SOUZA, A.P.S.; OLIVEIRA, L.P. de; GENEZINI, F.A.; SANTOS, A. dos. Simulating Araponga: the high resolution diffractometer of Brazilian Multipurpose Reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, November 29 - December 2, 2021, Online. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2021.
LANDINI, LILIANE; ARAUJO, SUMAIR G.; FORBICINI, CHRISTINA A.L.G.O.. Evaluation of microwave technology in the additional purification of Mo-99, produced from LEU targets. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 2352-2357.Abstract: In the present work, the feasibility of the microwave technology was studied as an additional purification step (sublimation) in the production of Mo-99, via the alkaline dissolution of LEU (low enrichment uranium) targets of UAlx/Al, in the RMB (Brazilian Multipurpose Reactor) project, which is usually accomplished by induction furnace. The intention was to decrease the time spent in this purification step, for later comparison between the methods. Thus, non-radioactive samples of sodium molybdate (solution) and appropriate catalysts/materials (which could withstand up to 1300°C) were prepared and employed. All experiments were performed in a microwave oven scale (1000W/2.45GHz), under atmospheric pressure. Considering that the experiments with induction furnace lasted from 1.5h to 2h for the sublimation of oxide and molybdenum separation, the preliminary results, obtained in this study, demonstrated the time savings and the possibility of reaching temperatures up to 1200°C in less than 30 minutes. Therefore, the use of this technique is considered promising for this application, although other studies and specific devices are required.
BEU, CASSIA M.L.; ESPINDOLA, FELIPE D.C.; LANDULFO, EDUARDO. Low-Level Jet observational study for the Brazilian Nuclear Reactor region. In: COMERON, ADOLFO (Ed.); KASSIANOV, EVGUENI I. (Ed.); SCHAFER, KLAUS (Ed.); PICARD, RICHARD H. (Ed.); WEBER, KONRADIN (Ed.) REMOTE SENSING OF CLOUDS AND THE ATMOSPHERE, 23th, September 10-13, 2018, Berlin, Germany. Proceedings... Bellingham, WA, USA: Society of Photo-optical Instrumentation Engineers, 2018. p. 1078616-1 - 1078616-18. (SPIE Proceedings Series, 10786).
DOI:
10.1117/12.2325476
Abstract: A doppler wind lidar was employed to investigate the features of the Low-Level Jet (LLJ) at Ipero, Sao Paulo State, Brazil.
The Ipero Municipality already host a nuclear facility for uranium enrichment and a new plant, a nuclear reactor, is planned
to be built there. The nuclear activities require a good understanding of atmospheric dispersion, as for normal operation
conditions as for accidental emissions. The LLJ is a natural phenomenon that may occur within the Planetary Boundary
Layer and plays an important role for the atmospheric dispersion. Knowing the LLJ characteristics is essential to evaluate
the performances of the weather forecast models that are used as input for the atmospheric dispersion models. The field
campaign results showed that the LLJs occur with high frequency at Ipero and that the Stable Boundary Layer (SBL) is
shallow, which in turn is unfavored for pollutant dilution because all surface emissions remain confined within the SBL.
The 2 weather forecast models evaluated didn´t reproduce the LLJ, despite their high horizontal resolution. The numerical
models also underestimated the wind speed. Both the LLJ and the wind speed are key parameters for dispersion
simulations. As the weather forecast models diverge of the observational data, they must be better parameterized for
provide reliable simulations before being adopted as input for any atmospheric dispersion models. The field campaign
(planned to extend for 1 year) data are essential for the parameterization of the numerical models.
CASTRO, ALFREDO J.A. de; ANDRADE, DELVONEI A. de. Experimental investigation of critical velocity in fuel element for the RMB reactor. In: BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th, November 25-28, 2018, Águas de Lindóia, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Engenharia e Ciências Mecânicas, 2018. Abstract: The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of
aluminum-coated fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These
plates have a thickness of the order of millimeters and are much longer in relation to their thickness. They are
arranged in parallel inside the fuel element assembly to form channel gaps between them of only a few millimeters
wide through which the coolant flows. This configuration, combined with the need for a flow at high flow rates to
ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel plate due to the
vibration induced by the flow in the channels. In the case of critical velocity, excessive permanent deflections of the
plates can cause blockage of the flow channel in the reactor core and, lead to overheating in the plates. For this work
an experimental loop capable of high volume flows and a test section that simulates a plate-like fuel element with three
cooling channels was developed. The dimensions of the test section were based on the dimensions of the Fuel Element
of the Brazilian Multipurpose Reactor (RMB), whose project is being coordinated by the National Commission of
Nuclear Energy (CNEN). The experiments performed had the objective of reaching Miller's critical velocity condition.
The critical velocity was reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel
plates.
DAMASCENO, MARCOS O.; MARQUES, FERNANDA A. da S.; DIAS, RICARDO R.; SANTOS, JACINETE L. dos; FORBICINI, CHRISTINA A.L.G. de O.. Study of new routes for purification of fission (99)Mo. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 1773-1784.Abstract: 99mTc is the most widely applied medical radioisotope in the world, especially for cancer diagnosis procedures. It is provided by 99Mo radioactive decay, which is one of the fission products of irradiated uranium by nuclear reactors. At main production centers, 99Mo chemical processing line up different steps to separate it from other fission products, depending on features of targets or local requirements. In this work, two new routes (MR1 and MR2) for 99Mo purification are presented, called MR1 and MR2, can be set up in the Brazilian Multipurpose Reactor project (RMB). In the first studied route, 99Mo purification initiated by eluting the solution through a Dowex 1x8 resin chromatography column, followed by a second step using a Chelex resin column and finally, the process was finished using an alumina column. For a second route, the first step is also performed with a Dowex 1x8 column, followed by a second separation step using alumina column, and lastly, a sublimation process was carried out in a tubular oven under programmed conditions. The final yield for the MR1 route has reached 84.4% and the overall time process about 7 hours, by contrast, MR2 route came to 75.3% in 9 hours.
SANTOS, ADIMIR dos; YAMAGUCHI, MITSUO; FANARO, LEDA C.C.B.; SANTOS, DIOGO F. dos; SOUZA, GREGORIO S. de; JUNQUEIRA, FERNANDO de C.; SILVA, GRACIETE S. de A. e; BELCHIOR JUNIOR, ANTONIO; PRADO, ADELK de C.; JOAO, THIAGO G.; ROSSI, PEDRO C.R.. New plate-type core of the IPEN/MB-01 research reactor facility for validation of RMB project. In: INTERNATIONAL CONFERENCE ON RESEARCH REACTORS: ADDRESSING CHALLENGES AND OPPORTUNITIES TO ENSURE EFFECTIVENESS AND SUSTAINABILITY, November 25-29, 2019, Buenos Aires, Argentina. Proceedings... Vienna, Austria: International Atomic Energy Agency, 2020. Abstract: The IPEN/MB-01 research reactor had its first criticality in November 1988 and, ever since, has been of major importance in Brazilian reactor physics researches, achieving international level for experiments comparison and validation (benchmarks). In this facility it is possible to build many different core configurations (i.e., rectangular, square and cylindrical), once versatility and flexibility were both taken into account on its initial project. The core is a fissile material assembly, inserted in a water tank, where the chain reaction is self-maintained and controlled at low power levels, so that, in normal operation, the feedback effects of temperatures are negligible. The core is intended for neutrons simulation of light water moderated reactors allowing the experimental verification of the calculation methods, reactor cell and mesh structures, control rods effectiveness, isothermal reactivity coefficients and core dynamics due to reactivity insertions. The first standard IPEN/MB-01 core had UO2 rod-type fuel, 4.3 % enriched in U-235 and using B4C and Ag-In-Cd rods for safety and control of the reactor. The facility is located at IPEN/CNEN-SP (Nuclear and Energy Research Institute), in Sao Paulo - Brazil. Within the scope of the new research reactor project, the Brazilian Multipurpose Reactor (RMB), it was designed a new critical configuration for the IPEN/MB-01. After thirty years of work, the rod-type fuels were replaced by plate-type fuels, in order to validate the RMB calculation methodologies, as well as the nuclear data libraries used. The RMB is an open pool-type reactor with maximum power of 30 MW, being the core a 5x5 configuration, consisting of 23 fuel elements, made of U3Si2-Al, having a medium density of 3.7 gU/cm3 and 19.75% enriched in U-235, and two positions available in the core for materials irradiation devices. The production of radioisotopes, silicon doping, neutron activation analysis, nuclear fuels and structural materials testing and the development of scientific and technological research using neutron beams are the main targets of the RMB enterprise. The new IPEN/MB-01 core has a 4×5 configuration, having 19 fuel elements, consisting of U3Si2-Al, 2.8 gU/cm³ and 19.75% enriched in U-235, plus one aluminum block. The IPEN/MB-01 new plate-type fuel assembly uses Cadmium wires as burnable poison, as the one used in RMB core for controlling the core power density and excess of reactivity during its operation. The core is also reflected by 4 boxes of heavy water (D2O), inserted in a moderator tank of light water. The maximum nominal power is 100 W and, for a safe operation, the critical assembly has both safety and auxiliaries’ systems. This paper presents a description of the new core and the principal neutronic parameters. The new core of the IPEN/MB-01 will be certainly a world class benchmark core for the core physics calculation of research reactors.
