Implementing SPRA probabilistic fragility analysis of four typical nuclear structures

Book · Sun Dec 31 04:00:00 EST 1995

OSTI ID:170367

Zhao, Y; Wilson, P R; Stevenson, J D ^[1]

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1. Stevenson and Associates, Inc., Cleveland, OH (United States)

In this paper the procedures used and the results obtained in the Seismic Probabilistic Risk Assessment (SPRA) fragility analysis are presented for four typical structures that include three year enclosures and buildings, and a turbine building complex of a pressurized water reactor (PWR) nuclear power plant (NPP) located East of the Rocky Mountains. The major procedures include structural modeling, structural dynamic analysis, failure mode and strength capacity evaluation, determination of randomness and uncertainty parameters of variables involved, and the SPRA fragility and the medium High Confidence Low Probability of Failure (HCLPF{sub 50}) calculation in terms of the peak ground acceleration (PGA). The three-dimensional (3-D) structural models developed have different features from each other including a fixed-base stick model of a reinforced concrete structure physically separated from a housed tank, a stick model of a reinforced concrete structure including the effects of the housed tank response and structure-foundation interaction (SFI), a fixed-base full size steel frame structure, and a stick model with a combination of reinforced concrete and steel frame members and including the SFI effects. The 3-D response spectrum dynamic analyses were performed directly on these structure models using the site specific free field 50th percentile Uniform Hazard Spectrum shape (UHS) based on a 10,000 year return period earthquake factored to a Review Level Earthquake (RLA) Zero Period Ground Acceleration (ZPGA) of 0.4 g. Different failure modes were evaluated using the associated failure criteria for the structure models. Some insights are expected from the typical application of the SPRA probabilistic fragility analysis of nuclear structures.

• OSTI ID: 170367
• Report Number(s): CONF-950740--; ISBN 0-7918-1343-6
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BUILDINGS
CONDENSATES
EARTHQUAKES
FAILURE MODE ANALYSIS
FIRE EXTINGUISHERS
FUEL OILS
MATHEMATICAL MODELS
NUCLEAR POWER PLANTS
NUMERICAL DATA
PROBABILISTIC ESTIMATION
SAFETY ANALYSIS
SOIL-STRUCTURE INTERACTIONS
STEAM TURBINES
STORAGE
STORAGE FACILITIES
STRESS ANALYSIS
THREE-DIMENSIONAL CALCULATIONS