VPBER-600 enhanced safety water cooled medium power reactor
Creators
- 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)
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).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 24067311
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; DESIGN; MODIFICATIONS; NATURAL CONVECTION; POWER RANGE 100-1000 MW; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; SAFETY ANALYSIS; TIME DEPENDENCE; USSR
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; EASTERN EUROPE; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; HEAT TRANSFER; MEGAWATT POWER RANGE; POWER RANGE; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Composed of four volumes.