SOARES, HUMBERTO V.; BELCHIOR JUNIOR, ANTONIO; FREITAS, ROBERTO L.. RELAP5 modeling of a siphon break effect on the Brazilian Multipurpose Reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5443-5456.Abstract: This work presents the thermo-hydraulic simulation of the Brazilian Multipurpose Reactor (RMB) using the RELAP5/Mod3 code. The RMB will provide Brazil with a fundamental infrastructure for the national development on activities of the nuclear sector in the areas of social, strategic, industrial applications and scientific and technological development. A RELAP5/Mod3 code model was developed for thermo-hydraulic simulation of the RMB to analyze the phenomenology of the Siphon Breakers device (four flap valves in the cold leg and one open tube for the atmosphere in the hot leg) during a Loss of Coolant Accident (LOCA) at different points in the primary circuit. The Siphon Breaker device is an important passive safety system for research reactors in order to guarantee the water level in the core under accidental conditions. Different simulations were carried out at different location in the Core Cooling System (CCS) of the RMB, for example: LOCA before the CCS pumps with and without pump trip and LOCA after the CCS pumps and the heat exchanger. In all RELAP5/Mod3 code simulations, the Siphon Breaker device's performance after a LOCA was effective to allow enough air to enter the outlet pipe of the CCS in order to break the siphon effect and preventing the pool level from reaching the riser (chimney) and the RMB core discovering. In all cases, the reactor pool level stabilized at about 5.5 m after the end of the LOCA simulation and the fuel elements were kept underwater and cooled.
HONÓRIO, DANIEL H.; JESUS, MARCELO Z.; PERROTTA, JOSE A.; MOLNARY, LESLIE de; AQUINO, AFONSO R.. Licensing aspects of the Brazilian Multipurpose Reactor (RMB). In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4078-4091.Abstract: The Brazilian Multipurpose Reactor (RMB) is a project funded by the Brazilian Government by means
of the Ministry of Science Technology Innovation and Communication. RMB will be the new Brazilian
research reactor, constructed to attend three main purposes: radioisotope production, R&D and material
testing. It will be sited 125 km away from S~ao Paulo, strategically, at a Nuclear Compound, where a state
owned pole of nuclear technology is located. To construct and operate the RMB facilities, as required
by the National Environmental Policy, it is necessary, in addition to the nuclear licensing process of the
National Nuclear Energy Commission (CNEN), to conduct all the environmental licensing stages with
the Brazilian Environmental Agency (IBAMA). Given this regulatory scenario, based on the standards,
guidelines and legal requirements of the IAEA, CNEN, IBAMA and other Brazilian o cial agencies,
since 2012, the activities required to comply with the protocol for obtaining initial environmental and
construction licenses is being implemented. This paper aims to show a timeline about this process, update
the community and register further steps. The RMB entrepreneurs carried out the Environmental
Impact Assessment issued the Local report for the radioprotection directory and held three public hearings.
Those, among other e orts, resulted on the Local Approval License, which was issued by CNEN
Deliberative Commission and on the Initial Environmental License issued by IBAMA. Both of these permits
were placed in 2015. Since then some activities for complying with the permit conditions is being
performed at the site and properly reported in order to obtain the installation license from the agency.
