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Fracture analyses of WWER reactor pressure vessels

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Abstract

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.
Authors:
Sievers, J; Liu, X [1] 
  1. Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany)
Publication Date:
Sep 01, 1997
Product Type:
Technical Report
Report Number:
IWG-LMNPP-96/1; CONF-9705163-
Reference Number:
SCA: 210200; PA: AIX-28:059649; EDB-97:116468; SN: 97001844581
Resource Relation:
Conference: IAEA specialists` meeting on methodology for pressurized thermal shock evaluation, Esztergom (Hungary), 5-8 May 1997; Other Information: PBD: 1997; Related Information: Is Part Of Methodology for pressurized thermal shock evaluation. Proceedings of the IAEA specialists meeting. Working material; PB: 457 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PRESSURE VESSELS; FRACTURE MECHANICS; AGING; FINITE ELEMENT METHOD; LIFETIME; THEORETICAL DATA; THREE-DIMENSIONAL CALCULATIONS; WWER TYPE REACTORS
OSTI ID:
519700
Research Organizations:
International Atomic Energy Agency, Vienna (Austria). International Working Group on Life Management of Nuclear Power Plants
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ON: DE97640092; TRN: XA9744645059649
Availability:
INIS; OSTI as DE97640092
Submitting Site:
INIS
Size:
pp. 325-345
Announcement Date:
Sep 23, 1997

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Citation Formats

Sievers, J, and Liu, X. Fracture analyses of WWER reactor pressure vessels. IAEA: N. p., 1997. Web.
Sievers, J, & Liu, X. Fracture analyses of WWER reactor pressure vessels. IAEA.
Sievers, J, and Liu, X. 1997. "Fracture analyses of WWER reactor pressure vessels." IAEA.
@misc{etde_519700,
title = {Fracture analyses of WWER reactor pressure vessels}
 author = {Sievers, J, and Liu, X}
 abstractNote = {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.}
 place = {IAEA}
 year = {1997}
 month = {Sep}
 }