it is cemented directly inside the packing. The objective of this research is to increase the amount of the incorporated waste in each package, using the drying process before the cementation, consequently reducing the volume of the waste to be disposed. Drying and cementation parameters were established in order to scale-up the process aiming at waste products that comply with the requirements of CNEN standard. The cementation of the resulting dry wastes was carried out with different formulations, varying the amount of cement, dry waste and water. These tests were analyzed in order to select the best products, with higher waste incorporation than current process and its complying the requirements of the standard CNEN NN 6.09. (author)

  2. Pu utilization in fast-breeder and in light-water reactors in Italy

    International Nuclear Information System (INIS)

    Mangiagalli, D.; Cicognani, F.; Pistella, F.; Testa, G.; Villani, A.; Ariemma, A.; Castelli, G.F.; Linari, A.; Paoletti Gualandi, M.; Musso, B.

    1977-01-01

    The paper illustrates the most important activities carried out in Italy for the development of fast breeder reactors and its fuel as well as for plutonium recycle in light water reactors. The Italian strategy is based, on one hand, on the short-term commercialization of fast breeder reactors, and on the other, on the adoption of the technology of the Phenix prototype whose further development will be ensured by the joint Italian and French efforts as insured by the important agreements signed by CNEN, NIRA (Nucleare Italiana Reattori Avanzati) and Italian manufacturing industries with CEA and the main French industries. The paper also includes the main results of the ENEL Demonstration Program on Pu prototypes introduced in the Garigliano BWR in 1968 and 1970, and of the destructive and non-destructive analyses on said fuel, as well as of the analyses carried out by CNEN on prototypical fuel fabricated by CNEN and irradiated in various reactors. Furthermore, the paper deals with design and licensing aspects of the 46 Pu-island assembly reload introduced in the Garigliano reactors in 1975 and of a batch of 8 all Pu assemblies loaded in the Trino Vercellese PWR in 1976. Subsequently, the experimental activities planned for the near future both on high burn-up prototypes and on industrial fuel after one cycle of operation are examined [fr

  3. Study and survey of assembling parameters to a radioactive source production laboratory used to verify equipment

    International Nuclear Information System (INIS)

    Gauglitz, Erica

    2010-01-01

    This paper presents a survey of parameters for the proper and safe flooring, doors, windows, fume hoods and others, in a radiochemical laboratory. The layout of each item follows guidelines and national standards of the National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), aiming to ensure the radiological protection of workers and environment. The adequate items arrangement in the radiochemical laboratory ensures quality and safety in the production of 57 Co 137 Cs and 133 Ba radioactive sealed sources, with activities 185, 9.3 and 5.4 MBq, respectively. These sources are used to verify meter activity equipment and should be available throughout the Nuclear Medicine Center, following the recommendations of CNEN-NN-3.05 standard R equirements for Radiation Protection and Safety Services for Nuclear Medicine , to verify the activity of radiopharmaceuticals that are administered in patients, for diagnosis and therapy. Verification of measuring activity equipment will be used to perform accuracy, reproducibility and linearity tests, which should show results within the limits specified in the standard CNEN-NN-3.05. (author)

  4. Suggestion for improvement of PET quality control tests in Brazil

    International Nuclear Information System (INIS)

    Ferreira, Fernanda C.L.; Magalhaes, Cinthia M.S.; Souza, Divanizia N.

    2009-01-01

    Nowadays nuclear medicine has a considerable importance among the other medical specialties. This medical specialty utilizes high-tech equipment for imaging in the diagnosis, obtaining information on the clinical functionality of organs and systems of the human body through the use of radioisotopes . In view of the importance of guaranteeing the image quality in SPECT and PET systems, enabling patients not repeat exams due to lack of quality control of equipment used in nuclear medicine, this paper aims to present a possible suggestion to update the quality control tests needed for quality assurance of nuclear medicine services. They were considered the requirements of the National Commission of Nuclear Energy (CNEN) and the National Health Surveillance Agency (ANVISA) in Brazil. The minimum requirements to be defined for inclusion of quality control tests on PET in the standard CNEN are extremely important because they will guide the evaluation of PET systems, determining the quality control tests to be performed. And those tests for PET will be a regulatory requirement by the CNEN and ANVISA. As the National Health Surveillance Agency has already publication of RDC 38 with recommendations for services of nuclear medicine. This study will continue with evaluation of PET systems and presenting the tests of quality control with additional objects and simulators to ensure safety in PET systems have not standardized in nuclear medicine services in Brazil. (author)

