IVG.1M Reactor

IVG.1M research reactor is an upgraded version of IVG.1 reactor used for tests of fuel assemblies (FA) and cores of high temperature gas-cooled reactors including nuclear jet propulsion (NJP) reactors and nuclear power propulsion plants (NPPP).

IVG.1M reactor can be used in tests providing solution of the following tasks:

  • testing of different type FA under operating conditions;
  • FA structure material reactor tests;
  • testing of FA structures and their elements;
  • study of possible accident conditions and testing of preventive measures.
Baikal-1 Reactor Complex

Baikal-1 Reactor Complex

Baikal-1 Reactor Complex

Reactor Control Room

Technical characteristics

Thermal power

72 MW

Core effective diameter

548 mm

Core height

800 mm

Uranium-235 content in the core

4,6 kg

Thermal neutron flux density

3,5×1014 n/cm2·s

Water rate through the reactor

up to 380 kg/s

Maximum water temperature

950°C

The most important works conducted recently at the reactor are:

  • studies on ITER (International Thermonuclear Experimental Reactor) structure material interaction with hydrogen and its isotopes under reactor irradiation condition;
  • study of reactor radiation scattering in the atmosphere to validate safety of nuclear power.
The Reactor View on the Reloading Machine Side

The Reactor View on the Reloading Machine Side