Published 1985
| Version v1
Book
On the analysis of cracks in nuclear piping
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