Published 1985 | Version v1
Book

On the analysis of cracks in nuclear piping

Creators

  • 1. Ansaldo S.p.A. - Divisione Impianti, Genoa

Description

In this paper a criterion is discussed to eliminate the unrealistic hypothesis of catastrophic failure in a nuclear grade pipe. Experimental evidence is given to sustain a design curve based upon the SHA (Strain Hardening Approach) method. The validity of the approach is discussed with particular reference to the problem of crack stability. Safety margins are demonstrated, showing that in general nuclear piping loads are much lower than the critical ones postulated herein

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (USA)
Imprint Title
Proceedings of the 1985 pressure vessels and piping conference. Volume PVP-98-8. Fracture, fatigue and advanced mechanics
Journal Page Range
p. 107-114.

Conference

Title
ASME Pressure Vessel and Piping Division conference.
Dates
24-29 Jun 1985.
Place
New Orleans, LA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17073404
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRACK PROPAGATION; FAILURES; PIPES; REACTOR COOLING SYSTEMS; REACTOR SAFETY; STABILITY; STRAIN HARDENING
Descriptors DEC
COOLING SYSTEMS; HARDENING; REACTOR COMPONENTS; SAFETY