| Country | Japan |
| Facility Name | JRR-3M |
| Facility Number | JP-0008 |
| Status | OPERATIONAL |
| Last Updated | 2002/08/30 |
| General Data |
| Owner | JAPAN ATOMIC ENERGY RESEARCH INSTITUTE |
| Operator | TOKAI RESEARCH ESTABLISHMENT |
| Licensing | MINISTRY OF EDUCATION, CULTURE, SPORTS, SCIENCE & TECHNOLOGY |
| Construction Date | 1985/08/02 |
| Criticality Date | 1990/03/22 |
| Safeguards | IAEA |
| Initial Cost | 32.5 B YEN |
| Annual Cost | 1.8 B YEN |
| Total Staff | 41 |
| No of Operators | 25 |
| Technical Data |
| Reactor Type | POOL |
| Thermal Power, Steady (kW) | 20,000.00 |
| Max Flux SS, Thermal (n/cm2-s) | 2.7 E14 |
| Max Flux SS, Fast (n/cm2-s) | 1.4E14 |
| 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 | 2400 M3/HR |
| Coolant Velocity in Core | 5.9 M/S |
| Reflector | BE,D2O,H2O |
| Reflector Number of Sides | 4 |
| Control Rods Material | HF |
| Control Rods number | 6 |
| Experimental Facilities |
| Horizontal Channels | 9 |
| Horizontal Max Flux (n/cm2-s) | |
| Horizontal Use | BEAM EXPERIMENTS |
| Vertical Channels | 17 |
| Vertical Max Flux (n/cm2-s) | 2.7E14 |
| Vertical Use | MATERIAL IRRADIATION TESTS, RADIOISOTOPES PRODUCTION |
| Core Irradiation Facilities | 9 |
| Core Max Flux (n/cm2-s) | 2.7E14 |
| Reflector Irradiation Facilities | 8 |
| Loops Number | |
| Loops Max Flux | |
| Loops use |
| Fuel data |
| Origin of Fissile Material | USA |
| Enrichment Supplier | USA |
| Equilibrium Core Size | 26 |
| Plates per Element | 21 |
| Dimensions of Plates | 1.521X 71.0 X 770 |
| Rods per Element | |
| Dimensions of Rods, mm | |
| Tubes per Element | |
| Dimensions of Tubes, mm | |
| Cladding Material | AL ALLOY |
| Cladding Thickness, mm | 0.38 |
| Fuel Material | U3O8ALX & U3SI2ALX |
| Fuel Thickness, mm | 0.51 |
| Uranium Density, g/cm3 | 4.8 |
| Burnup on Discharge, max % | 60 |
| Burnup Average, % | 30 |
| Last Shipment Year | |
| Last Receipt Year | 2002 |
| Fuel Fabricator | CERCA, FRANCE |
| Utilization |
| Hours per Day | 24 |
| Days per Week | 7 |
| Weeks per Year | 28 |
| MW Days per Year | 3300 |
| Materials/fuel test experiments | Number of runs: 6 |
| Isotope Production | 192 Ir, 198Au, 196Yb, 60Co |
| 600000 | |
| Neutron Scattering | Neutron scattering |
| 926 | |
| Neutron Radiography | On-line beam hours: 1500 |
| Neutron capture therapy | NO |
| Activation Analysis | PGNAA, INAA |
| 1500 | |
| Transmutation | Mass of Silicon (kg) : 2354 Mass of gemstones (kg): N/A |
| Geochronology | Fission Track |
| 2 | |
| 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 | 20000.00 | 1990/03/22 | 1985/08/02 | 19 | 11 |