Seismic fragility analysis of a piping structure in a nuclear power plant
Creators
- 1. Dept. of Civil Engg., Indian Institute of Science, Bangalore (India)
Description
The problem of predicting the fragility of a piping structure using computational models is considered. A framework for including uncertainties in load characteristics, structural properties and modeling is proposed. The earthquake input impinging on the primary structure is modeled as a vector of stationary Gaussian random processes. The piping response, conditioned on the structural and modeling uncertainties, is predicted by using standard random vibration theory. The study assumes linear structural behavior and neglects any possible interaction between the reactor containment structure and the piping structure. Failure criteria, in terms of exceedance of structural response in a given duration and over specified levels, are formulated based on extreme value theory of Gaussian random processes. The unconditional failure probability is computed using a newly developed gradient-board approximation. The proposed procedure is first validated by using Monte Carlo simulations on simple structures and subsequently applied to a realistic nuclear power plant piping structure. (author)
Additional details
Publishing Information
- Publisher
- Allied Publishers Pvt. Ltd.
- Imprint Place
- New Delhi (India)
- ISBN
- 81-7764-415-7
- Imprint Title
- Proceedings of the national seminar on seismic design of nuclear power plants
- Imprint Pagination
- 536 p.
- Journal Page Range
- p. 301-312
Conference
- Title
- National seminar on seismic design of nuclear power plants
- Dates
- 21-22 Feb 2003
- Place
- Chennai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 34071832
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT BUILDINGS; FAILURES; FEASIBILITY STUDIES; GAUSSIAN PROCESSES; GROUND MOTION; MONTE CARLO METHOD; NUCLEAR POWER PLANTS; PIPES; RELIABILITY; SEISMIC EFFECTS; VALIDATION
- Descriptors DEC
- BUILDINGS; CALCULATION METHODS; CONTAINMENT; MOTION; NUCLEAR FACILITIES; POWER PLANTS; TESTING; THERMAL POWER PLANTS; TUBES
Optional Information
- Notes
- 14 refs., 4 figs., 3 tabs.