Navegação por Autores IPEN "MADI FILHO, TUFIC"

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  • IPEN-DOC 23875

    MADI FILHO, TUFIC ; CARDENAS, JOSE P.N. ; PETRI, ANNA R. ; SANTOS, ROBINSON A. dos ; MARTINS, JOAO F.T. ; CARVALHO, DIEGO V.S.; ALVARENGA, T.; BELLEZZO, M.; LARANJO, G.; LIMA, M.; OLIVEIRA, P.; PEREIRA, MARIA da C.C. . Am-Be neutron irradiator used for nuclear instrumentation training. In: INTERNATIONAL CONFERENCE ON ADVANCEMENTS IN NUCLEAR INSTRUMENTATION, MEASUREMENT METHODS AND THEIR APPLICATIONS, 3rd, June 23-27, 2013, Marseille, France. Proceedings... Piscataway, NJ: IEEE, 2013.

    Abstract: A neutron irradiator was assembled at IPEN (Nuclear and Energy Research Institute) facility to perform qualitative-quantitative analysis of materials, using thermal and fast neutrons. In order to determine the 116mIn decay constant, a thermal flux obtained experimentally by Monte Carlo N-Particle Transport Code-MCNP, in a previous work, was used in the nuclear experiment. The activity calculated from the activation parameters was 13.51±0.17 kBq and the activity determined experimentally was 12.51± 0.36 kBq. The decay constant determined by the pulse height analyzer (PHA) measures was 211.4 μ·s-1, and that determined by fitting the data using a Multichannel Scaler (MCS) system was 200.3 ± 1.6 μ·s-1. The half-life of 116mIn found in the literature is 3256.8 s, which corresponds to a decay constant of 212.8 μ·s-1. The present experiment does not intend to establish a new value for the decay constant: it solely aims students’ practical exercises in nuclear properties of elements. This experiment is part of the nuclear experimental course.

    Palavras-Chave: half-life; indium 116; neutrons; nuclear decay; nuclear properties

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  • IPEN-DOC 27106

    RODRIGUES, ANTONIO C.I. ; MADI FILHO, TUFIC ; SILVA, DAVILSON G. da . Analysis and construction of the high density storage racks for spent fuel of the research reactor IEA-R1. RAD Conference Proceedings, v. 3, p. 123-126, 2018. DOI: 10.21175/RadProc.2018.27

    Abstract: The IEA-R1 research reactor works 40h weekly, with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions, the reactor operating for 32h/week will have 3 spent fuel by year, approximately 3 utilization rate Positions/year; thus, we will have only about six years of capacity for storage. Since the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel by doubling the wet storage in the reactor’s pool. 3M’s neutron absorber BoralcanTM was chosen after reviewing the literature about available materials for the construction of a new storage rack. This work presents studies for the construction of new storage racks with double of capacity using the same place of the current ones. Criticality safety analysis was performed with MCNP-5 Monte Carlo code, using two Evaluated Nuclear Data Files (ENDF/B-VI and ENDF/B-VII) in calculations, and subsequently, the results were compared. The full charge of the storage rack with only new fuel elements (maximum reactivity) was considered to calculate the keff. The results obtained in the simulations show that it is possible doubling the storage capacity of the spent fuel elements. Additionally, it complies with safety limits established by International Atomic Energy Agency (IAEA) and Brazilian Commission of Nuclear Energy (CNEN) standards to the criticality criteria (keff <0.95). This is only possible with the use of neutron absorber material.

    Palavras-Chave: research reactors; spent fuel storage; fuel racks; monte carlo method; boron; iear-1 reactor; fuel storage pools; fuel elements; storage

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  • IPEN-DOC 27084

    RODRIGUES, ANTONIO C.I. ; MADI FILHO, TUFIC ; SILVA, DAVILSON G. da . Analysis and project of the high density storage racks for spent fuel of the research reactor IEA-R1. In: INTERNATIONAL CONFERENCE ON RADIATION AND APPLICATIONS IN VARIOUS FIELDS OF RESEARCH, 6th, June 18-22, 2018, Ohrid, Macedonia. Abstract... Niš, Serbia: RAD Association, 2018. p. 143-143.

    Abstract: The IEA-R1 research reactor works 40h weekly with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions (current conditions of reactor operation 32h weekly will have 3 spend fuel by year, then, approximately 3 utilization rate Positions/year). Thus, we will have only about six years of capacity for storage. Whereas the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel. Hence, it is necessary to double the wet storage capacity (storage in the IEA-R1 reactor’s pool). After reviewing the literature about materials available for use in the construction of the new storage rack with absorber of neutrons, the BoralcanTM (manufactured by 3M) was chosen, due to its properties. This work presents studies: (a) for the construction of new storages racks with double of the current capacity using the same place of current storages racks and (b) criticality analysis using the MCNP-5 code. Two American Nuclear Data Libraries were used: ENDF / B-VI and ENDF / B-VII, and the results obtained for each data bases were compared. These analyzes confirm the possibility of doubling the storage capacity of fuel elements burned in the same place occupied by the current storage rack attending to the IEA-R1 reactor needs and attending the safety requirements according to the National Nuclear Energy Commission – CNEN and the International Atomic Energy Agency (IAEA). To calculate the keff new fuel elements (maximum possible reactivity) used in full charge of the storage rack were considered. With the results obtained in the simulation we can conclude that doubling the amount of racks for spent fuel elements are complied with safety limits established in the IAEA standards and CNEN of criticality (keff <0.95). It is mandatory to use neutron absorber material.

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  • IPEN-DOC 17113

    MADI FILHO, TUFIC ; NAHUEL CARDENAS, JOSE P. ; RODRIGUES, ANTONIO C.I. . Application of prompt gamma source for n-16 detector system calibration. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 10th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 17th; MEETING ON NUCLEAR INDUSTRY, 2nd, October 24-28, 2011, Belo Horizonte, MG. Proceedings... Sao Paulo: ABEN, 2011, 2011.

    Palavras-Chave: iear-1 reactor; prompt gamma radiation; pvc; americium; beryllium; neutron flux; calibration; nitrogen 16; radiation detectors

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  • IPEN-DOC 19341

    RODRIGUES, ANTONIO C.I. ; MADI FILHO, TUFIC ; RICCI FILHO, WALTER . Borated stainless steel storage project to the spent fuel of the IEA-R1 reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 11th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 18th; MEETING ON NUCLEAR INDUSTRY, 3rd, November 24-29, 2013, Recife, PE. Proceedings... Sao Paulo: ABEN, 2013, 2013.

    Palavras-Chave: borates; capacity; design; fuel racks; iaea; iear-1 reactor; recommendations; spent fuel elements; spent fuel storage; stainless steels

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  • IPEN-DOC 18894

    TONDIN, JULIO B.M. ; MADI FILHO, TUFIC . Burn-up and operation time of fuel elements produced in IPEN. In: VANIN, VITO R. (Ed.) BRAZILIAN WORKSHOP ON NUCLEAR PHYSICS, 32rd, September 7-11, 2010, Campos do Jordão, SP. Proceedings... American Institute of Physics, 2010. p. 397-400.

    Palavras-Chave: burnup; brazilian cnen; fission; fuel elements; iear-1 reactor; materials testing; nuclear fuels; operation; plates; reactor control systems; reactor fueling; reactor safety; uranium 235

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  • IPEN-DOC 28372

    PEREIRA, MARIA da C.C. ; MADI FILHO, TUFIC ; BERRETTA, JOSE R. ; TOMAZ, LUCAS F. . Characteristics of PB2+ doped CsI matrix under gamma and neutron excitations. In: HOLZMANN, HENRIQUE A. (Org.); DALLAMUTA, JOAO (Org.). Engenharias: da genialidade à profissão e seu desenvolvimento 2. Ponta Grossa, PR: Atena Editora, 2021. cap. 11. DOI: 10.22533/at.ed.246211811