  5. Goiania, ten years later. Proceedings of an international conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    Following the radiological accident that happened in Goiania, Brazil, in late 1987, the Brazilian National Nuclear Energy Commission (CNEN) was able to turn to the international community for assistance under the terms of the 1986 IAEA sponsored Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency; this marked the first time the convention was invoked. Additionally, to prevent the loss of useful information, CNEN and the IAEA designated a panel of international experts to investigate the causes and consequences of the accident and draw up a comprehensive report, `The Radiological Accident in Goiania`, which the IAEA published in 1988. Under its nuclear safety programme, it is the IAEA`s intention to follow up serious radiological accidents with review and analysis, to document the causes and circumstances and to disseminate conclusions, lessons to be learned and recommendations from which all States may benefit. A decade after the Goiania accident, the CNEN convened the international conference `Goiania, Ten Years Later` in co-operation with the IAEA. The purpose of this conference was to share with the local population and the international community the knowledge gained during this tragic event and in the following years. The conference attracted some 400 participants from 17 countries (Argentina, Austria, Brazil, Canada, Cuba, El Salvador, Estonia, Germany, Israel, Italy, Mexico, Peru, Russian Federation, Spain, Uruguay, United States of America and Venezuela). The present IAEA proceedings contain some 50 papers selected for publication by the editorial committee of the conference Refs, figs, tabs

  6. Goiania, ten years later. Proceedings of an international conference

    International Nuclear Information System (INIS)

    1998-12-01

    Following the radiological accident that happened in Goiania, Brazil, in late 1987, the Brazilian National Nuclear Energy Commission (CNEN) was able to turn to the international community for assistance under the terms of the 1986 IAEA sponsored Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency; this marked the first time the convention was invoked. Additionally, to prevent the loss of useful information, CNEN and the IAEA designated a panel of international experts to investigate the causes and consequences of the accident and draw up a comprehensive report, 'The Radiological Accident in Goiania', which the IAEA published in 1988. Under its nuclear safety programme, it is the IAEA's intention to follow up serious radiological accidents with review and analysis, to document the causes and circumstances and to disseminate conclusions, lessons to be learned and recommendations from which all States may benefit. A decade after the Goiania accident, the CNEN convened the international conference 'Goiania, Ten Years Later' in co-operation with the IAEA. The purpose of this conference was to share with the local population and the international community the knowledge gained during this tragic event and in the following years. The conference attracted some 400 participants from 17 countries (Argentina, Austria, Brazil, Canada, Cuba, El Salvador, Estonia, Germany, Israel, Italy, Mexico, Peru, Russian Federation, Spain, Uruguay, United States of America and Venezuela). The present IAEA proceedings contain some 50 papers selected for publication by the editorial committee of the conference

  7. Establishment of cementation parameters of dried waste from evaporation coming from NPP operation

    Energy Technology Data Exchange (ETDEWEB)

    Faria, Érica R.; Tello, Clédola C.O., E-mail: erica.engqui@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte/MG (Brazil); Costa, Bruna S., E-mail: brusilveirac@gmail.com [Universidade Federal de Minas Gerais, Belo Horizonte, MG (Brazil)

    2017-07-01

    The radioactive wastes generated in Brazil are treated and sent to initial and intermediate storages. The 'Project RBMN' proposes the implantation of the Brazilian repository to receive and permanently dispose the low and intermediate level radioactive wastes. The CNEN NN 6.09 standard - Acceptance Criteria for Disposal of Low and Intermediate Radioactive Wastes (LIRW) - establishes the fundamental requirements to accept the wastes packages in the repository. The evaporator concentrate is one of liquid wastes generated in a Nuclear Power Plant (NPP) operation and usually it is cemented directly inside the packing. The objective of this research is to increase the amount of the incorporated waste in each package, using the drying process before the cementation, consequently reducing the volume of the waste to be disposed. Drying and cementation parameters were established in order to scale-up the process aiming at waste products that comply with the requirements of CNEN standard. The cementation of the resulting dry wastes was carried out with different formulations, varying the amount of cement, dry waste and water. These tests were analyzed in order to select the best products, with higher waste incorporation than current process and its complying the requirements of the standard CNEN NN 6.09. (author)

