Evolution of reactor plants with VVER-type reactors and basic principles of safety systems and normal systems application in accidents with core damage
- 1. Electrogorsk Research ampersand Engineering Centre of Nuclear Plants Safety, Moscow (Russian Federation)
- 2. Experimental ampersand Design Organization GIDROPRESS, Moscow (Russian Federation)
Description
The principal negative effect of beyond-design accidents, accidents of core damage included, is confined to a possibility of source term to the environment. The amount and nature of this process is determined by numerous parameters, including safety barriers resistance to radionuclides release. These barriers (natural structural boundaries) are: fuel matrix, fuel cladding, reactor vessel and primary circuit, concrete pit, reactor plant equipment compartments. On the basis of comparing safety systems for different reactor plants equipped with VVER reactors the article covers the main principles of using the former in accidents of core collapse as applied for the peculiarities of each stage of destruction. Methods of suppression and localization of beyond-design accidents taking into account the safety systems design features. 4 refs., 14 tabs
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Title
- Proceedings of the international topical meeting on advanced reactors safety: Volume 1
- Imprint Pagination
- 640 p.
- Journal Page Range
- p. 282-289.
Conference
- Title
- American Nuclear Society (ANS) international meeting on advanced reactors safety.
- Acronym
- ARS '97
- Dates
- 1-5 Jun 1997.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29012825
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; FUEL ASSEMBLIES; REACTOR ACCIDENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-970607--Vol.1.