Country | Mexico (United Mexican States) |
Facility Name | CHICAGO MODELO 9000 |
Facility Number | MX-0003 |
Status | OPERATIONAL |
Last Updated | 2001/03/01 |
General Data |
Owner | UNIV. AUTONOMA DE ZACATECAS |
Operator | CENTRO REGIONAL DE ESTUDIOSNUCLEARES |
Licensing | COMISION NACIONAL DE SEGURIDAD NUCLEAR Y SALVAGUARDIAS |
Construction Date | 1968/07/18 |
Criticality Date | 1969/05/14 |
Safeguards | IAEA |
Initial Cost | |
Annual Cost | 16 K US$ |
Total Staff | 16 |
No of Operators | 1 |
Technical Data |
Reactor Type | SUBCRIT |
Thermal Power, Steady (kW) | 0.00 |
Max Flux SS, Thermal (n/cm2-s) | 2.6E4 |
Max Flux SS, Fast (n/cm2-s) | 9.4E4 |
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 | |
Forced Cooling | |
Coolant Velocity in Core | |
Reflector | H2O |
Reflector Number of Sides | 2 |
Control Rods Material | |
Control Rods number |
Experimental Facilities |
Horizontal Channels | |
Horizontal Max Flux (n/cm2-s) | |
Horizontal Use | |
Vertical Channels | 2 |
Vertical Max Flux (n/cm2-s) | |
Vertical Use | STUDENT TRAINING, EXPERIMENTS |
Core Irradiation Facilities | 2 |
Core Max Flux (n/cm2-s) | 1.0E7 |
Reflector Irradiation Facilities | |
Loops Number | |
Loops Max Flux | |
Loops use |
Fuel data |
Origin of Fissile Material | USA |
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 | AL ALLOY |
Cladding Thickness, mm | 1.1 |
Fuel Material | |
Fuel Thickness, mm | |
Uranium Density, g/cm3 | |
Burnup on Discharge, max % | |
Burnup Average, % | |
Last Shipment Year | |
Last Receipt Year | |
Fuel Fabricator | NUCLEAR CHICAGO, USA |
Utilization |
Hours per Day | 0 |
Days per Week | 0 |
Weeks per Year | 0 |
MW Days per Year | 0 |
Materials/fuel test experiments | NO |
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 | NO |
Operating Experience |
Reactor | Thermal Power | Date of | Operational for | |||
Category | Type | kW | Criticality | Construction | Years | Months |
TRAINING | SUBCRIT | 0.00 | 1969/05/14 | 1968/07/18 | 40 | 9 |