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The Russian abbreviation VVER stands for 'water-water energy reactor' (i.e. water-cooled water-moderated energy reactor). The design is a type of pressurised water reactor (PWR). The main distinguishing features of the VVER [3] compared to other PWRs are: Horizontal steam generators; Hexagonal fuel assemblies; No bottom penetrations in the ...
It would use VVER-1300/510 water pressurized reactors constructed to meet modern nuclear and radiation safety requirements. The VVER-TOI project is developed on the basis of the design documents worked out for AES-2006, considering the experience gained in development of projects based on VVER technology both in Russia and abroad, such as ...
This category includes power stations with the VVER-440, VVER-1000, VVER-1200 reactors. Pages in category "Nuclear power stations using VVER reactors" The following 33 pages are in this category, out of 33 total.
The VVER-1300 design is also known as the AES-2010 design, and is sometimes mistakenly designated as the VVER-TOI design. The VVER-1300/510 is based on the VVER-1200/392M that was originally used as the reference design for the VVER-TOI project, although the VVER-1300/510 now serves that role (which has led to confusion between the VVER-TOI ...
Control rod assembly for a pressurized water reactor, above fuel element Control rods are used in nuclear reactors to control the rate of fission of the nuclear fuel – uranium or plutonium . Their compositions include chemical elements such as boron , cadmium , silver , hafnium , or indium , that are capable of absorbing many neutrons without ...
The reactors are pressurised water reactor of Russian design, model VVER-1000/V-412 referred also as AES-92. Thermal capacity is 3,000 MW, gross electrical capacity is 1,000 MW with a net capacity of 917 MW. [28] Construction is by NPCIL and Atomstroyexport.
The nuclear plant has six Soviet-designed VVER-1000 V-320 water-cooled and water-moderated reactors containing Uranium 235, and also has spent nuclear fuel at the facility.
Most units use VVER pressurized water reactor (PWR) technology supplied from Russia. The first four units are Russian standard reactors of type VVER-1000, and have capacity approximately 1 GW. Units 5 and 6 are Chinese-designed ACPR-1000 reactors, with a traditional 3-loop system. Units 7 and 8 will use the updated VVER-1200 design capable of ...