| Country | Brazil, Federative Republic of |
| Facility Name | IPEN/MB-01 |
| Facility Number | BR-0004 |
| Status | OPERATIONAL |
| Last Updated | 2008/10/09 |
| General Data |
| Owner | IPEN-CNEN, SAO PAULO |
| Operator | IPEN, CIDADE UNIVERSITARIA |
| Licensing | COMISSAO NACIONAL DE ENERGIA NUCLEAR (CNEN) |
| Construction Date | 1984/11/01 |
| Criticality Date | 1988/11/09 |
| Safeguards | IAEA |
| Initial Cost | |
| Total Staff | 6 |
| No of Operators | 3 |
| Technical Data |
| Reactor Type | CRIT ASSEMBLY |
| Thermal Power, Steady (kW) | 0.10 |
| Max Flux SS, Thermal (n/cm2-s) | 1.0E9 |
| Max Flux SS, Fast (n/cm2-s) | 6.0E9 |
| Thermal Power, Pulsed (MW) | 0.00 |
| Max Flux Pulsed, Thermal (n/cm2-s) | |
| Max Flux Pulsed, Fast (n/cm2-s) | |
| Moderator | LIGHT WATER |
| Coolant | LIGHT WATER |
| Natural Convection Cooling | YES |
| Forced Cooling | |
| Coolant Velocity in Core | |
| Reflector | H2O |
| Reflector Number of Sides | |
| Control Rods Material | AG,IN,CD,BC |
| Control Rods number | 4; 2 CONTROL, 2 SAFETY |
| Experimental Facilities |
| Horizontal Channels | |
| Horizontal Max Flux (n/cm2-s) | |
| Horizontal Use | |
| Vertical Channels | |
| Vertical Max Flux (n/cm2-s) | |
| Vertical Use | |
| Core Irradiation Facilities | |
| Core Max Flux (n/cm2-s) | |
| Reflector Irradiation Facilities | |
| Loops Number | |
| Loops Max Flux | |
| Loops use |
| Fuel data |
| Origin of Fissile Material | BRAZIL |
| Enrichment Supplier | BRAZIL |
| Equilibrium Core Size | 680 |
| Plates per Element | |
| Dimensions of Plates | |
| Rods per Element | 1 |
| Dimensions of Rods, mm | 1194 |
| Tubes per Element | |
| Dimensions of Tubes, mm | |
| Cladding Material | SS |
| Cladding Thickness, mm | 0.6 |
| Fuel Material | UO2 |
| Fuel Thickness, mm | 10.6 |
| Uranium Density, g/cm3 | 10.33 |
| Burnup on Discharge, max % | |
| Burnup Average, % | |
| Last Shipment Year | |
| Last Receipt Year | |
| Fuel Fabricator | IPEN, BRAZIL |
| Utilization |
| Hours per Day | 3 |
| Days per Week | 3 |
| Weeks per Year | 44 |
| MW Days per Year | 0 |
| Materials/fuel test experiments | Number of runs: 149 |
| Isotope Production | NO |
| Neutron Scattering | NO |
| Neutron Radiography | NO |
| Neutron capture therapy | NO |
| Activation Analysis | NO |
| Transmutation | NO |
| Geochronology | NO |
| Teaching | Number of students: 2 |
| Training | Number of operators/experimenters trained: 8 |
| Other Uses | As a neutron source for reaction rates, kinetics parameters and shield experiments. |
| Operating Experience |
| Reactor | Thermal Power | Date of | Operational for | |||
| Category | Type | kW | Criticality | Construction | Years | Months |
| CRITICAL ASSEMBLY | CRIT ASSEMBLY | 0.10 | 1988/11/09 | 1984/11/01 | 21 | 6 |