[en] 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

[en] Design bases of new generation nuclear power units (nuclear power plants - NPP, nuclear co-generation plants - NCP, nuclear distract heating plants - NDHP), using integral type PWPS, developed in OKBM, Nizhny Novgorod and trends of design decisions optimization are considered in this report. The problems of diagnostics, servicing and repair of the integral reactor components in course of operation are discussed. The results of safety analysis, including the problems of several accident localization with postulated core melting and keeping corium in the reactor vessel and guard vessel are presented. Information on experimental substantiation of the suggested plant design decisions is presented. (author)

[en] VPBER-600 new generation reactor is water-cooled and water-moderated medium power reactor with primary circuit integral arrangement. In VPBER-600 project in the framework of maximum use of self-protectiveness and passive safety principles there were further developed the main solutions on safety which were perfected in AST-500 NDHP and approved by IAEA expertise. The integral arrangement of equipment allowed to exclude in VPBER-600 the classes of accidents with primary circuit large and medium leaks, a simple circulation circuit and high level of natural circulation is provided which allowed to organize core cooling in all emergency situations. An additional passive barrier of localization is introduced, - the guard vessel, inclosing the reactor and primary circuit systems. There are envisaged completely passive secondary circuit independent systems for removal of heat in emergency through built-in heat exchangers which are actuated by self-operating direct-action devices. A system of simple passive means is established ensuring a high safety level of 'passive' VPBER-600 reactor. (author)

[en] Decription of basic design and schematic solutions of the VPBER-600 reactor are given. Technical basis and practical testing of the basis equipment are shown. Design principles of protection and localizing systems are presented. Safety concept based on the reactor inherant selfprotection and application of passive systems and device are formulated. The VPBER-600 reactor exceeds the best foreign facilities of the AP-600 type by the level of their safety

[en] This installation has a series of safety barriers and can be used in electricity or heat producing plants. A description of its parameters and technical solutions is given