Published 1992 | Version v1
Book

VPBER-600 enhanced safety water cooled medium power reactor

  • 1. Experimental Machine Building Design Bureau, Nizhny Novgorod (Russian Federation)

Description

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)

Part of:
ANP'92 international conference on design and safety of advanced nuclear power plants

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
ANP'92 international conference on design and safety of advanced nuclear power plants
Imprint Pagination
[2182 p.].
Journal Page Range
v. 1 p. 4.5/1-4.5/6.

Conference

Title
international conference on design and safety of advanced nuclear power plants.
Acronym
ANP'92
Dates
25-29 Oct 1992.
Place
Tokyo (Japan).

Optional Information

Notes
Imprint:Composed of four volumes.