IPEN-CNEN/SP. F. A. Genezini 1, A. J. Fernando 1, A. Marra Neto 1, P. E. Aoki 2, W. A. P. Calvo 2
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1 F. A. Genezini 1, A. J. Fernando 1, A. Marra Neto 1, P. E. Aoki 2, W. A. P. Calvo 2 National Nuclear Energy Commission - Nuclear and Energy Research Institute Nuclear 1 Nuclear and Energy Research Research Reactor Centre Institute 2 Radiation Technology Centre National Nuclear IPEN-CNEN/SP Energy Commission IPEN-CNEN/SP
2 IEA R1 Research Reactor (5MW) Research Reactors in Brazil History, activities and ageing program Contents IEA R1 Research Reactor for Industrial Applications Neutron imaging, neutron diffraction and NAA in industry Silicon dopping Material tests for Brazilian Navy Radiotracers in health Radiotracers and radioactive sealed sources in industry Radiotracers of noble gases ( 40 Ar and 79 Kr) Final Remarks Multipurpose Research Reactor (30MW)
3 National Nuclear Energy Commission - BRAZIL Federal Government Autarchy under the Ministry of Science, Technology, Innovations and Communications Acts in P&D in the Nuclear Technology field, as well as rendering technological services and education Regulatory Authority MCTIC Ministry of Science, Technology, Innovations and Communications CNEN National Nuclear Energy Commission - Brazil ~1600 workers CDTN (MG) Nuclear Technology and Development Center 316 workers IEN (RJ) Nuclear Engineering Institute 225 workers IPEN - (SP) Nuclear and Energy Research Institute 773 workers IRD (RJ) Radiological Protection and Dosimetry Institute 225 workers CRCN (PE) Regional Center of Nuclear Sciences 63 workers There are other (6) smaller units: Angra dos Reis District, Rio de Janeiro, RJ; Caetite District, Caetité, BA; Fortaleza District, Fortaleza, CE; Goiania District, Goiânia, GO; Planalto Central District, Brasília, DF; Laboratory Division of Poços Caldas, Poços de Caldas, MG.
4 Name Applications Power Localization Type IPEN/MB-01 Critical facility PWR core analysis 100 W IPEN-CNEN/SP Pin open core ARGONAUTA Research and training 500 W IEN-CNEN/RJ Argonaut IPR-R1 Research and training 100 kw CDTN- CNEN/MG IEA-R1 Nuclear Research Reactors in Brazil Radioisotope production, research and training Triga MARK-I 5 MW IPEN-CNEN/SP Pool type MTR core 100 W 500 W 100 kw 5MW
5 Nuclear and Energy Research Institute IPEN/MB-01 Research Reactor (100W) IEA R1 Research Reactor (5MW) Located in the campus of Sao Paulo University (USP) Total area of about 500,000 m 2 102,000 m 2 of building area 11 Research Centers 773 permanent staff 1,333 undergraduate and graduate students 100 Post doctorates 361 Collaborators
6 IPEN s Main Facilities Nuclear Radioactive IEA-R1 Research Reactor (1957 5MW) IPEN/MB-01 Reactor ( W) Nuclear Fuel Centre (R&D, production) 2 Cyclotron Accelerators - IBA (Cyclones 30MeV and 18/9MEV) 2 Electron Beam Accelerator - RDI (1.5MeV) Radiopharmacy Centre 3 Gamma Irradiators ( 60 Co) Terawatt Laser Unity of treatment and storage of radioactive waste
7 IEA-R1 Research Reactor (5MW) On September, 1955 under the Atoms for Peace program, the USA and Brazilian governments agreed to construct a swimming-pool type research reactor in São Paulo, Brazil and the task was concluded on 1957
8 IEA-R1 Research Reactor (5MW) First criticality was achieved on 16 th September, 1957 First reactor operating in the southern hemisphere
9 IEA-R1 Research Reactor (5MW) Constructor: Babcok-Wilcox First criticality: September 16th, 1957 Type: open pool type reactor Moderator and coolant: light water Reflectors: graphite and beryllium Nominal power: 5 MW Operating power: 4.5MW Thermal flux: 5 x n cm -2 s -1 Fast flux: 1.3 x n cm -2 s -1 8 radial and 2 tangential beam holes Operating cycle: 9h per day, 4 days per week Fuel elements: 20% enriched uranium 24 rods of U 3 Si 2 -Al, 3 g.cm -3 produced at IPEN
