Uranium-graphite reactor development in the USSR
Description
The paper analyses design experience and development prospects of graphite-moderated channel power reactors, which represent one of the main lines of nuclear power activity in the Soviet Union. The characteristics of these reactors are described and discussed, and data are presented to show that their power can be increased to 1.5 million kW and more. The authors consider some technical solutions which would ensure the reliability and safety of such reactors, at higher power, and describe those adopted for the projected 2.4 million kW channel reactor in sectional block design with nuclear steam superheat. The prospects for further growth of unit capacities and improvement of the technical and economic characteristics of these reactors are discussed
Availability note (English)
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8303611.pdf
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Additional details
Additional titles
- Original title (Russian)
- Razvitie uran-grafitovykh kanal'nykh reaktorov v SSSR
- Augmented title (English)
- RBMK-1000 and RBMK-1500 reactors, RBMKP-2400 reactor design of modular construction
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- IAEA-CN--36/586
Conference
- Title
- International conference on nuclear power and its fuel cycles.
- Dates
- 2 - 13 May 1977.
- Place
- Salzburg, Austria.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 8303611
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL CHANNELS; FUEL CYCLE; LWGR TYPE REACTORS; NUCLEAR SUPERHEATING; PLANNING; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR OPERATION; SPECIFICATIONS
- Descriptors DEC
- COOLING SYSTEMS; GRAPHITE MODERATED REACTORS; HEATING; OPERATION; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SUPERHEATING; WATER COOLED REACTORS
Optional Information
- Notes
- 1.C.-.P.1./05 Also available in English.