Stochastic evaluation of the dynamic response and the cumulative damage of nuclear power plant piping
- 1. Tokyo Metropolitan Univ. (Japan). Faculty of Technology
Description
This report deals with a fundamental study concerning an evaluation of uncertainties of the nuclear piping response and cumulative damage under excess-earthquake loadings. The main purposes of this study cover following several problems. (1) Experimental estimation analysis of the uncertainties concerning the dynamic response and the cumulative failure by using piping test model. (2) Numerical simulation analysis by Monte Carlo method under the assumption that relation between restoring force and deformation is characterized by perfectly elasto-plastic one. (Checking the mathematical model.) (3) Development of the conventional uncertainty estimating method by introducing a perturbation technique based on an appropriate equivalently linearized approach. (Checking the estimation technique.) (4) An application of this method to more realistical cases. Through above mentioned procedures some important results are obtained as follows; First, fundamental statistical properties of the natural frequencies and the number of cycle to failure crack initiation are evaluated. Second, the effect of the frequency fluctuation and the yielding fluctuation are estimated and examined through Monte Carlo simulation technique. It has become clear that the yielding fluctuation gives significant effect on the piping power response up to its failure initiation. Finally some results through proposed perturbation technique are discussed. Statistical properties estimated coincide fairly well with those through numerical simulation. (author)
Additional details
Publishing Information
- Journal Title
- Mem. Fac. Tech., Tokyo Metropolitan Univ.
- Journal Issue
- no.30
- Series
- Mem. Fac. Tech., Tokyo Metropolitan Univ.
- ISSN
- 0082-4747
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 13696572
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CRACKS; ELASTICITY; FAILURES; FLUCTUATIONS; FRACTURE MECHANICS; FRACTURE PROPERTIES; MONTE CARLO METHOD; NUMERICAL SOLUTION; PERTURBATION THEORY; PIPES; PLASTICITY; REACTOR COMPONENTS; SEISMIC EFFECTS; STATISTICAL MODELS; STATISTICS
- Descriptors DEC
- MATHEMATICAL MODELS; MATHEMATICS; MECHANICAL PROPERTIES; MECHANICS; VARIATIONS