  8. Environmental radiological impact of a Brazilian deactivated Uranium Mine along the period 1999-2009

    International Nuclear Information System (INIS)

    Pereira, W.S.; Kelecom, A.; Silva, A.X.

    2015-01-01

    This study aims to assess the environmental radiological impact (ERI) from the release of wastewaters used by the Mining Industrial Complex at Poços de Caldas (CIPC), today called Ore Treatment Unit (UTM) in Caldas, MG, Brazil, during the period 1999-2009. The effluent waters were analyzed once a week at point 014 (associated with the mine and waste pile 8). Critical radionuclides are 238 U, 226 Ra, 210 Pb, 232 Th and 228 Ra. The 238 U and 232 Th were analyzed by spectrophotometry. The 226 Ra, 210 Pb and 228 Ra, in turn, were analyzed by radiochemical separation methods and subsequent radiometry. The dose estimates were based on the model proposed by the National Nuclear Energy Commission (CNEN) for a hypothetical critical group associated with the point of effluents release into the river Ribeirao das Antas (point 014). The maximum dose rate allowed by CNEN for release is equal to 0.3 mSv·y -1 for individuals of the critical group. Our calculations were performed using the average concentration along the ten years period study. The estimated dose value for the individual of the critical group was 0.12 mSv·y -1 . It may be concluded that the reference levels established by CNEN were not reached. This indicates that the treatment of effluents generated by the CIPC/UTM was conducted efficiently, ensuring the safety of the population living in the surroundings of the Ore Processing Unit (UTM) at Caldas. (author)

  9. Some legal aspects related implementation at Brazil of the International Atomic Energy Agency recommendations related to radiation protection

    International Nuclear Information System (INIS)

    Mezrahi, Arnaldo; Matos, Gilberto Cardoso de; Wieland, Patricia

    2002-01-01

    The National Nuclear Energy Commission (CNEN) - the Brazilian nuclear regulatory authority- applies the basic guidelines regarding Radiation Protection (CNEN standard NE-3.01) in force since June 1988, for the licensing and control of nuclear, industrial, medical and research facilities, as well as for the safety of sources and for radioactive material transportation. In 1996, the IAEA published a new recommendations that established patterns for protection against ionizing radiation and for the safety of radiation sources and recommended Member States to adopt them. The adoption of the IAEA document, namely Safety Series 115, by a member state, does not imply to follow the whole text. The application of IAEA recommendations, contained in its documents, should take into consideration the autochthonous characteristics of each Member State. The Safety Series 115 has a very broad scope involving recommendation to countries at different development stages, especially those that do not even have a nuclear regulatory authority. In the specific case of Brazil, besides its advanced technological level, there exists a very complex and effective legal framework that hinders the establishment of norms and regulations regarding radiation protection guidelines. Therefore the direct application of the IAEA's recommendations requires a very careful legal evaluation in order to avoid conflicts of competence and duplication of efforts among the different involved authorities. This paper presents some of the important legal aspects especially in what concerns CNEN's competence, which is responsible for the issuance of the new radiation protection guidelines in accordance with the legislation. (author)

  10. Environmental Education in Brazil: Preventive Measures to Avoid Contamination with U and Th

    International Nuclear Information System (INIS)

