| Country | Switzerland (Swiss Confederation) |
| Facility Name | AGN 211 P |
| Facility Number | CH-0004 |
| Status | OPERATIONAL |
| Last Updated | 2010/01/27 |
| General Data |
| Owner | UNIVERSITAET BASEL |
| Operator | INSTITUT FUER PHYSIK, UNIVERSITAET BASEL |
| Licensing | HAUPTABTEILUNG FUER SICHERHEIT DER KERNANLAGEN |
| Construction Date | 1959/04/30 |
| Criticality Date | 1959/08/01 |
| Safeguards | IAEA |
| Initial Cost | 350 K SFR |
| Annual Cost | 30 K SFR |
| Total Staff | 4 |
| No of Operators | 2 |
| Technical Data |
| Reactor Type | HOMOG (S) |
| Thermal Power, Steady (kW) | 2.00 |
| Max Flux SS, Thermal (n/cm2-s) | 3.6E10 |
| Max Flux SS, Fast (n/cm2-s) | 1.0E7 |
| 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 | CARBON |
| Reflector Number of Sides | 4 |
| Control Rods Material | CD,B,SS |
| Control Rods number | 4 |
| Experimental Facilities |
| Horizontal Channels | 1 |
| Horizontal Max Flux (n/cm2-s) | |
| Horizontal Use | NEUTRON DIFFRACTION |
| Vertical Channels | 1 |
| Vertical Max Flux (n/cm2-s) | |
| Vertical Use | IRRADIATION |
| Core Irradiation Facilities | 1 |
| Core Max Flux (n/cm2-s) | 3.6E10 |
| Reflector Irradiation Facilities | |
| Loops Number | |
| Loops Max Flux | |
| Loops use |
| Fuel data |
| Origin of Fissile Material | USA |
| Enrichment Supplier | USA |
| Equilibrium Core Size | 12 |
| Plates per Element | 18 |
| Dimensions of Plates | 66 X 457 X 1.4 |
| Rods per Element | |
| Dimensions of Rods, mm | |
| Tubes per Element | |
| Dimensions of Tubes, mm | |
| Cladding Material | AL ALLOY |
| Cladding Thickness, mm | 0.45 |
| Fuel Material | |
| Fuel Thickness, mm | 0.50 |
| Uranium Density, g/cm3 | |
| Burnup on Discharge, max % | |
| Burnup Average, % | 0.01 |
| Last Shipment Year | |
| Last Receipt Year | |
| Fuel Fabricator | AEROJET GENERAL NUCLEONICS, USA |
| Utilization |
| Hours per Day | 1 |
| Days per Week | 2 |
| Weeks per Year | 13 |
| MW Days per Year | 0 |
| Materials/fuel test experiments | NO |
| Isotope Production | 24Na, 60Co, 28Al |
| N/A | |
| Neutron Scattering | NO |
| Neutron Radiography | NO |
| Neutron capture therapy | NO |
| Activation Analysis | INAA |
| 15 | |
| Transmutation | NO |
| Geochronology | NO |
| Teaching | Number of students: 30 |
| Training | NO |
| Other Uses | NO |
| Operating Experience |
| Reactor | Thermal Power | Date of | Operational for | |||
| Category | Type | kW | Criticality | Construction | Years | Months |
| TRAINING | HOMOG (S) | 2.00 | 1959/08/01 | 1959/04/30 | 51 | 6 |