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23.01.2019

IGR Reactor

Impulse research reactor IGR is a self-quenching uranium-graphite homogeneous thermal neutron reactor. It was established in 1985, the physical start-up and commissioning of the reactor has been carried in 1960.

Among impulse graphite reactors of a large integral capacity, the IGR reactor has the highest thermal neutron fluence in the experimental cavity 228 mm in diameter and 3825 mm in height.

Technical specifications of the IGR reactor:

  • Thermal neutron flux density …………………………………………. 7×1016 n/cm2.s
  • Thermal neutron fluence ………………………………………………. 3.7×1016 n/cm2
  • Minimum half-width of impulse…….………………………………… 0.12 s
  • Diameter/length of a central experimental channel .………………….. 0.228 /3.825 m
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Ample opportunities to combine operational performances of the reactor, pneumohydraulic stand and loop units as well as long operating experience indicate that IGR Reactor Complex is one of the best instruments for addressing the challenge of dynamic testing the nuclear engineering facilities.    

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Within the scope of the most significant long-standing research and development programs implemented at the IGR reactor, the following was studied:

  • nuclear fuel thermal resistance under Nuclear Rocket Engine (NRE) Program;
  • radiation resistance of electronic installations and automation elements of space and airborne vehicles;
  • triggering modes of terrestrial NRE prototypes;
  • reactor dynamics with reactivity up to  5 β;
  • impulse reactor control systems;
  • release and deposition of fission products in different experimental devices;
  • performance limit of fuel elements and FAs with a fuel of various component composition and dedication – space, transport, research and energy.