The next generation analysis methodology for cracked pipe systems subjected to dynamic loads
- 1. Battelle, Columbus, OH (United States)
Description
Evaluation procedures for cracked piping systems under dynamic loads, seismic and water hammer in particular, have evolved over the years from assuming an instantaneous brittle double-ended pipe break in the early years of the nuclear industry, to using peak load from a linear elastic analysis with elastic-plastic fracture mechanics over the past 10 years. With improvements in computing power and developments in the fracture mechanics analysis of cracked pipe, it is now possible, using work station computers, to perform nonlinear time-history cracked-pipe analyses that can predict, not only the maximum load, but an make reasonably accurate, but slightly conservative, predictions of the time to surface crack penetration, how far the crack may propagate around the circumference, and the crack opening history for leak rate, decompression, and jet-force calculations. This new analysis methodology, the so-called cracked-pipe element nonlinear FEA fracture analysis is currently being formulated and refined. The analytical methods and comparison with experimental cracked-pipe data, as well as some specific applications illustrating margins obtained by this methodology versus more traditional analyses will be summarized
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1198-0
- Imprint Title
- Seismic engineering -- 1994: Volume 1. PVP-Volume 275-1
- Imprint Pagination
- 287 p.
- Journal Page Range
- p. 159-172.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26021584
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACK PROPAGATION; DESIGN; EXPERIMENTAL DATA; FINITE ELEMENT METHOD; FORECASTING; FRACTURE PROPERTIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ISOTOPE PRODUCTION REACTORS; NUCLEAR POWER PLANTS; PIPELINES; PIPES; PWR TYPE REACTORS; SEISMIC EFFECTS; SERVICE LIFE; STRESS ANALYSIS
- Descriptors DEC
- CALCULATION METHODS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; IRRADIATION REACTORS; LIFETIME; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER PLANTS; POWER REACTORS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.