TORRES, WALMIR M.; UMBEHAUN, PEDRO E.; MATTAR NETO, MIGUEL; BELCHIOR JUNIOR, ANTONIO; FREITAS, ROBERTO L.. RMB experimental program on the hydrodynamical behavior of fuel assemblies. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4440-4449.Abstract: The Brazilian Multipurpose Reactor - RMB is a 30 MW pool type research reactor, that uses Materials Testing Reactor - MTR type fuel assemblies. It has a 5x5 square array core with 23 fuel assemblies and two in-core irradiation positions, operating with upward flow and average velocities nearly 10 m/s in the fuel plates channels. The IEA-R1 is a 5 MW pool type research reactor, which also has a 5x5 square array core with 19 standard fuel assemblies, four control fuel assemblies and a central beryllium irradiation device. It operates with downward flow nearly 1.8 m/s in the channels.
In order to verify and provide data and information about the dynamical behavior of fuel assemblies under nominal and critical conditions, the experimental circuit ORQUÍDEA is being designed. This information will be very important for the licensing process of the fuel assembly before its use in the reactor core. This circuit will permits upward and downward flow and dynamical behavior of the fuel assemblies and its parts will be tested and verified. Flow rate, temperature, pressure and differential pressure transducers are the instruments of the circuit. Endurance and critical flow velocity tests will be performed. Dummy fuel assemblies will be used in the tests. It will be instrumented with pressure, strain-gages and flow velocity instruments.
The COLIBRI experimental circuit is being designed to make tests that allow the studies of the fluid-structure phenomenology of fuel plates similar to those of the RMB fuel assemblies when subjected to high flow velocities, which can induce pressure differences between the channels formed by the fuel plates. Preliminary structural response studies of the plate’s behavior were performed using a Finite Element Analysis model generated by ANSYS Mechanical. The pressure loadings caused by the fluid flow were calculated using a Computational Fluid Dynamics model created with ANSYS CFX. The fluid-structure interactions will be verified for different channel configurations. In this circuit, vibrations and collapse of the dummy fuel plates will be tested. Experimental data will be compared with CFD (Computational Fluid Dynamics) calculations.
This work presents a preliminary design for the ORQUÍDEA and COLIBRI experimental circuits to be built at the Instituto de Pesquisas Energéticas e Nucleares - IPEN of the Comissão Nacional de Energia Nuclear - CNEN.
JOÃO, THIAGO G.; SANTOS, DIOGO F. dos; ROSSI, PEDRO C.R.; SOUZA, GREGORIO S. de; SANTOS, ADIMIR dos. Monte Carlo modeling of the new plate-type core for the Brazilian IPEN/MB-01 research reactor. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4131-4143.Abstract: After 30 years of operation, the IPEN/MB-01 research reactor is about to receive a new plate-type core. This replacement is due to the Brazilian Multipurpose Reactor (RMB) needs, the largest project in nuclear engineering taking place in Brazil. The RMB will be a 30MW open pool-type research reactor, keeping the core in a 5x5 configuration (23 fuel elements, made of U3Si2-Al fuel plates, with 3.7 gU/cm3, 19.75% enriched in U-235 and two extra positions available for materials irradiation). The radioisotopes production, material irradiation, nuclear fuels structural testing and the development of scientific and technological research using neutron beams are the main targets of the RMB enterprise. In this way, in order to verify, experimentally, the calculation methods and data libraries used for the Brazilian Multipurpose Reactor design, reactor cell and mesh structures, control rods effectiveness, isothermal reactivity coefficients and core dynamics due to reactivity insertions, the IPEN/MB-01 new plate-type core is being implemented at the Nuclear and Energy Research Institute (IPEN/CNEN-SP), SP-Brazil. It´s a tank-type research reactor. The core has a 4×5 configuration, with 19 fuel elements (U3Si2-Al, 2.8gU/cm³ and 19.75% enriched in U-235), plus one aluminum block (internal irradiation position). As burnable poison, cadmium wires were used, once they are also employed at the RMB project to control the power density and the excess of reactivity during its operation. The core is reflected by four boxes of heavy water (D2O) and its maximum nominal power is 100W. Thereby, a Monte Carlo modeling was developed using the Monte Carlo N-Particle code (MCNP), along with NJOY, for processing the materials nuclear cross sections. This modeling for the IPEN/MB-01 new plate-type core is presented and some neutronic calculations were also depicted in this paper.
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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,
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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.