Published December 1993 | Version v1
Journal article

VPBEhR-600 reactor plant for nuclear stations of a new generation

Description

The design of the VPBEhR-600 reactor plant consisting of the water cooled and moderated integrated reactor, in the vessel of which the core with control system working devices, direct-current steam generator assemblied of heat-exchanging sections, built-in pressure compensator, main circulation pumps flow sections and heat exchangers-consensers of emergency core cooling system are located, is described. The VPBEhR-600 engineering solutions give an opportunity to create nuclear power plant of a new generation with improved safety basing on technologies well mastered by Russian industry

Additional details

Additional titles

Original title (Russian)
Реакторная установка VPBEhR-600 для атомных станций нового поколения

Publishing Information

Journal Title
Ehnergeticheskoe Stroitel'stvo
Journal Issue
no.12
Journal Page Range
p. 31-35.
CODEN
ENSTAC