Published March 1989 | Version v1
Journal article Metadata-only

Verification of the analysis for fracture behaviour estimation of pressure vessels

Creators

  • 1. Valtion Teknillinen Tutkimuskeskus, Espoo (Finland)

Description

Within the Nordic countries a four-year research programme in the area of elastic-plastic fracture mechanics was initiated in 1985. The main technical objective of the programme is to clarify how catastrophic, that is unstable, fracture can be prevented in pressure vessels and piping by using the leak-before-break concept. In this article the experimental details of the first tests are described and compared to various analytical and numerical (2D and 3D) analyses. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
112
Series
Nucl. Eng. Des.
Journal Page Range
299-309
ISSN
0029-5493
CODEN
NEDEA

Conference

Title
The contribution of component and large specimen testing to structural integrity assessment methodology.
Original Conference Title
13. MPA Seminar ueber Sicherheit und Verfuegbarkeit in der Anlagentechnik: Der Beitrag der Komponenten- und Grossprobenpruefung zur Beurteilung von Bauteilen und Anlagen
Acronym
13. MPA seminar on safety and reliability of pressure components
Dates
8-9 Oct 1987.
Place
Stuttgart (Germany, F.R.).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
20061039
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CRACKS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; RUPTURES; THREE-DIMENSIONAL CALCULATIONS; VERIFICATION
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; FAILURES; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS