Privacy Notice
|
Security and Privacy Notice |
|
The VVER's are the Soviet counterpart of western Pressurized Water Reactor (PWR) designs. Like all nuclear units based on light water technology, the Soviet VVER design uses water to cool the reactor and to generate steam. Water also acts as moderator, slowing down the neutrons to increase the chances of fissioning. The moderating effect of the water also adds to safety since a water loss slows the nuclear chain reaction.
Earliest VVER's were developed by the Soviets before 1970. The most common one of those designs, the VVER-440 Model V230, employs six primary coolant loops, each with a horizontal steam generator. The modified version of the VVER-440, Model V213, was a product of the first uniform safety requirements drawn up by the Soviet designers. This model includes added emergency core cooling and auxiliary feedwater systems as well as upgraded accident localization systems. The larger VVER-1000 design, which was developed after 1975, is a four-loop system housed in a containment type structure with spray type steam suppression system.
See also: Current Publications