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