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Technical data on RBMK-1500 reactor at Ignalina nuclear power plant – a decommissioned RBMK reactor. Chernobyl – A Canadian Perspective – A brochure describing nuclear reactors in general and the RBMK design in particular, focusing on the safety differences between them and CANDU reactors. Published by Atomic Energy of Canada Limited.
Chernobyl Nuclear Power Plant's original Soviet plan consisted of 12 units, and that units 5 and 6 were phase three of the plan. At the time, only two phases were complete, reactors 1, 2, 3 and 4. Both units were intended to be RBMK-1000 and would generate approximately 1,000 megawatts each, and also be supported by two cooling towers located ...
Reactor hall No. 1 of the Chernobyl Plant A simplified diagram comparing the Chernobyl RBMK and the most common nuclear reactor design, the Light water reactor. RBMK issues: 1. Using a graphite moderator in a water-cooled reactor, permitting criticality in a total loss of coolant accident. 2. A positive steam void coefficient that made the ...
A bigger problem was the design of the RBMK control rods, each of which had a graphite neutron moderator section attached to its end to boost reactor output by displacing water when the control rod section had been fully withdrawn from the reactor. That is, when a control rod was at maximum extraction, a neutron-moderating graphite extension ...
RBMK reactors, such as the reactors at Chernobyl, had a dangerously high positive void coefficient. This allowed the reactor to run on unenriched uranium and to require no heavy water, saving costs; RBMKs were also capable of producing weapons-grade plutonium, unlike the other main Soviet design, the VVER. [1]
The design and reliability of the turbines earned them the State Prize of Ukraine for 1979. The Kharkiv turbine plant later developed a new version of the turbine, K-500-65/3000-2, in an attempt to reduce use of valuable metal. The Chernobyl plant was equipped with both types of turbines; block 4 had the newer ones.
Generation II reactor designs generally had an original design life of 30 or 40 years. [3] This date was set as the period over which loans taken out for the plant would be paid off. However, many generation II reactors are being life-extended to 50 or 60 years, and a second life-extension to 80 years may also be economical in many cases. [ 4 ]
Leningrad Nuclear Power Plant (Russian: Ленинградская атомная электростанция; Ленинградская АЭС Leningradskaya atomnaya elektrostantsiya; Leningradskaya AES (pronunciation ⓘ)) is a nuclear power plant located in the town of Sosnovy Bor in Russia's Leningrad Oblast, on the southern shore of the Gulf of Finland, some 70 kilometres (43 mi) to ...