| Country | Pakistan, Islamic Republic of |
| Facility Name | PARR-2 |
| Facility Number | PK-0002 |
| Status | OPERATIONAL |
| Last Updated | 2008/12/03 |
| General Data |
| Owner | PAKISTAN ATOMIC ENERGY COMMISSION |
| Operator | PAKISTAN INST. OF NUCLEAR SCI. & TECHNOLOGY |
| Licensing | PAKISTAN ATOMIC ENERGY COMMISSION |
| Construction Date | 1988/01/01 |
| Criticality Date | 1989/11/02 |
| Safeguards | IAEA |
| Initial Cost | 2 M US$ |
| Annual Cost | 70 K US$ |
| Total Staff | 10 |
| No of Operators | 7 |
| Technical Data |
| Reactor Type | MNSR |
| Thermal Power, Steady (kW) | 30.00 |
| Max Flux SS, Thermal (n/cm2-s) | 1.0E12 |
| Max Flux SS, Fast (n/cm2-s) | 3.2E11 |
| 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 | 10 MM/S |
| Reflector | BE,H2O |
| Reflector Number of Sides | ANNULAR+TOP+BOTTOM |
| Control Rods Material | CD |
| Control Rods number | 1 |
| 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 | 10 |
| Loops Number | |
| Loops Max Flux | |
| Loops use |
| Fuel data |
| Origin of Fissile Material | CHINA |
| Enrichment Supplier | CHINA |
| Equilibrium Core Size | 344 |
| Plates per Element | |
| Dimensions of Plates | |
| Rods per Element | 1 |
| Dimensions of Rods, mm | dia 5.5; 250 length |
| Tubes per Element | |
| Dimensions of Tubes, mm | |
| Cladding Material | AL ALLOY |
| Cladding Thickness, mm | 0.6 |
| Fuel Material | U-AL ALLOY |
| Fuel Thickness, mm | 4.3 DIA |
| Uranium Density, g/cm3 | 0.86 |
| Burnup on Discharge, max % | 1.5 |
| Burnup Average, % | |
| Last Shipment Year | |
| Last Receipt Year | 1989 |
| Fuel Fabricator | CHINA |
| Utilization |
| Hours per Day | 5 |
| Days per Week | 1 |
| Weeks per Year | 50 |
| MW Days per Year | 3 |
| Materials/fuel test experiments | NO |
| Isotope Production | NO |
| Neutron Scattering | NO |
| Neutron Radiography | NO |
| Neutron capture therapy | NO |
| Activation Analysis | INAA, RNAA, CNAA |
| 982 | |
| Transmutation | NO |
| Geochronology | NO |
| Teaching | Number of students: 50 |
| Training | Number of operators/experimenters trained: 2 |
| Other Uses | Tours for visitors. |
| Operating Experience |
| Reactor | Thermal Power | Date of | Operational for | |||
| Category | Type | kW | Criticality | Construction | Years | Months |
| RESEARCH | MNSR | 30.00 | 1989/11/02 | 1988/01/01 | 20 | 3 |