Country | Chile, Republic of |
Facility Name | RECH-1 |
Facility Number | CL-0001 |
Status | OPERATIONAL |
Last Updated | 2009/05/10 |
General Data |
Owner | COMISION CHILENA DE ENERGIA NUCLEAR |
Operator | LA REINA NUCLEAR CENTRE-CCHEN |
Licensing | COMISION CHILENA DE ENERGIA NUCLEAR (CCHEN) |
Construction Date | 1970/10/10 |
Criticality Date | 1974/10/13 |
Safeguards | IAEA |
Initial Cost | 8 M POUNDS |
Annual Cost | 130 K US$ |
Total Staff | 10 |
No of Operators | 6 |
Technical Data |
Reactor Type | POOL |
Thermal Power, Steady (kW) | 5,000.00 |
Max Flux SS, Thermal (n/cm2-s) | 7.0E13 |
Max Flux SS, Fast (n/cm2-s) | 5.0E13 |
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 | YES |
Forced Cooling | > 20 kW |
Coolant Velocity in Core | 1.63 M/S |
Reflector | BE |
Reflector Number of Sides | 4 |
Control Rods Material | CD |
Control Rods number | 6 |
Experimental Facilities |
Horizontal Channels | 5 |
Horizontal Max Flux (n/cm2-s) | 5.0E9 |
Horizontal Use | NEUTRON DIFFRACTION, RADIOGRAPHY, PGNAA, DEPTH PROFILING |
Vertical Channels | |
Vertical Max Flux (n/cm2-s) | |
Vertical Use | |
Core Irradiation Facilities | 8 |
Core Max Flux (n/cm2-s) | 7.0E13 |
Reflector Irradiation Facilities | 2 |
Loops Number | |
Loops Max Flux | |
Loops use |
Fuel data |
Origin of Fissile Material | Russia |
Enrichment Supplier | Russia |
Equilibrium Core Size | 36 |
Plates per Element | 16 |
Dimensions of Plates | 626 X 69.8 X 1.56 |
Rods per Element | |
Dimensions of Rods, mm | |
Tubes per Element | |
Dimensions of Tubes, mm | |
Cladding Material | AL ALLOY |
Cladding Thickness, mm | 0.48 |
Fuel Material | UALX - AL |
Fuel Thickness, mm | 0.61 |
Uranium Density, g/cm3 | 0.645 HEU; 1.258 MEU; 3.4 LEU |
Burnup on Discharge, max % | 50 |
Burnup Average, % | 42 |
Last Shipment Year | 2000 |
Last Receipt Year | 2005 |
Fuel Fabricator | CHILE FFP |
Utilization |
Hours per Day | 24 |
Days per Week | 1 |
Weeks per Year | 50 |
MW Days per Year | 250 |
Materials/fuel test experiments | Number of runs: 5 |
Isotope Production | 99mTc, 131I |
N/A | |
Neutron Scattering | Diffraction, Scattering, Diffusion |
N/A | |
Neutron Radiography | On-line beam hours: N/A |
Neutron capture therapy | NO |
Activation Analysis | N/A |
1571 | |
Transmutation | NO |
Geochronology | 40Ar/39Ar |
240 | |
Teaching | NO |
Training | NO |
Other Uses | NO |
Operating Experience |
Reactor | Thermal Power | Date of | Operational for | |||
Category | Type | kW | Criticality | Construction | Years | Months |
RESEARCH | POOL | 5000.00 | 1974/10/13 | 1970/10/10 | 35 | 7 |