10 IEA-R1 Research Reactor - Ageing Program The IAE-R1 Research Reactor has a continuous program of modernization Past main improvements Recent main improvements Ongoing main improvements
11 IEA-R1 Research Reactor - Main Activities IEA-R1 reactor acts in three types of activities 1) R&D: Basic and applied research in nuclear sciences in association with universities and other research institutes 2) Teaching: At undergraduate and graduate levels together Sao Paulo University 3) Products and Services: Resulting from the reactor uses for industrial applications, hospitals, clinics, environmental agencies
12 Valve for water flow control Valve for water flow control Neutron Imaging for Industrial applications Valve 3D image Hydrogen Fuel cell - Proton Exchange Membrane - PEM / MEA Water into the MEA Water distribution map
13 High Resolution Neutron Diffraction for Industrial Applications The texture of materials in metals Position Sensitive Detector (PSD) (inside the PSD shield) Neutron monochromator (inside the main shield) Rotating-Oscillating Collimator (ROC) Sapphire filter (inserted into the in-pile collimator) Microstructure and porous media of Portland cement Main neutron shield PSD neutron shield Movable platform Beam shutter (inside the main shield) Extra shield Measurement of residual stress in components 2 - drive mechanism *Parente, C. B. R., Mazzocchi, V. L., Mestnik-Filho, J., Mascarenhas, Y. P., Berliner, R. Nucl. Instr. and Meth. in Phys. Res. A 622 (2010)
14 Neutron Activation Analysis (NAA) for Industrial Applications Corrosion evaluation in alloys used as biomaterials Elemental composition of alloys used as biomaterials Abrasiveness of tooth paste Chemical compositions of fertilizers CFC determination in polyurethane used as insulator in refrigerators
15 Silicon Production for Electronic Industries NTD Neutron Transmutation Doping 30 Si(n, ) 31 Si 31 P+β - Neutron Flux profile Silicon Irradiation Rig Crystal diameter: Crystal Length: Target Resistivity: Annual Capacity: 5 inch 50 cm 30 Ohm.cm 1200kg
16 Material Tests for Brazilian Navy Material irradiations (fuel mini plates, pressurized instrumented element) Material testing under high neutron flux
17 Iodine -131 Production IEA-R1 Research Reactor can supply 60% of Brazilian demand Irradiation of 50g of enriched telurium oxide ( 130 Te O 2 ) seled into an aluminum capsule for 254h under a neutron flux of 1 x10 14 cm -2.s -1 (final activity of 12Ci in 131 I) After irradiatiation the iodine is separeted from 130 Te in the Radiopharmacy Centre 130 Te (n, ) 131m Te 30h 131 Te 25min 131 I
18 Samarium-153 Production IEA-R1 Research Reactor supply 100% of national demand in Brazil Irradiation of 37mg of enriched samarium oxide ( 152 Sm O 2 ) seled into a quartz bulb and aluminum capsule for 24h under a neutron flux of 1.5x10 13 cm -2.s -1 Final activity of 3 Ci in 153 Sm
19 Sealed Sources for Industrial Applications 1) Production of sealed sources ( 60 Co, 192 Ir, 182 Ta ) Tantalum Irradiation of 1.25g of metalic 181 Ta coated with Al 6082 alloy for 5h under a neutron flux of 1x10 14 cm -2.s -1 (final activity of 290mCi in 182 Ta) 2) Distribution 350/year: 192 Ir (25 100Ci, 74 days, 353keV) 20/year: 75 Se (40 80Ci, 120 days, 217keV)
20 Radiotracers for Industrial Applications 1) Iridium Environmental studies, in the form of a premixed sand (glass powder plus activated iridium) to study drag sediment in river Irradiation of 380g of ground glass with 0,3% of 191 Ir seled into a quartz bulb for 25h under a neutron flux of 5.5x10 13 cm -2.s -1 (final activity of 19mCi in 192 Ir) 2) Mercury Determination of the mercury mass immobilized in electrolytic cells from soda and chlorine producing industries Irradiation of 120g of 202 Hg seled into a quartz bulb for 50h under a neutron flux of 9x10 13 cm -2.s -1 (final activity of 40Ci in 203 Hg)
