Published 2001 | Version v1
Report Open

Upgrading of VVER 440 nuclear safety

Creators

  • 1. Vuje, Nuclear Power Plant Research InstituteTrnava Inc., Okruzna 5, SK-91864 Trnava (Slovakia)

Description

Full text: Establishment of two separate safety systems; - modification of systems providing safe and reliable management of both Design Basis Accidents and Beyond Design Basis Accidents; - modification of reactor protection system to achieve failure probability less than 10-5/a; - enhancement of safety and reliability in residual heat removal mode during seismic events (Feed and Bleed in both secondary and primary systems); - increase of reliability in safety related power supplies; - enhancement of seismic resistance and fire protection. (author)

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Part of:
13th international workshop on nuclear public information in practice. Transactions

Additional details

Publishing Information

Imprint Title
13th international workshop on nuclear public information in practice. Transactions
Imprint Pagination
119 p.
Journal Page Range
p. 84
Report number
INIS-XA-C--014

Conference

Title
13. international workshop on nuclear public information in practice
Acronym
ENS PIME 2001
Dates
4-7 Feb 2001
Place
Evian (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
36033286
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; DESIGN BASIS ACCIDENTS; FIRE RESISTANCE; PRIMARY COOLANT CIRCUITS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SECONDARY COOLANT CIRCUITS; SEISMIC EVENTS; SEISMIC ISOLATION; SYSTEM FAILURE ANALYSIS; WWER TYPE REACTORS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SAFETY; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information