Research Reactor Details - VK-50


Country Russian Federation
Facility Name VK-50
Facility Number RU-0043
Status OPERATIONAL
Last Updated 2009/06/23


General Data
Owner  MINISTRY ON ATOMIC ENERGY OF RUSSIAN FEDERATION
Operator  RESEARCH INSTITUTE OF ATOMIC REACTORS
Licensing  GOSATOMNADZOR OF RUSSIA
Construction Date  1965/11/15
Criticality Date  1965/07/01
Safeguards  MIA OF RUSSIAN FEDERATION
Initial Cost
Total Staff 225
No of Operators 163


Technical Data
Reactor Type BWR-PROTOTYPE
Thermal Power, Steady (kW) 200,000.00
Max Flux SS, Thermal (n/cm2-s) 5 E13
Max Flux SS, Fast (n/cm2-s) 1.5 E 14
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 No
Coolant Velocity in Core 1.0
Reflector H2O
Reflector Number of Sides All
Control Rods Material B,SS
Control Rods number 19


Experimental Facilities
Horizontal Channels No
Horizontal Max Flux (n/cm2-s)
Horizontal Use
Vertical Channels No
Vertical Max Flux (n/cm2-s)
Vertical Use
Core Irradiation Facilities
Core Max Flux (n/cm2-s)
Reflector Irradiation Facilities
Loops Number No
Loops Max Flux
Loops use


Fuel data
Origin of Fissile Material RUSSIA
Enrichment Supplier RUSSIA
Equilibrium Core Size
Plates per Element
Dimensions of Plates
Rods per Element 138
Dimensions of Rods, mm 7.58 OD
Tubes per Element
Dimensions of Tubes, mm 9.1 dia x 2000
Cladding Material ZR
Cladding Thickness, mm 0.65
Fuel Material UO2
Fuel Thickness, mm 6.28
Uranium Density, g/cm3 10.2
Burnup on Discharge, max % 30000 MWd/TU
Burnup Average, % 15000 MWd/TU
Last Shipment Year
Last Receipt Year
Fuel Fabricator RUSSIA


Utilization
Hours per Day  24
Days per Week  7
Weeks per Year  41
MW Days per Year  52000
Materials/fuel test experiments  Number of runs: 2
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  Support of new generation NPP; generation of heat/electricity


Operating Experience
Reactor Thermal Power Date of Operational for
Category Type kW Criticality Construction Years Months
 PROTOTYPE REACTOR  BWR-PROTOTYPE  200000.00  1965/07/01  1965/11/15  44  11