    Abstract: In recent years, there has been an increasing interest in finding new fast scintillating material or improve the characteristics of known scintillatorsfor the demand of high energy physics, industrial and nuclear medical applications. Divalent lead ions Pb2+ built in some crystal structures are efficient emission centers and their applications in scintillators wereand arestill the reason of an intensive study of emission properties of different compounds containing these ions. In this context, the crystals of Pb2+ doped CsI matrix were grown by the vertical Bridgman techniqueandsubjected to annealing in vacuum of 10-6 mbar and constanttemperatureof 350°C, for 24 hours, and then they were employed. To evaluate the response of the CsI:Pb scintillator crystal to gamma radiation, radioactive sources of 137Cs (662 keV), 60Co (1173 keV and 1333 keV), 22Na (511 keV and 1275 keV) and 133Ba (355 keV) wereused. The operating voltage of the photomultiplier was 2700 V for the detection of gamma rays and the accumulation time in the counting process was 600 s. The scintillator response to neutron radiation from a radioactive source of AmBe with energy range of 1 to 12 MeV was available. The activity of the AmBe source was 1 Ci Am. The emission ratewas 2.2x 106 neutrons/ second. The operating voltage of the photomultiplier tube was 1300 V. The accumulation time in the counting process was 600 s. With the results obtained, it may be observed that the crystals are sensitive to these radiations.

    Palavras-Chave: annealing; barium 122; bridgman method; cesium 137; cesium iodides; cobalt 60; crystals; doped materials; lead; luminescence; scintillations; sodium 22

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  • IPEN-DOC 24134

    PEREIRA, MARIA da C.C. ; MADI FILHO, TUFIC ; BERRETTA, JOSE R. ; TOMAZ, LUCAS F. ; PINTO, MARLENE C. . Characteristics of Pb2+ doped CsI matriz under gamma and neutron excitations. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017.

    Abstract: In recent years, there has been an increasing interest in finding new fast scintillating material or improve the characteristics of known scintillators for the demand of high energy physics, industrial and nuclear medical applications. Ions divalent lead Pb2+ built in some crystal structures are efficient emission centers and their applications in scintillators was and still is the reason of an intensive study of emission properties of different compounds containing these ions. The aggregation of impurities in CsI is poorly studied. The problem of impurity aggregation in CsI is of interest from point of view of the luminescent properties modification of this scintillation material. In this context, the crystals of Pb2+ doped CsI matrix were grown by the vertical Bridgman technique and subjected to annealing in vacuum of 10-6 mbar and continuous temperatura of 350°C, for 24 hours, and then they were employed. To evaluate the response of the CsI:Pb scintillator crystal to gamma radiation, radioactive sources of 137Cs (662 keV), 60Co (1173 keV and 1333 keV), 22Na (511 keV and 1275 keV) and 133Ba (355 keV) was used. The operating voltage of the photomultiplier was 2700 V for the detection of gamma rays and the accumulation time in the counting process was 600 s. The crystals used in gamma spectroscopy were cut with dimensions of 20 mm in diameter and 20 mm in height. The scintillator response to neutron radiation from a radioactive source of Am/Be with energy range of 1 MeV to 12 MeV was available. The activity of the AmBe source was 1Ci Am. The fluency was 2.6 x 106 neutrons / second. The operating voltage of the photomultiplier tube was 1300 V. The accumulation time in the counting process was 600 s. The scintillator crystals were cut with dimensions of 20 mm diameter and 10 mm height. With the results obtained, it may be observed that the crystals are sensitive to these radiations.

    Palavras-Chave: annealing; barium 122; bridgman method; cesium 137; cesium iodides; cobalt 60; crystals; doped materials; gamma radiation; gamma spectroscopy; lead; sodium 22

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  • IPEN-DOC 24773

    PEREIRA, MARIA da C.C. ; MADI FILHO, TUFIC ; BERRETTA, JOSE R. ; MESQUITA, CARLOS H. de . Characteristics of the CsI:Tl scintillator crystal for X-Ray imaging applications. Materials Sciences and Applications, v. 9, n. 2, p. 268-280, 2018. DOI: 10.4236/msa.2018.92018

    Abstract: Scintillators are high-density luminescent materials that convert X-rays to visible light. Thallium doped cesium iodide (CsI:Tl) scintillation materials are widely used as converters for X-rays into visible light, with very high conversion efficiency of 64.000 optical photons/MeV. CsI:Tl crystals are commercially available, but, the possibility of developing these crystals into different geometric shapes, meeting the need for coupling the photosensor and reducing cost, makes this material very attractive for scientific research. The objective of this work was to study the feasibility of using radiation sensors, scintillators type, developed for use in imaging systems for X-rays. In this paper, the CsI:Tl scintillator crystal with nominal concentration of the 10−3 M was grown by the vertical Bridgman technique. The imaging performance of CsI:Tl scintillator was studied as a function of the design type and thickness, since it interferes with the light scattering and, hence, the detection efficiency plus final image resolution. The result of the diffraction X-ray analysis in the grown crystals was consistent with the pattern of a face-centered cubic (fcc) crystal structure. Slices 25 × 2 × 3 mm3 (length, thickness, height) of the crystal and mini crystals of 1 × 2 × 3 mm3 (length, thickness, height) were used for comparison in the imaging systems for X-rays. With these crystals scintillators, images of undesirable elements, such as metals in food packaging, were obtained. One-dimensional array of photodiodes and the photosensor CCD (Coupled Charge Device) component were used. In order to determine the ideal thickness of the slices of the scintillator crystal CsI:Tl, Monte Carlo method was used.

    Palavras-Chave: cesium iodides; doped materials; thallium ions; crystal growth; phosphors; image processing; photodiodes; charge-coupled devices

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  • IPEN-DOC 26204

    COSTA, PRISCILA ; RAELE, MARCUS P. ; DOMIENIKAN, CLAUDIO ; MADI FILHO, TUFIC ; ZAHN, GUILHERME S. ; GENEZINI, FREDERICO A. . Characterization of a portable thermal neutron detector. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 1163-1170.

    Abstract: A portable thermal neutron detector prototype, using a PIN-type silicon photodiode coupled to a boron converter, was developed at the Nuclear and Energy Research Institute (IPEN-CNEN/SP). Several boron layers were made by Pulsed Laser Deposition method and two different prototypes were made using distinct approaches in the associated electronics. The prototypes were characterized by measurements with the cold neutron beam at PHADES (Polarized 3He and Detector Experiment Station), in the NIST Center for Neutron Research. The distance between the prototype and the neutron source was different for each prototype: 70 cm (prototype one) and 7 cm (prototype two). The linearity behavior was verified for both prototypes in order to verify the relationship between counts and neutron fluence. The intrinsic efficiency values obtained for prototypes one and two were, respectively, (1.78 ± 0.01)% and (5.2 ± 0.4)%. The angular dependence was verified only for prototype one. The concept of this detector can be applied in a future dosimeter project.

    Palavras-Chave: thermal neutrons; photodiodes; portable equipment; silicon; cold neutrons; efficiency; neutron detectors; brazilian cnen

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  • IPEN-DOC 21137

    ROCHA, MARCELO S. ; CABRAL, EDUARDO L.L. ; SABUNDJIAN, GAIANE ; YORIYAZ, HELIO ; LIMA, ANA C.S.; BELCHIOR JUNIOR, ANTONIO ; PRADO, ADELK C. ; MADI FILHO, TUFIC ; ANDRADE, DELVONEI A. ; SHORTO, JULIAN M.B. ; MESQUITA, ROBERTO N. ; OTUBO, LARISSA ; BAPTISTA FILHO, BENEDITO D. ; PINHO, PRISCILA G.M.; RIBATSKY, GHERHARDT; MORAES, ANDERSON A.U. de. Characterization of physical properties of Alsub(2)Osub(3) and ZrOsub(2) nanofluids for heat transfer applications. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 12th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 19th; MEETING ON NUCLEAR INDUSTRY, 4th, October 4-9, 2015, São Paulo, SP. Proceedings... 2015.

    Palavras-Chave: aluminium oxides; zirconium oxides; physical properties; nanofluids; viscosity; cooling; heat transfer; scanning electron microscopy

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  • IPEN-DOC 26847

    COSTA, PRISCILA ; RAELE, MARCUS P. ; DOMIENIKAN, CLAUDIO ; COSTA, FABIO E. ; MADI FILHO, TUFIC ; ZAHN, GUILHERME S. ; GENEZINI, FREDERICO A. . A compact electronic system for a photodiode neutron detector. In: JAKSIC, ALEKSANDAR (Ed.); KARAMARKOVIC, JUGOSLAV (Ed.) INTERNATIONAL CONFERENCE ON RADIATION APPLICATIONS, September 16-19, 2019, Belgrade, Serbia. Abstract... Niš, Serbia: Sievert Association, 2019. p. 36-36.

    Abstract: The demand for portable neutron detectors is on the rise, and for that purpose, low cost boron-10 has been frequently used instead of helium-3, which is usually employed in large and expensive detectors. Portable detectors are of interest in some applications, such as neutron dosimeters or inspection systems targeted in the detection of fissile material and drugs in airports. In this work a portable thermal neutron detection system was developed which is based on a commercial silicon photodiode coupled to a boron converter; this prototype is then plugged into a portable electronic system. The boron layer was produced by pulsed laser deposition, either on a thin glass slide or on the photodiode itself. The boron deposition in the photodiode was made directly in the active area of the detector, so before and after the deposition process a characterization of the device regarding both the dark current and the operation voltage was performed using an americium source. Finally, both configurations were tested. The neutron detection process occurs by detecting the alpha and lithium particles produced by the interaction of the incoming neutron with the boron-10 nuclides. These heavy ions then interact with the active area of the reverse-biased photodiode, producing an electric signal that has to be preamplified and then properly amplified by the portable electronic system, which in turn produces an output that can either be sent to a multichannel analyzer or to a digital counter. The integrated circuit of the low noise preamplifier transforms the detector’s current pulse into a voltage pulse with amplitude proportional to the charge carried by the current pulse. The shaper-driver consists of a differentiator and an integrator and is responsible for filtering and further amplifying the preamplifier signal, generating a NIM-compatible energy output pulse. The performance of the photodiode-amplifier set for alpha particles was successively tested using a 243Am radioactive source. Initial tests were made using the boron-deposited glass, and the electronic signal was properly read. However, when the same system was tested using the boron deposited directly in the photodiode, the output signal couldn’t be read, due to the fact that during the deposition process there was an increase in the dark current and a decrease in the operation bias. In this way, a new portable electronic system was developed using a hybrid integrated amplifier circuit. This new electronic setup allowed the use of both configurations, and was tested both with alpha-emitting Americium and neutron-emitting AmBe sources. In conclusion, both portable electronic systems have proven suitable for the thermal neutron detector developed.

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  • IPEN-DOC 26844

    RODRIGUES, ANTONIO C.I. ; MADI FILHO, TUFIC ; SILVA, DAVILSON G. da . Core modeling of the research reactor IEA-R1 with the MCNP-6.2 computational code. In: JAKSIC, ALEKSANDAR (Ed.); KARAMARKOVIC, JUGOSLAV (Ed.) INTERNATIONAL CONFERENCE ON RADIATION APPLICATIONS, September 16-19, 2019, Belgrade, Serbia. Abstract... Niš, Serbia: Sievert Association, 2019. p. 13-13.

    Abstract: The objective of this work is to develop the modeling of the IEA-R1 reactor core with the MCNP-6.2 computational code that was recently acquired. The main advantage of this new version of the code is the performance of burnup calculations of the fuel elements. This modeling will be valid by comparing the thermal and epithermal neutron flux obtained in the calculations with the MCNP-6.2 and the fluxes measured with the activation of gold foils (Au) with and without cadmium coating (Cd) in the same positions of irradiation and, with the same arrangement of fuel elements in the reactor core. After the validation of this model, the idea is to use it for the burnup calculations of the fuel elements that are fundamental for a correct management of the reactor core. Currently, the management of the core is carried out by deterministic codes that are very old and have many approximations leading to very conservative results, for example, TWODB, HAMMER, and CITATION.

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  • IPEN-DOC 12020

    PEREIRA, MARIA da C.C. ; MADI FILHO, TUFIC ; HAMADA, MARGARIDA M. . Dependence of scintillation characteristics in the CsI:Br cristals on Brsup(-) concentrations under gamma excitations. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 8th/ MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 15th, Sept. 30 - Oct. 5, 2007, Santos, SP. Proceedings... Sao Paulo: ABEN, 2007, 2007.

    Palavras-Chave: bridgman method; bromine additions; cesium iodides; crystal doping; crystal growth; energy resolution; energy spectra; experimental data; gamma radiation; kev range 100-1000; luminescence; microhardness

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  • IPEN-DOC 12023

    TETZNER, GUARACIABA de C.; HAMADA, MARGARIDA M. ; MADI FILHO, TUFIC ; VASQUEZ, PABLO A.S. ; RELA, PAULO R. ; CALVO, WILSON A.P. ; MESQUITA, CARLOS H. . Description of two tomography systems developed at IPEN-CNEN/SP. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 8th/ MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 15th, Sept. 30 - Oct. 5, 2007, Santos, SP. Proceedings... Sao Paulo: ABEN, 2007, 2007.

