| Country | Canada |
| Facility Name | ZED-2 |
| Facility Number | CA-0005 |
| Status | OPERATIONAL |
| Last Updated | 2001/03/23 |
| General Data |
| Owner | ATOMIC ENERGY OF CANADA LIMITED |
| Operator | CHALK RIVER LABORATORIES |
| Licensing | CANADIAN NUCLEAR SAFETY COMMISSION |
| Construction Date | 1958/12/01 |
| Criticality Date | 1960/09/01 |
| Safeguards | IAEA |
| Initial Cost | 3.6 M C$ |
| Annual Cost | 0.3 M C$ |
| Total Staff | 5 |
| No of Operators | 5 |
| Technical Data |
| Reactor Type | TANK |
| Thermal Power, Steady (kW) | 0.20 |
| Max Flux SS, Thermal (n/cm2-s) | 1.0E9 |
| Max Flux SS, Fast (n/cm2-s) | 5.0E8 |
| Thermal Power, Pulsed (MW) | 0.00 |
| Max Flux Pulsed, Thermal (n/cm2-s) | |
| Max Flux Pulsed, Fast (n/cm2-s) | |
| Moderator | HEAVY WATER |
| Coolant | |
| Natural Convection Cooling | |
| Forced Cooling | |
| Coolant Velocity in Core | |
| Reflector | GRAPHITE |
| Reflector Number of Sides | 5 |
| Control Rods Material | CD |
| Control Rods number | 12 |
| 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 | 7 |
| Loops Max Flux | 1.0E09 |
| Loops use | HIGH TEMPERATURE LATTICE PHYSICS EXPERIMENTS |
| Fuel data |
| Origin of Fissile Material | CANADA |
| Enrichment Supplier | |
| Equilibrium Core Size | |
| Plates per Element | |
| Dimensions of Plates | |
| Rods per Element | |
| Dimensions of Rods, mm | |
| Tubes per Element | |
| Dimensions of Tubes, mm | |
| Cladding Material | |
| Cladding Thickness, mm | |
| Fuel Material | UO2 - U METAL |
| Fuel Thickness, mm | |
| Uranium Density, g/cm3 | |
| Burnup on Discharge, max % | |
| Burnup Average, % | |
| Last Shipment Year | |
| Last Receipt Year | |
| Fuel Fabricator | AECL, CA |
| Utilization |
| Hours per Day | 1 |
| Days per Week | 5 |
| Weeks per Year | 52 |
| MW Days per Year | 0 |
| Materials/fuel test experiments | Number of runs: 200 |
| Isotope Production | NO |
| Neutron Scattering | NO |
| Neutron Radiography | NO |
| Neutron capture therapy | NO |
| Activation Analysis | NO |
| Transmutation | NO |
| Geochronology | NO |
| Teaching | NO |
| Training | NO |
| Other Uses | Calibration of self-powered flux detectors - 10% of the time. |
| Operating Experience |
| Reactor | Thermal Power | Date of | Operational for | |||
| Category | Type | kW | Criticality | Construction | Years | Months |
| RESEARCH | TANK | 0.20 | 1960/09/01 | 1958/12/01 | 49 | 5 |