Published 1995 | Version v1
Book Metadata-only

Performance of a commercial finite element program in simulating ratcheting in piping

Creators

  • 1. North Carolina State Univ., Raleigh, NC (United States). Center for Nuclear Power Plant Structures, Equipment and Piping

Description

Based on a review of high-level seismic tests on piping components and systems, and the corresponding analyses, we concluded that existing finite element codes are incapable of accurately simulating the ratcheting behavior observed in the experiments. We have incorporated an improved cyclic plasticity model into an ANSYS user subroutine and demonstrated its effectiveness by comparing ANSYS simulations with the results of a set of ratcheting experiments. (author). 5 refs., 4 figs

Part of:
Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 3

Additional details

Publishing Information

Publisher
Editora de Universidade Federal do Rio Grande do Sul.
Imprint Place
Porto Alegre, RS (Brazil)
ISBN
85-7025-351-6
Imprint Title
Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 3
Imprint Pagination
647 p.
Journal Page Range
p. 489-494.

Conference

Title
13. International Conference on Structural Mechanics in Reactor Technology.
Dates
13-18 Aug 1995.
Place
Porto Alegre, RS (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
27053993
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; DYNAMIC LOADS; EARTHQUAKES; FINITE ELEMENT METHOD; GROUND MOTION; MECHANICAL VIBRATIONS; NUCLEAR POWER PLANTS; PIPES; REACTOR COMPONENTS; RISK ASSESSMENT; SAFETY; SEISMIC EFFECTS; SEISMIC EVENTS; SEISMOLOGY; SOIL-STRUCTURE INTERACTIONS
Descriptors DEC
CALCULATION METHODS; MOTION; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.