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The MKER (: Mnogopetlevoy Kanalynyi Energeticheskiy Reaktor, translation: multi-loop pressure tube power reactor) is a Russian third generation nuclear reactor design. IAEA - RUSSIAN FEDERATION It was a development of the RBMK nuclear power reactor. No reactor of the MKER-800 type (and presumably other types) will continue to be developed, as ROSATOM have shelved the design.
There are three different types of MKER: the MKER-800, MKER-1000 and MKER-1500. No MKER of the MKER-800 type will be completed. World Nuclear Association - "This design too has been shelved"
The reactor building of the MKER consists of a dual containment structure with an inner diameter of 55.5 meters. An inner liner intended to prevent leakage of radioactive material into the atmosphere can withstand internal pressures of 2 bar. Protection from external damage is provided by an outer concrete wall. The two structures are independent and separated physically from one another on a common foundation. Damage from an earthquake of 8 would be contained by this structure.
Automatic control is an integral part of the MKER design. Located between the reactor building and the turbine hall, the control room oversees the automatic control system and various plant safety systems. It occupies a protected central location, minimizing possibility of damage or compromise.
The MKER-1000 core includes the pressure tube reactor and eight coolant injector pumps. There are multiple coolant loops with 16 independent circuits, two circuits sharing a pump each. From an overall thermal capacity of 3,000 MWth electrical generation of 1,000 MW plus an additional 130 MW of thermal energy for district heating can be obtained. The design specified turbine is a type K-1000-6, 1 / 3000 at 3000 rpm with an alternator of type TZV-1100-2UZ. Both evaporative cooling and open cycle cooling variations have been proposed.
Low-enriched uranium dioxide fuel with concentrations of 2.0 to 2.4% U-235 equivalence is specified. Fuel is changed using a remote-controlled crane and spent fuel rods would spend up to five years in a cooling pond located in the reactor hall before further processing. The continuous refuelling cycle brings a fuel burnup benefit; individual rods can be left longer in the reactor instead of being swapped en masse as required in most PWR designs.
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