    Palavras-Chave: cobalt 60; computerized simulation; computerized tomography; experimental data; image processing; m codes; nai detectors; phantoms; plastic scintillators; polypropylene; resolution

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  • IPEN-DOC 12157

    MADI FILHO, TUFIC ; MARTINS, JOAO F.T.; HAMADA, MARGARIDA M. . Desenvolvimento de detector de plastico cintilador para medidas de neutrons. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 8th/ MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 15th, Sept. 30 - Oct. 5, 2007, Santos, SP. Proceedings... Sao Paulo: ABEN, 2007, 2007.

    Palavras-Chave: neutron beams; neutron detection; neutron detectors; neutron dosimetry; neutron monitors; plastic scintillation detectors; plastic scintillators

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  • IPEN-DOC 22118

    MARTINS, JOAO F.T. ; MADI FILHO, TUFIC ; HAMADA, MARGARIDA M. . Desenvolvimento de detector plástico cintilador para medidas de nêutrons. In: PROGRAMA INSTITUCIONAL DE BOLSAS DE INICIAÇÃO CIENTÍFICA, 13.; PROGRAMA DE BOLSAS E INICIAÇÃO CIENTÍFICA CNEN, 4., 29-30 de agosto, 2007, São Paulo, SP. Resumo expandido... 2007.

    Palavras-Chave: radiation detectors; neutron detection; neutron detectors; neutrons; plastic scintillation detectors

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  • IPEN-DOC 21086

    RODRIGUES, ANTONIO C.I. ; MADI FILHO, TUFIC ; SIQUEIRA, PAULO T.D. ; RICCI FILHO, WALTER . Design of a new wet storage rack for spent fuels from IEA-R1 reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 12th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 19th; MEETING ON NUCLEAR INDUSTRY, 4th, October 4-9, 2015, São Paulo, SP. Proceedings... 2015.

    Palavras-Chave: iear-1 reactor; wet storage; spent fuels; monte carlo method; aluminium; boron carbides; cladding; design; fuel elements; m codes

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  • IPEN-DOC 15620

    MADI FILHO, TUFIC . Detectores de neutrons. In: ZAMBONI, CIBELE B. (Coord.). Fundamentos da fisica de neutrons. Editora Livraria da Fisica: Sao Paulo, 2007, 2007. p. 19-30,

    Palavras-Chave: neutron detectors; neutron converters; matter; interactions; radiation detectors

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  • IPEN-DOC 12033

    MATEUS, NATALINA de F.; MADI FILHO, TUFIC . Determination of chemical elements in Eucalyptus grandis, manured with biosolid, by neutrons activation analysis. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 8th/ MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 15th, Sept. 30 - Oct. 5, 2007, Santos, SP. Proceedings... Sao Paulo: ABEN, 2007, 2007.

    Palavras-Chave: bromine; concentration ratio; eucalyptuses; experimental data; fertilizers; gamma spectroscopy; high-purity ge detectors; manganese; multi-element analysis; neutron activation analysis; potassium; sewage sludge; sodium

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✔ Na página inicial nas referências são sinalizados todos os autores IPEN, ao clicar nesse símbolo será aberta uma nova página correspondente à aquele autor – trata-se da página do pesquisador.

✔ Na página do pesquisador, é possível verificar, as variações do nome, a relação de todos os trabalhos com texto completo bem como um quadro resumo numérico; há links para o Currículo Lattes e o Google Acadêmico ( quando esse for informado).

ATENÇÃO!

ESTE TEXTO "AJUDA" ESTÁ SUJEITO A ATUALIZAÇÕES CONSTANTES, A MEDIDA QUE NOVAS FUNCIONALIDADES E RECURSOS DE BUSCA FOREM SENDO DESENVOLVIDOS PELAS EQUIPES DA BIBLIOTECA E DA INFORMÁTICA.

