| Country | Brazil, Federative Republic of |
| Facility Name | IPR-RI |
| Facility Number | BR-0002 |
| Status | OPERATIONAL |
| Last Updated | 2009/04/03 |
| General Data |
| Owner | CENTRO DE DESENVOLVIMENTO DA TECNOLOGIA NUCLEAR/CDTN-CNEN |
| Operator | CENTRO DE DESENVOLVIMENTO DA TECNOLOGIA NUCLEAR/CDTN-CNEN |
| Licensing | COMISSAO NACIONAL DE ENERGIA NUCLEAR, (CNEN) |
| Construction Date | 1958/01/01 |
| Criticality Date | 1960/11/06 |
| Safeguards | AIEA/ABACC |
| Initial Cost | 250 K US$ |
| Annual Cost | 100 K US$ |
| Total Staff | 4 |
| No of Operators | 4 |
| Technical Data |
| Reactor Type | TRIGA MARK I |
| Thermal Power, Steady (kW) | 100.00 |
| Max Flux SS, Thermal (n/cm2-s) | 4.3E12 |
| Max Flux SS, Fast (n/cm2-s) | 1.5E12 |
| Thermal Power, Pulsed (MW) | 0.00 |
| Max Flux Pulsed, Thermal (n/cm2-s) | |
| Max Flux Pulsed, Fast (n/cm2-s) | |
| Moderator | H2O,ZRH |
| Coolant | LIGHT WATER |
| Natural Convection Cooling | YES |
| Forced Cooling | at 300kW |
| Coolant Velocity in Core | 4 CM/S |
| Reflector | GRAPHITE |
| Reflector Number of Sides | annular |
| Control Rods Material | B4C |
| Control Rods number | 3 |
| Experimental Facilities |
| Horizontal Channels | |
| Horizontal Max Flux (n/cm2-s) | |
| Horizontal Use | |
| Vertical Channels | 1 |
| Vertical Max Flux (n/cm2-s) | 5.8E7 |
| Vertical Use | NEUTRON RADIOGRAPHY EXTRACTOR |
| Core Irradiation Facilities | 3 |
| Core Max Flux (n/cm2-s) | 4.3E12 |
| Reflector Irradiation Facilities | 40-80 pos. |
| Loops Number | |
| Loops Max Flux | |
| Loops use |
| Fuel data |
| Origin of Fissile Material | USA |
| Enrichment Supplier | USA |
| Equilibrium Core Size | |
| Plates per Element | |
| Dimensions of Plates | |
| Rods per Element | 1 |
| Dimensions of Rods, mm | 37.6 X 724 |
| Tubes per Element | |
| Dimensions of Tubes, mm | |
| Cladding Material | AL OR SS |
| Cladding Thickness, mm | 0.76 |
| Fuel Material | UZRH |
| Fuel Thickness, mm | 35.6 |
| Uranium Density, g/cm3 | 0.11 (U235) |
| Burnup on Discharge, max % | |
| Burnup Average, % | |
| Last Shipment Year | |
| Last Receipt Year | 1974 |
| Fuel Fabricator | GENERAL ATOMICS, USA |
| Utilization |
| Hours per Day | 8 |
| Days per Week | 2 |
| Weeks per Year | 40 |
| MW Days per Year | 2 |
| Materials/fuel test experiments | NO |
| Isotope Production | 60Co, 56Mn, 82Br, 198Au, 192Ir, 32P, 41Ar |
| N/A | |
| Neutron Scattering | NO |
| Neutron Radiography | On-line beam hours: N/A |
| Neutron capture therapy | NO |
| Activation Analysis | biomaterials, environmental samples, airborne particles, industrial products |
| N/A | |
| Transmutation | NO |
| Geochronology | NO |
| Teaching | Number of students: N/A |
| Training | Number of operators/experimenters trained: N/A |
| Other Uses | NO |
| Operating Experience |
| Reactor | Thermal Power | Date of | Operational for | |||
| Category | Type | kW | Criticality | Construction | Years | Months |
| RESEARCH | TRIGA MARK I | 100.00 | 1960/11/06 | 1958/01/01 | 49 | 6 |