학술논문
Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor.
Document Type
Article
Author
Source
Subject
*NUCLEAR energy
*SODIUM cooled reactors
*FAST reactors
*NUCLEAR facilities
*NUCLEAR engineering
*NUCLEAR reactor safety measures
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Language
ISSN
1063-4258
Abstract
The status of work on the development of a 1200 MW sodium-cooled reactor facility for serial construction is presented. The general characteristics of the facility and the power-generating unit as well as the objectives which must be attained as a result of the design are presented. The design of the power-generating group is based on solutions some of which have been checked during the operation of sodium-cooled reactors in Russia and some have been validated by the appropriate research and development work performed for BN-800. At the same time, new solutions are used which are aimed at improving the technical-economic indicators and increasing the level of safety. Additional R&D work will be needed to validate them. [ABSTRACT FROM AUTHOR]