O gerenciamento do Repositório está a cargo da Biblioteca do IPEN. Constam neste RI, até o presente momento 20.950 itens que tanto podem ser artigos de periódicos ou de eventos nacionais e internacionais, dissertações e teses, livros, capítulo de livros e relatórios técnicos. Para participar do RI-IPEN é necessário que pelo menos um dos autores tenha vínculo acadêmico ou funcional com o Instituto. Nesta primeira etapa de funcionamento do RI, a coleta das publicações é realizada periodicamente pela equipe da Biblioteca do IPEN, extraindo os dados das bases internacionais tais como a Web of Science, Scopus, INIS, SciElo além de verificar o Currículo Lattes. O RI-IPEN apresenta também um aspecto inovador no seu funcionamento. Por meio de metadados específicos ele está vinculado ao sistema de gerenciamento das atividades do Plano Diretor anual do IPEN (SIGEPI). Com o objetivo de fornecer dados numéricos para a elaboração dos indicadores da Produção Cientifica Institucional, disponibiliza uma tabela estatística registrando em tempo real a inserção de novos itens. Foi criado um metadado que contém um número único para cada integrante da comunidade científica do IPEN. Esse metadado se transformou em um filtro que ao ser acionado apresenta todos os trabalhos de um determinado autor independente das variáveis na forma de citação do seu nome.

A elaboração do projeto do RI do IPEN foi iniciado em novembro de 2013, colocado em operação interna em julho de 2014 e disponibilizado na Internet em junho de 2015. Utiliza o software livre Dspace, desenvolvido pelo Massachusetts Institute of Technology (MIT). Para descrição dos metadados adota o padrão Dublin Core. É compatível com o Protocolo de Arquivos Abertos (OAI) permitindo interoperabilidade com repositórios de âmbito nacional e internacional.

1. Portaria IPEN-CNEN/SP nº 387, que estabeleceu os princípios que nortearam a criação do RDI, clique aqui.


2. A experiência do Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP) na criação de um Repositório Digital Institucional – RDI, clique aqui.

O Repositório Digital do IPEN é um equipamento institucional de acesso aberto, criado com o objetivo de reunir, preservar, disponibilizar e conferir maior visibilidade à Produção Científica publicada pelo Instituto, desde sua criação em 1956.

Operando, inicialmente como uma base de dados referencial o Repositório foi disponibilizado na atual plataforma, em junho de 2015. No Repositório está disponível o acesso ao conteúdo digital de artigos de periódicos, eventos, nacionais e internacionais, livros, capítulos, dissertações, teses e relatórios técnicos.

A elaboração do projeto do RI do IPEN foi iniciado em novembro de 2013, colocado em operação interna em julho de 2014 e disponibilizado na Internet em junho de 2015. Utiliza o software livre Dspace, desenvolvido pelo Massachusetts Institute of Technology (MIT). Para descrição dos metadados adota o padrão Dublin Core. É compatível com o Protocolo de Arquivos Abertos (OAI) permitindo interoperabilidade com repositórios de âmbito nacional e internacional.

O gerenciamento do Repositório está a cargo da Biblioteca do IPEN. Constam neste RI, até o presente momento 20.950 itens que tanto podem ser artigos de periódicos ou de eventos nacionais e internacionais, dissertações e teses, livros, capítulo de livros e relatórios técnicos. Para participar do RI-IPEN é necessário que pelo menos um dos autores tenha vínculo acadêmico ou funcional com o Instituto. Nesta primeira etapa de funcionamento do RI, a coleta das publicações é realizada periodicamente pela equipe da Biblioteca do IPEN, extraindo os dados das bases internacionais tais como a Web of Science, Scopus, INIS, SciElo além de verificar o Currículo Lattes. O RI-IPEN apresenta também um aspecto inovador no seu funcionamento. Por meio de metadados específicos ele está vinculado ao sistema de gerenciamento das atividades do Plano Diretor anual do IPEN (SIGEPI). Com o objetivo de fornecer dados numéricos para a elaboração dos indicadores da Produção Cientifica Institucional, disponibiliza uma tabela estatística registrando em tempo real a inserção de novos itens. Foi criado um metadado que contém um número único para cada integrante da comunidade científica do IPEN. Esse metadado se transformou em um filtro que ao ser acionado apresenta todos os trabalhos de um determinado autor independente das variáveis na forma de citação do seu nome.