21 Radiotracers for Industrial Applications 3) Lanthanum Study the solid phase (catalysts) of Fluidized Cracking Catalytic (FCC) plants in petroleum refineries Irradiation of 1.5g of catalytic with 1.45% of 139 La into a sealed quartz bulb for 5h under a neutron flux of 4.3x10 13 cm -2.s -1 (final activity of 325mCi in 140 La) 4) Iodine-131 and Bromine-82 - Flow rate measurement and residence time distribution (RTD) studies in rivers, lakes and wastewater treatment plants Irradiation of 20g of potassium bromide with 1,45% of 81 Br into a sealed aluminum capsule for 8h under a neutron flux of 2x10 13 cm -2.s -1 (final activity of 1Ci in 82 Br) 5) Gold Impact study of great civil works (construction of artificial harbor, airport and hydroelectric reservoir) by labeling sand to be removed from the bottom with emulsion of gold
22 Radiotracers for Industrial Applications 6) Argon-41 - Study the gas phase in Fluidized Cracking Catalytic (FCC) plants A special irradiation device is filled with 40 Ar. It is inserted into the reactor core and irradiated for 1 hour under a neutron flux of 5x10 13 cm -2.s -1
23 Argon-41 Production Irradiation container is pluged in a special system, which delivery the radiotracer directly into the shield bottles (final activity of 20Ci in 41 Ar)
24 Krypton-79 Production 7) Krypton-79 - Study the gas phase in Fluidized Cracking Catalytic (FCC) plants Quartz bulb with g of 99.9% 78 Kr sealed into an aluminum capsule Irradiated for 32h under neutron flux of 9.9 x10 13 cm -2.s -1 (final activity of 600mCi in 79 Kr)
25 Krypton-79 Production After irradiation the aluminum capsule is taken from the reactor core and packaged into a proper shielding.
26 Krypton-79 Production The aluminum capsule is opened into a hot cell with appropriate filters and then it is sent to the industrial plant inside a hermetic shielding
27 Final Remarks In 2017 we celebrate the 60 th anniversary of the first criticality of the IEA-R1 Research Reactor (International Workshop ) Although its long operation, the modernization program allows us to continue its safe and productive use of the IEA-R1 Research Reactor The IEA-R1 Research Reactor is looking for new opportunities to enhance its industrial applications
28 Multipurpose Research Reactor (30MW) HOTCELLS FOR MO-99 ROCESSING RADIOISOTOPE PRODUCTION RADIOISOTOPES FOR MEDICINE OPERATION HUMAN RESOURCES FOR UTILIZATION, OPERATION, AND MAINTENANCE UF 6 20% ENRICHED RADIOISOTOPES FOR INDUSTRY RADIOISOTOPES FOR RESEARCH FUEL AND MATERIAL TESTING FUEL IRRADIATION TEST EXPERIMENTAL DEVICES FOR FUEL AND MATERIAL IRRADIATION TESTING HOTCELLS FOR POST-IRRADIATION ANALYSIS MULTIPURPOSE RESEARCH REACTOR HOTCELLS FOR RADIOISOTOPES MANIPULATION COLD AND HOT SUPPORTING LABORATORIES FUEL ASSEMBLIES MANUFACTURE FINANCIAL SUPPORT FOR UTILIZATION, OPERATION, AND MAINTENANCE LICENSING SITE DEFINITION LAWS AND STANDARDS MATERIAL IRRADIATION TEST NEUTRON APPLICATIONS EXPERIMENTAL HALL GUIDE HALL (Beam Tubes,CNS,HNS) IRRADIATED FUEL AND HIGH LEVEL WASTE STORAGE UTILIZATION, OPERATION, AND MAINTENANCE WORKSHOPS 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
29 THANK YOU FOR YOUR ATTENTION! IAEA ARCAL CXLVI/RLA1013 ( ) Creating Expertise in the Use of Radiation Technology for Improving Industrial Performance, Developing New Materials and Products, and Reducing the Environmental Impact of the Industry
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