    Silva Pastura, Valeria Fonseca da; Wieland, Patricia

    2008-01-01

    Aiming at increasing awareness of radiation health effects, environmental issues and preventive measures, the Nuclear Energy National Commission (CNEN) launched in 2004 an education and public outreach programme for mine workers, students, teachers, governmental leaders, labor representatives and members of communities nearby small mining sites at the North and Northeast regions. Many Brazilian conventional mines present a significant risk of exposure to radiation due to Uranium and Thorium. CNEN inspects the mines but there are several small mining sites dedicated to open pit short term mineral extraction, called 'garimpagem', that are of difficult control. Therefore, information at large about preventive measures to avoid contamination during exploration, transportation and storage is necessary. CNEN developed an educational campaign which includes a series of open seminars, talks, folders, booklets and posters. The objective of this paper is to present the Brazilian educational campaign to avoid contamination risks at those small mineral exploration sites and its results. This campaign is a joint task that receives collaboration of other organizations such as federal police, schools and universities

  11. Management of radioactive disused lightning rods

    International Nuclear Information System (INIS)

    Santos, Paulo de Oliveira; Silva, Fabio

    2013-01-01

    The manufacture of radioactive lightning rod was allowed from 1970 to 1989. This authorization was based on state-of-the art science of that time that verified that radioactive lightning rods had efficiency superior to the conventional lightning rods, denominated Franklin. However, the experience showed that their efficiency was not superior enough to justify the use of radioactive sources. Consequently, in 1989, the National Commission or Nuclear Energy - CNEN, issued the Resolution 04/89 from 04-19-1989, that forbidden the importation of 241 Am tapes, assembling and commercialization of radioactive lightning-rods. The institutes of CNEN are responsible for receiving these lightning-rods and sending to the users procedures for removing and dispatch to the institutes. Therewith, these devices are kept away from the human being and environment. The Nuclear technology Development Center - CDTN and Institute for Energy and Nuclear Research - IPEN of CNEN, has built laboratories appropriate for dismantling such devices and store the 241 Am tapes safely. Nowadays are being researched methodologies to evaluate the contamination levels of the frame for possible recycling and become better the management of these devices. (author)

  12. Application of nondestructive methods for qualification of high density fuels in the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Silva, Jose E.R.; Silva, Antonio T.; Domingos, Douglas B.; Terremoto, Luis A.A.

    2011-01-01

    IPEN/CNEN-SP manufactures fuels to be used in its research reactor - the IEA-R1. To qualify those fuels, it is necessary to check if they have a good performance under irradiation. As Brazil still does not have nuclear research reactors with high neutron fluxes, or suitable hot cells for carrying out post-irradiation examination of nuclear fuels, IPEN/CNEN-SP has conducted a fuel qualification program based on the use of uranium compounds (U 3 O 8 and U 3 Si 2 dispersed in Al matrix) internationally tested and qualified to be used in research reactors, and has attained experience in the technological development stages for the manufacturing of fuel plates, irradiation and non-destructive post-irradiation testing. Fuel elements containing low volume fractions of fuel in the dispersion were manufactured and irradiated successfully directly in the core of the IEA-R1. However, there are plans at IPEN/CNEN-SP to increase the uranium density of the fuels. Ten fuel miniplates (five containing U 3 O 8 -Al and five containing U 3 Si 2 -Al), with densities of 3.2 gU/cm 3 and 4.8 gU/cm 3 respectively, are being irradiated inside an irradiation device placed in a peripheral position of the IEA-R1 core. Non-destructive methods will be used to evaluate irradiation performance of the fuel miniplates after successive cycles of irradiation, by means: monitoring the reactor parameters during operation; periodic underwater visual inspection of fuel miniplates, eventual sipping test for fuel miniplates suspected of leakage and underwater measuring of the miniplate thickness for assessment of the fuel miniplate swelling. (author)

  13. Project of an information integrated system to provide support to the regulatory control of the radioactive waste inventory

    International Nuclear Information System (INIS)

