Published 2000
| Version v1
Journal article
Evaluation of fatigue-ratcheting damage of a pressurised elbow undergoing damage seismic inputs
Creators
- 1. Ecole Polytechnique, 91 - Palaiseau (France). Lab. de Mecanique des Solides
- 2. Laboratoire de Mecanique, ENSTA, 91760, Palaiseau (France)
Description
We present a simplified method to calculate the plastic ratchet of elbow-shaped pipes submitted to seismic loading and an internal pressure. This method is simplified in the sense that the value of the ratchet is obtained without the use of finite element method (FEM) calculations. Here we derive a formula and use it to evaluate the fatigue-ratcheting damage of an elbow. This approach is applicable to complex plastic response appropriately described by non-linear kinematics hardening, which is more realistic for stainless steel such as 316-L. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 196
- Journal Issue
- 1
- Journal Page Range
- p. 41-50
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- Nuclear advances through global cooperation (ICONE-5)
- Acronym
- 5. ASME/SFEN/JSME international conference on nuclear engineering
- Dates
- 25-29 May 1997
- Place
- Nice (France)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 31016567
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUSTENITIC STEELS; BENDING; FATIGUE; HARDENING; NONLINEAR PROBLEMS; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; PLASTICITY; REACTOR COOLING SYSTEMS; REACTOR SAFETY; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; DEFORMATION; ENERGY SYSTEMS; ENGINEERING; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SAFETY; STEELS; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 7 refs.