Published 1997 | Version v1
Book

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.