    Christovao, Marilia Tavares

    2005-05-01

    Sources and radioactive waste deriving from industry activities, medical practice and other areas are collected, received, and stored as waste on Brazilian Nuclear Energy Commission (CNEN) Institutes, that also generate, treat and store their own radioactive waste. The object of this project is to present an Integrated Information System named SICORR, having as guidelines, the referred processes to the radioactive waste regulatory control, under the responsibility of the Radioactive Waste Division (DIREJ), the General Coordination of Licensing and Control (CGLC), the Directorate of Safety and Radiation Protection (DRS) and the CNEN. The main objective of the work was reached, once the project SICORR modeling considers the radioactive waste control inventory, enclosing the treatment and integration of the radioactive waste and the radionuclides data and processes; the installations that produce, use, transport or store radiation sources data; and, CNEN Institutes responsible for the radioactive waste management data. The SICORR functions or essential modules involve the data treatment, integration, standardization and consistency between the processes. The SICORR specification and the analysis results are registered in documents, Software Specification Proposal (PESw) and Software Requirements Specification (ERSw), and are presented in text, in diagrams and user interfaces. Use cases have been used in the SICORR context diagram. The user interfaces for each use case have been detailed, defining the graphical layout, the relationships description with other interfaces, the interface details properties and the commands and the product entrances and exits. For objects radioactive waste and radionuclides, states diagrams have been drawn. The activities diagram represents the business model process. The class diagram represents the static objects and relationships that exist between them, under the specification point of view. The class diagram have been determined

  14. Environmental radiological impact of a Brazilian deactivated Uranium Mine along the period 1999-2009

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, W.S., E-mail: wspereira@inb.gov.br [Industrias Nucleares do Brasil (FCN/GMR/INB), Resende, RJ (Brazil). Fabrica de Combustivel Nuclear. Grupo Multidisciplinar de Radioprotecao; Kelecom, A., E-mail: lararapls@hotmail.com [Universidade Federal Fluminense (LARARA-PLS/UFF), Niteroi, RJ (Brazil). Laboratorio de Radiobiologia e Radiometria Pedro Lopes dos Santos; Silva, A.X., E-mail: ademir@con.ufrj.br [Corrdenacao dos Programas de Pos-Graduacao em Engenharia (COPPE), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear. Departamento de Engenharia Nuclear

    2015-07-01

    This study aims to assess the environmental radiological impact (ERI) from the release of wastewaters used by the Mining Industrial Complex at Poços de Caldas (CIPC), today called Ore Treatment Unit (UTM) in Caldas, MG, Brazil, during the period 1999-2009. The effluent waters were analyzed once a week at point 014 (associated with the mine and waste pile 8). Critical radionuclides are {sup 238}U, {sup 226}Ra, {sup 210}Pb, {sup 232}Th and {sup 228}Ra. The {sup 238}U and {sup 232}Th were analyzed by spectrophotometry. The {sup 226}Ra, {sup 210}Pb and {sup 228}Ra, in turn, were analyzed by radiochemical separation methods and subsequent radiometry. The dose estimates were based on the model proposed by the National Nuclear Energy Commission (CNEN) for a hypothetical critical group associated with the point of effluents release into the river Ribeirao das Antas (point 014). The maximum dose rate allowed by CNEN for release is equal to 0.3 mSv·y{sup -1}for individuals of the critical group. Our calculations were performed using the average concentration along the ten years period study. The estimated dose value for the individual of the critical group was 0.12 mSv·y{sup -1}. It may be concluded that the reference levels established by CNEN were not reached. This indicates that the treatment of effluents generated by the CIPC/UTM was conducted efficiently, ensuring the safety of the population living in the surroundings of the Ore Processing Unit (UTM) at Caldas. (author)

  15. Application of nondestructive methods for qualification of high density fuels in the IEA-R1 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Jose E.R.; Silva, Antonio T.; Domingos, Douglas B.; Terremoto, Luis A.A., E-mail: jersilva@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    IPEN/CNEN-SP manufactures fuels to be used in its research reactor - the IEA-R1. To qualify those fuels, it is necessary to check if they have a good performance under irradiation. As Brazil still does not have nuclear research reactors with high neutron fluxes, or suitable hot cells for carrying out post-irradiation examination of nuclear fuels, IPEN/CNEN-SP has conducted a fuel qualification program based on the use of uranium compounds (U{sub 3}O{sub 8} and U{sub 3}Si{sub 2} dispersed in Al matrix) internationally tested and qualified to be used in research reactors, and has attained experience in the technological development stages for the manufacturing of fuel plates, irradiation and non-destructive post-irradiation testing. Fuel elements containing low volume fractions of fuel in the dispersion were manufactured and irradiated successfully directly in the core of the IEA-R1. However, there are plans at IPEN/CNEN-SP to increase the uranium density of the fuels. Ten fuel miniplates (five containing U{sub 3}O{sub 8}-Al and five containing U{sub 3}Si{sub 2}-Al), with densities of 3.2 gU/cm{sup 3} and 4.8 gU/cm{sup 3} respectively, are being irradiated inside an irradiation device placed in a peripheral position of the IEA-R1 core. Non-destructive methods will be used to evaluate irradiation performance of the fuel miniplates after successive cycles of irradiation, by means: monitoring the reactor parameters during operation; periodic underwater visual inspection of fuel miniplates, eventual sipping test for fuel miniplates suspected of leakage and underwater measuring of the miniplate thickness for assessment of the fuel miniplate swelling. (author)

  16. A new Brazilian regulation for the security of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    Tavares, Renato L.A.; Filho, Josélio S.M.; Torres, Luiz F.B.; Lima, Alexandre R.; Lima, Fabiano P.C.

    2017-01-01

    The present paper aims to outline the challenges related to the elaboration and concepts involved in a regulatory transition from a purely prescriptive approach to a combined approach that mixes performance-based concepts and evaluation metrics based on statistical data of equipment and personnel. This methodology might represent an improvement compared to a purely prescriptive approach, in which the regulatory authority defines the measures to be taken by operators of nuclear facilities to prevent theft, sabotage events, and mitigate their consequences. The prescriptive approach, despite having the advantages of clarity in the definition of requirements, simplicity in regulatory terms (inspections to verify compliance), and homogeneity in relation to various facilities, does not allow a clear and effective performance measurement, may provide insufficient or excessive security measures (with excessive expenditure of material and human resources), and the possibility of providing a false sense of security. It is known that, in many countries, the state-sponsored nuclear security regime mixes elements of the two mentioned approaches, prescriptive and based on performance, which is not Brazilian practice nowadays. Such methodological developments happened globally due to the increase of threat level for nuclear facilities and materials. The currently regulation in force is CNEN-NE 2.01, which provides a set of measures intended to implement Physical Protection Systems in Nuclear, Radiological Facilities as well as Transport Operations, and all documents related to security of such issues. The new regulation, named CNEN-NN 2.01, will focus only on Nuclear Material and Facilities (two other regulations specific for Security of Radioactive Sources and Transport Operations are under elaboration process). CNEN NN 2.01 is intended to provide further adherence to new international recommendations, e.g, IAEA INFCIRC 225 Rev.5 (NSS 13), which is currently regarded as the

  17. Organization and development of the Brazilian nuclear program

    International Nuclear Information System (INIS)

    Pinto, C. Syllus M.; Alves, R. Nazare; Lepecki, W.; Costa, H.M. da; Grinberg, M.; Grimberg, M.

    1977-01-01

    The paper presents the Brazilian Nuclear Energy Program: its development until the present stage, as well as the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - ELETROBRAS, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - NUCLEBRAS, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities as well as promotes the participation of the Brazilian industry in the nuclear field. Besides describing the new distribution of regulatory functions given by law to the CNEN, this paper gives special emphasis to the large industrial complex which is in the process of being established with the setting-up of the many NUCLEBRAS subsidiaries in joint-venture with German firms in the nuclear field, as a consequence of the Industrial Cooperation between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy signed between the two countries on June 27, 1975. The programs for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed, based on the Government's policy on the subject [es

  18. Project of an information integrated system to provide support to the regulatory control of the radioactive waste inventory; Projeto de um sistema integrado de informacao para suporte ao controle regulatorio do inventario de rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    Christovao, Marilia Tavares

    2005-05-15

    Sources and radioactive waste deriving from industry activities, medical practice and other areas are collected, received, and stored as waste on Brazilian Nuclear Energy Commission (CNEN) Institutes, that also generate, treat and store their own radioactive waste. The object of this project is to present an Integrated Information System named SICORR, having as guidelines, the referred processes to the radioactive waste regulatory control, under the responsibility of the Radioactive Waste Division (DIREJ), the General Coordination of Licensing and Control (CGLC), the Directorate of Safety and Radiation Protection (DRS) and the CNEN. The main objective of the work was reached, once the project SICORR modeling considers the radioactive waste control inventory, enclosing the treatment and integration of the radioactive waste and the radionuclides data and processes; the installations that produce, use, transport or store radiation sources data; and, CNEN Institutes responsible for the radioactive waste management data. The SICORR functions or essential modules involve the data treatment, integration, standardization and consistency between the processes. The SICORR specification and the analysis results are registered in documents, Software Specification Proposal (PESw) and Software Requirements Specification (ERSw), and are presented in text, in diagrams and user interfaces. Use cases have been used in the SICORR context diagram. The user interfaces for each use case have been detailed, defining the graphical layout, the relationships description with other interfaces, the interface details properties and the commands and the product entrances and exits. For objects radioactive waste and radionuclides, states diagrams have been drawn. The activities diagram represents the business model process. The class diagram represents the static objects and relationships that exist between them, under the specification point of view. The class diagram have been determined

  19. Italian activities in the field of uranium enrichment

    International Nuclear Information System (INIS)

    Bullio, P.

    1977-01-01

    The Italian effort on uranium enrichment is principally developed along the two classical processes: gaseous diffusion, centrifuges. Research, development and industrial activities play different role in the two methods; a special working group (GIAU) was established by CNEN to help coordinating this activity. In the field of gaseous diffusion, research and development effort, was, from the starting of the program in 1968, mainly devoted to barriers and compressors. The aim was to gain a full understanding of the process and to demonstrate the capability to overcome the main problems of this technology. Isotope separation of UF 6 was demonstrated in 1974 at an experimental plant level. Cost sharing contracts were signed between CNEN and industries to build prototypes and ''first of a kind'' components; small production lines have been set up to evaluate economics and assess production quality: Eurodif is partially associated with the development of this activity. On the industrial level Agip Nucleare and CNEN were among the promoters of the Eurodif venture from the beginning in 1973 and now own 25% of the shares. In the field of ultracentrifugation the work is still devoted mainly to research and development on the machines. The demonstration of the separation process has been achieved in 1973 at laboratory level with a Zippe type centrifuge. Further on, work has been aimed to the development of high capacity machines and different solutions are under close scrutiny. Carbon fibers and multiple rotors machines have been mechanically tested; the first reference design of small cascade plant has been completed. In the field of laser separation, after a complete and critical survey of different process under development abroad, experimental research work is now being undertaken; experiments on basic aspects of the process are in progress [fr

  20. Radiation exposure to workers at cyclotron facilities

    International Nuclear Information System (INIS)

    Ribeiro, M.S.; Sanches, M.P.; Sanchez, A.S.; Rodrigues, D.L.

    2001-01-01

    Radiopharmaceuticals quickly furnish the information doctors need to establish a precise diagnosis of the patient's condition, and therefore to prescribe the most effective therapy. In cancerology, F18-FDG, the most widely used PET imaging tracer, excels in the early detection of cancer tumors, even very tiny ones, which it locates and clearly distinguishes from healthy surrounding tissues. IPEN-CNEN/SP has two cyclotron accelerators used mainly for radioisotope production to be utilized in nuclear medicine for diagnosis and therapy. The first is a CV-28 cyclotron, variable energy that came into operation in 1982, which was used to produce F18-FDG and Iodine 123 up to 1998. The second, a Cyclone 30 cyclotron, 30 MeV, commenced operation in 1998 for certification purpose, and due to increase demand for radiopharmaceuticals in Brazil, started F18-FDG production in 1999. Cyclotron Laboratory will be a reference Research and Developing Center in our country and will help the Brazilian and Latin-American community. It is necessary to have an adequate database to allow regular follow up and analysis of the individual dose distributions for each group involved in the cyclotron activities. These databases are also important means to assess the effectiveness of efforts in order to maintain doses ALARA and reduce inequalities. The official individual occupational dosimetry is provided by certified Laboratory of Thermoluminescent Dosimetry at IPEN-CNEN/SP. This paper describes the occupational doses distribution in Laboratory of Cyclotrons at IPEN-CNEN/SP from January, 1998 to July, 2000 and propose improvements for the future. (author)