Published 1996 | Version v1
Miscellaneous

Analysis of the leak-before-break behaviour of the components loaded by significant torsional moments

  • 1. Technischer Ueberwachungs-Verein Norddeutschland e.V., Hamburg (Germany)

Description

Approximations are derived for a circumferential through-wall crack under bending and torsion and interaction diagrams are established for both load cases according to the plastic ultimate load and yield stress criteria methods. Evaluation of these approximations is done using finite element calculations. (orig./DG)

Abstract (German)

Es werden analytische Naeherungen fuer einen Umfangsdurchriss unter Biegung und Torsion abgeleitet und Interaktionsdiagramme fuer beide Lastfaelle nach der Plastische Grenzlast (PGL)- und Fliess-Spannungs-Kriterium (FSK)-Methode erstellt. Diese Naeherungen werden durch Finite-Elemente-Berechnungen bewertet. (orig./DG)
Part of:
Safety and reliability of plant technology with special emphasis on components of nuclear and conventional power plants - basis for evaluation and operating experience. Vol. 2. Papers 31-54

Additional details

Additional titles

Original title (German)
Untersuchung zum Leck-vor-Bruch-Verhalten von Rohrleitungskomponenten unter Beruecksichtigung signifikanter Torsionsmomente

Publishing Information

Imprint Title
Safety and reliability of plant technology with special emphasis on components of nuclear and conventional power plants - basis for evaluation and operating experience. Vol. 2. Papers 31-54
Imprint Pagination
453 p.
Journal Page Range
p. 43.1-43.15.

Conference

Title
Safety and reliability of plant technology components of nuclear and conventional power plants - basis for evaluation and operating experience.
Original Conference Title
22. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik -Komponenten nuklearer und konventioneller Kraftwerke - Beuteilungsgrundlagen und Betriebserfahrungen
Acronym
22. MPA seminar
Dates
10-11 Oct 1996.
Place
Stuttgart (Germany).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
28050140
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; CRACKS; CREEP; FINITE ELEMENT METHOD; FLEXURAL STRENGTH; LEAKS; PIPES; REACTOR COMPONENTS; REACTOR SAFETY; TORSION
Descriptors DEC
CALCULATION METHODS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; SAFETY

Optional Information

Notes
Imprint:Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Komponenten nuklearer und konventioneller Kraftwerke - Beurteilungsgrundlagen und Betriebserfahrungen. Bd. 2. Vortraege 31-54.