Status of Research Reactor Utilization in Brazil Instituto de Pesquisas Energéticas e Nucleares IPEN/CNEN-SP; Brazil IAEA Technical Meeting on Research Reactor Application for Materials Under High Neutron Fluence IAEA Headquarters, Vienna, Austria 17-21 November 2008
Summary Introduction Research Reactor Utilization ARGONAUTA Research Reactor IPR-R1 Research Reactor IPEN/MB-01 Research Reactor IEA-R1 Research Reactor Future Perspectives for RR Utilization
Introduction Research Reactors in Brazil Name Utilization Power Location Type IEA-R1 Research Radioisotope Production 5 MW IPEN/CNEN-SP São Paulo MTR Pool Type Reactor IPEN/MB-01 Critical Facility PWR Core Analysis 100 W IPEN/CNEN-SP São Paulo Pin Type Open Core IPR-R1 Research Training 100 kw CDTN/CNEN-MG Belo Horizonte TRIGA MARK-I ARGONAUTA Research Training 500 W IEN/CNEN-RJ Rio de Janeiro Argonaut
Introduction IPR-R1 Research Reactor Belo Horizonte São Paulo Rio de Janeiro ARGONAUTA Research Reactor IPEN/MB-01 Research Reactor IEA-R1 Research Reactor
Research Reactor Utilization ARGONAUTA Research Reactor Argonaut type reactor (Argonne National Laboratory Nuclear Assembly for University Training) Installed in 1965 at the Nuclear Engineering Institute (IEN) of the Brazilian Nuclear Energy Commission located at the Rio de Janeiro University Campus. 500 W of maximum power U 3 O 8 -Al MTR dispersion fuel type with 20% uranium enrichment. Main utilization Teaching and training in reactor physics Neutron radiography Neutron activation analysis
Research Reactor Utilization TRIGA MarkI type reactor, produced by General Atomic Company, USA. Installed in 1960 at the previous Radioactive Research Institute (IPR), today the Nuclear Technology Developing Center (CDTN) of the Brazilian Nuclear Energy Commission, located at Belo Horizonte, Minas Gerais Federal University Campus. 100 kw of maximum power for continuous operation. U-Zr-H Triga pin type fuel with 20% uranium enrichment. Main utilization: Specific radioisotope production for industry, medical, agriculture and engineering applications. Neutron activation analysis. Teaching physics. and training in reactor The reactor is one of the training tools for licensing the Brazilian nuclear power reactor operators. IPR-R1 Research Reactor
Research Reactor Utilization IPEN/MB-01 Research Reactor Designed and constructed with Brazilian technology. Installed at the Energetic and Nuclear Research Institute (IPEN) of the Brazilian Nuclear Energy Commission site, in Sao Paulo, had its first criticality in 1988. 100 W of maximum power. UO 2 fuel pins with 4.3% uranium enrichment. Main utilization: Validation of reactor physics methodology and nuclear data associated for PWR core analysis. Teaching and training in reactor physics.
Research Reactor Utilization IPEN/MB-01 Research Reactor The international community recognizes some experiments performed at this reactor as benchmarking data. The experimental data obtained at the reactor are: integral and differential reactivity worth of control rods; power calibration by foils activation and noise analysis; temperature coefficients; and void reactivity spatial and energetic flux distribution by foils activation and fission chambers detectors; reaction rates and spectral index measurement inside fuel rods; buckling measurement with different baffle material and thickness; criticality tests with different burnable poison specific physics. tests related to reactor
Research Reactor Utilization Pool type research reactor, Babcock & Wilcox project. Installed at the previous Atomic Energy Institute (IEA), presently the Nuclear and Energy Research Institute (IPEN) of the Brazilian Nuclear Energy Commission site, in Sao Paulo, inside the Sao Paulo University Campus, The reactor achieved its first criticality on September 16, 1957. 5 MW of maximum power (originally 2 MW) The reactor originally used 93% enriched U-Al fuel elements, but now it uses 20% enriched uranium U 3 Si 2 -Al dispersion fuel produced at IPEN. IEA-R1 Research Reactor
Research Reactor Utilization Main Utilization IEA-R1 Research Reactor Radioisotope Production 131 I (activation) 99 Mo (activation) 153 Sm 192 Ir 198 Au 82 Br 41 Ar Neutron Activation Analysis Silicon Doping
Research Reactor Utilization IEA-R1 Research Reactor Neutron Beam Utilization Neutron diffractometry BNCT research Neutron radiography Photonuclear reactions Materials Irradiation MTR Fuel mini plates irradiation PWR Fuel mini rods irradiation using pressurized rig Structural material testing using special rig with temperature control NDT analysis inside the pool Dimensional inspection Visual inspection Gamma scanning Sipping test Teaching and training. BNCT Neutron Diffractometer # 1 Neutron Radiography Photonuclear Reaction Neutron Diffractometer # 2
Future Perspectives for RR Utilization Brazilian Nuclear Program Review Electricity produced by nuclear power plants Brazil will continue to use nuclear energy in its electrical power generating matrix. Nuclear Fuel Brazil has a significant uranium ore reserve and domains the fuel cycle technology, including U enrichment. Increase of industrial activities for supplying the nuclear power plants needs. Nuclear Techniques Utilization Increase of the nuclear techniques applications and radioisotope utilization in the benefit of the society. Increase of autonomous technology development PNB Working Group PNB Advisory Group
Future Perspectives for RR Utilization Electricity Produced by Nuclear Power Plants Two Nuclear Power Plants in Operation Angra I 650 MWe Angra II 1350 MWe One Nuclear Power Plant under construction ( 2014 ) Angra III 1350 MWe Four Nuclear Power Plants proposed until 2030 > 1000 MWe (generation 3+) Source Hydraulic Thermal Nuclear Installed Capacity 2005 (GW) 69.9 14.9 2 Planned Capacity 2030 (GW) 164 32.6 7.3 Modest participation in the Others 5.9 8.4 electric power matrix (< 4%) Total 92.7 216.5 Wind - 4.7
Future Perspectives for RR Utilization Nuclear Fuel Fabrication Industry (INB Plants) Activity Location Capacity Mining Caetité Bahia 400 tons/year of yellow cake Conversion Resende Rio de Janeiro Planned Enrichment Resende Rio de Janeiro First module under commissioning (Brazilian technology) Reconversion Resende Rio de Janeiro TCAU route 140 tons/year of UO 2 UO 2 Pellets Fabrication Resende Rio de Janeiro 120 tons/year (Angra I and Angra II) Fuel Assembling Resende Rio de Janeiro 250 tons of U/year (Angra I e Angra II)
Future Perspectives for RR Utilization Radioisotope for Radiopharmaceutical Radioisotope Total Activity per year (Ci) Users* per year Comments Evolução da Distribuição de Gerador de Tecnécio 25.000.000 Atividade (mci) 20.000.000 Mo-99 20,000 300 imported 99m Tc mci 15.000.000 I-131 2,000 260 50% imported 50% IEA-R1 10.000.000 5.000.000 Cr-51 1 7 imported - 2000 2001 2002 2003 2004 2005 2006 2007 2008 Ano Sm-153 21 50 100% IEA-R1 Evolução da Distribuição de I-131 (em solução e em cápsula) 2.500.000 2.000.000 Lu-177 15 8 imported 131 I 1.500.000 mci 1.000.000 I-125 48 18 imported 500.000-2000 2001 2002 2003 2004 2005 2006 2007 2008 Ir-192 3,840 60 imported Ano Atividade ( mci)
Future Perspectives for RR Utilization New Multipurpose Research Reactor Due to the Brazilian nuclear program review proposals of increasing activities in the nuclear sector for the next decades; Due to the fact that the industrial application of power reactor and nuclear fuel technology requires, for an autonomous development, the need of fuel and material testing under irradiation; Due to the fact that the radioisotope production for radiopharmaceuticals application depends strongly on international suppliers; Due to the fact that neutron beam applications, for fundamental and technological research, are limited with the actual infrastructure. The Brazilian Nuclear Energy Commission (CNEN) is analyzing the costs and benefits of constructing a new research reactor in Brazil. This new research reactor should have neutron fluxes compatible to the multipurpose use and application needs.
Multipurpose Research Reactor Scope RADIOISOTOPE PRODUCTION RADIOISOTOPES FOR MEDICINE OPERATION HUMAN RESOURCES FOR UTILIZATION, OPERATION, AND MAINTENANCE UF 6 20% ENRICHED RADIOISOTOPES FOR INDUSTRY RADIOISOTOPES FOR RESEARCH HOTCELLS FOR MO-99 ROCESSING H O T C EL L S F O R R A D I O I SO T O PES M A N I PU L A T I O N FUEL ASSEMBLIES MANUFACTURE FINANCIAL SUPPORT FOR UTILIZATION, OPERATION, AND MAINTENANCE FUEL AND MATERIAL TESTING FUEL IRRADIATION TEST EXPERI M ENTAL DEVI CES FO R FUEL AND M ATERI AL I RRADI ATI O N TESTI NG H O T C E L L S F O R P O S T - IR R A D IA T IO N A N A L Y S IS MULTIPURPOSE RESEARCH REACTOR C O L D A N D H O T S U P P O R T I N G L A B O R A T O R I E S LICENSING SITE DEFINITION LAWS AND STANDARDS MATERIAL IRRADIATION TEST NEUTRON APPLICATIONS E X P E R I M E N T A L H A L L G U I D E H A L L ( B e a m T u b e s, C N S, H N S ) I R R A D I A TE D FU E L A N D H I G H LE V E L WA S TE S TO R A G E U T IL IZ A T ION, OP E R A T ION, A N D MA IN T E N A N C E WOR K S H OP S ENVIRONMENTAL LICENSING NUCLEAR LICENSING DESIGN / CONSTRUCTION / COMMISSIONING NAA NTD HUMAN RESOURCES FOR DESIGNING PLANT DESIGN TEACHING AND TRAINING NUCLEAR PHYSICS NEUTRON RADIOGRAPHY FABRICATION (CONTRACTS) CONSTRUCTION (CONTRACTS) COMMISSIONING MATERIALS SCIENCE BIOLOGICAL SCIENCES TECHNOLOGIC APPLICATIONS FINANCIAL SUPPORT NATIONAL PARTNERSHIPS INTERNATIONAL PARTNERSHIPS
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