| Country | Canada |
| Facility Name | MNR MCMASTER UNIV |
| Facility Number | CA-0004 |
| Status | OPERATIONAL |
| Last Updated | 2008/10/30 |
| General Data |
| Owner | MCMASTER UNIVERSITY |
| Operator | NUCLEAR REACTOR LABORATORY |
| Licensing | Canadian Nuclear Safety Commission |
| Construction Date | 1957/09/01 |
| Criticality Date | 1959/04/04 |
| Safeguards | IAEA |
| Initial Cost | 1.9 M CA$ |
| Total Staff | 11 |
| No of Operators | 5 |
| Technical Data |
| Reactor Type | POOL, MTR |
| Thermal Power, Steady (kW) | 3,000.00 |
| Max Flux SS, Thermal (n/cm2-s) | 1.0E14 |
| Max Flux SS, Fast (n/cm2-s) | 4.0E13 |
| 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 | only<110kW |
| Forced Cooling | gravity driven downflow |
| Coolant Velocity in Core | <2220 usgpm total core flow |
| Reflector | GRAPHITE |
| Reflector Number of Sides | 1 |
| Control Rods Material | AG,IN,CD,SS |
| Control Rods number | 5 safety (AG/IN/CD), 1 regulating (SS) |
| Experimental Facilities |
| Horizontal Channels | 6 |
| Horizontal Max Flux (n/cm2-s) | 5.0E12 |
| Horizontal Use | Neutron radiography, NEUTRON SCATTERING, PROMPT GAMMA ANALYSIS, SANS |
| Vertical Channels | 1 |
| Vertical Max Flux (n/cm2-s) | 1e12 |
| Vertical Use | neutron activation analysis |
| Core Irradiation Facilities | 4 |
| Core Max Flux (n/cm2-s) | 4.0E13 |
| Reflector Irradiation Facilities | 7(C)+1(Be) |
| Loops Number | |
| Loops Max Flux | |
| Loops use |
| Fuel data |
| Origin of Fissile Material | USA |
| Enrichment Supplier | USA |
| Equilibrium Core Size | 37 (31 standard, 6 control) |
| Plates per Element | 18 (16+9) |
| Dimensions of Plates | 1.27X67.8X600 |
| Rods per Element | |
| Dimensions of Rods, mm | |
| Tubes per Element | |
| Dimensions of Tubes, mm | |
| Cladding Material | AL ALLOY |
| Cladding Thickness, mm | 0.38 |
| Fuel Material | U3SI2ALX |
| Fuel Thickness, mm | 0.51 |
| Uranium Density, g/cm3 | 3.735 standard + 3.320 control |
| Burnup on Discharge, max % | 50 stand. + 35 contr |
| Burnup Average, % | 25 st. + 17.5 contr. |
| Last Shipment Year | 2008 |
| Last Receipt Year | 2008 |
| Fuel Fabricator | CERCA, FRANCE |
| Utilization |
| Hours per Day | 16 |
| Days per Week | 5 |
| Weeks per Year | 50 |
| MW Days per Year | 285 |
| Materials/fuel test experiments | NO |
| Isotope Production | N/A |
| N/A | |
| Neutron Scattering | N/A |
| N/A | |
| Neutron Radiography | On-line beam hours: N/A |
| Neutron capture therapy | NO |
| Activation Analysis | N/A |
| N/A | |
| Transmutation | Mass of Silicon (kg) : N/A Mass of gemstones (kg): N/A |
| Geochronology | N/A |
| N/A | |
| Teaching | NO |
| Training | Number of operators/experimenters trained: N/A |
| Other Uses | associated hot cells, high level labs |
| Operating Experience |
| Reactor | Thermal Power | Date of | Operational for | |||
| Category | Type | kW | Criticality | Construction | Years | Months |
| RESEARCH | POOL, MTR | 3000.00 | 1959/04/04 | 1957/09/01 | 50 | 1 |