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
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 25052681
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT SHELLS; DIAGRAMS; ECCS; INTEGRATED COOLING SYSTEMS; MODIFICATIONS; REACTOR CONTROL SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR SAFETY FUSES; WWER TYPE REACTORS
- Descriptors DEC
- CONTAINMENT; CONTROL SYSTEMS; COOLING SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; INFORMATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS