Published 1997 | Version v1
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Fracture analyses of WWER reactor pressure vessels

  • 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany)

Description

In the paper first the methodology of fracture assessment based on finite element (FE) calculations is described and compared with simplified methods. The FE based methodology was verified by analyses of large scale thermal shock experiments in the framework of the international comparative study FALSIRE (Fracture Analyses of Large Scale Experiments) organized by GRS and ORNL. Furthermore, selected results from fracture analyses of different WWER type RPVs with postulated cracks under different loading transients are presented. 11 refs, 13 figs, 1 tab

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Part of:
Methodology for pressurized thermal shock evaluation. Proceedings of the IAEA specialists meeting. Working material

Additional details

Publishing Information

Imprint Title
Methodology for pressurized thermal shock evaluation. Proceedings of the IAEA specialists meeting. Working material
Imprint Pagination
457 p.
Journal Page Range
p. 325-345.
Report number
IWG-LMNPP--96/1

Conference

Title
IAEA specialists' meeting on methodology for pressurized thermal shock evaluation.
Dates
5-8 May 1997.
Place
Esztergom (Hungary).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28059649
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
AGING; FINITE ELEMENT METHOD; FRACTURE MECHANICS; LIFETIME; PRESSURE VESSELS; THEORETICAL DATA; THREE-DIMENSIONAL CALCULATIONS; WWER TYPE REACTORS
Descriptors DEC
CALCULATION METHODS; CONTAINERS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; MECHANICS; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information