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Accident at Chernobyl nuclear power plant and its concequences. Part II. Annexes 1,3,4,5,6

AuteurUSSR State Committee
Datumaugustus 1986
Classificatie 2.34.8.10/07 (TSJERNOBYL - ONGELUK & OMGEVING - ALGEMEEN)
Voorkant

Uit de publicatie:

ANNEX 1

WATER-GRAPHITE CHANNEL REACTORS AND OPERATING EXPERIENCE WITH RBMK REACTORS

1. Water-graphite channel reactors and operating experience with RBMK reactors.

1.1. Water-graphite channel reactors use ordinary water as a coolant and graphite as
a moderator. The distinctive features of channel reactors are: the absence of a 
pressure vessel, the relative simplicity of the design, the extensive scope for channel-
by-channel inspection and control, the possibility of refuelling while the reactor is 
operating, the flexibility of the fuel cycle, and the practically unlimited potential 
for increasing the power by means of standard structural elements.

The first power reactor in the USSR was a channel-type reactor - the water-graphite 
reactor of the First Atomic Power Station, which had an electrical capacity of 5 MW 
and was started up in June 1954 at Obninsk, near Moscow.

The experience accumulated in the construction and operation of the First Atomic 
Power Station was utilized in planning the Beloyarsk Nuclear Power Plant (NPP) 
(1964, 300 MW).

The further development of the water-graphite reactor concept in the USSR led to the 
construction of the high power channel-type boiling-water reactor RBMK-1000 with 
an electrical capacity of 1000 MW, which, along side the WWER-1000 reactor, 
became the basic reactor for large-scale nuclear power production in the USSR.

The commissioning of the first RBMK-1000 reactor at the Leningrad NPP in 
1973 marked the inception of a series of reactors of this type.

The broad programme of construction of RBMK-1000 reactors carried out in the 
1970s led to the commissioning, over the period 1973 to 1985, of 14 reactors 
(4 reactors each at the Leningrad, Kursk, and Chernobyl' NPPs and 2 at the 
Smolensk NPP) with a total installed electrical capacity of 14 GW. In each new 
generation of reactors, improvements aimed at increasing their reliability and 
safety were introduced.

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