Published 2009 | Version v1
Report Metadata-only

Lifetime analysis of WWER Reactor Pressure Vessel Internals concerning material degradation

Creators

  • 1. Bay Zoltan Foundation for Applied Research, Institute for Logistics and Production Systems, Miskolc-Tapolca (Hungary)

Description

Present study aims at extending the operational lifetime of its WWER 440 type Units. Namely, the purpose of this task is to perform evaluative analysis of presumable changes in material properties of WWER 440 RVI. In line with this objective, making use of this analysis, this study shall determine that are there degradation mechanism, which limits the lifetime of the structural elements

Part of:
20. International conference on structural mechanics in reactor technology

Additional details

Identifiers

URL
http://www.vtt.fi/inf/pdf/symposiums/2009/S256.pdf;

Publishing Information

ISBN
978-951-38-6336-4; 978-951-38-6335-7
Imprint Title
20. International conference on structural mechanics in reactor technology
Imprint Pagination
450 p.
Journal Page Range
p. 128-130
Report number
VTT-SYMP--256

Conference

Title
20. International conference on structural mechanics in reactor technology.
Acronym
SMiRT 20
Dates
9-14 Aug 2009
Place
Espoo (Finland)

INIS

Country of Publication
Finland
Country of Input or Organization
Finland
INIS RN
41124990
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Non-conventional Literature, Conference
Descriptors DEI
AGING; DRILLING EQUIPMENT; GUIDE TUBES; LIFETIME EXTENSION; MATERIALS TESTING; NEUTRON FLUENCE; PRESSURE VESSELS; TIME DEPENDENCE; WWER TYPE REACTORS
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; EQUIPMENT; LIFETIME; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SERVICE LIFE; TESTING; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs. Imprint:More information available at http://www.iasmirt.org/