Published April 2019 | Version v1
Journal article

Seismic fragility evaluation of the base-isolated nuclear power plant piping system using the failure criterion based on stress-strain

  • 1. Seismic Research and Test Center, Pusan National University, Yangsan (Korea, Republic of)
  • 2. Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

In the design criterion for the nuclear power plant piping system, the limit state of the piping against an earthquake is assumed to be plastic collapse. The failure of a common piping system, however, means the leakage caused by the cracks. Therefore, for the seismic fragility analysis of a nuclear power plant, a method capable of quantitatively expressing the failure of an actual piping system is required. In this study, it was conducted to propose a quantitative failure criterion for piping system, which is required for the seismic fragility analysis of nuclear power plants against critical accidents. The in-plane cyclic loading test was conducted to propose a quantitative failure criterion for steel pipe elbows in the nuclear power plant piping system. Nonlinear analysis was conducted using a finite element model, and the results were compared with the test results to verify the effectiveness of the finite element model. The collapse load point derived from the experiment and analysis results and the damage index based on the stress-strain relationship were defined as failure criteria, and seismic fragility analysis was conducted for the piping system of the BNL (Brookhaven National Laboratory) - NRC (Nuclear Regulatory Commission) benchmark model

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
51
Journal Issue
2
Series
33 refs, 14 figs, 5 tabs
Journal Page Range
p. 561-572
ISSN
1738-5733

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50064667
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BENCHMARKS; CRACKS; DESIGN; FAILURES; FINITE ELEMENT METHOD; NUCLEAR POWER PLANTS; PIPES; SEISMIC EFFECTS; STRAINS; STRESSES
Descriptors DEC
CALCULATION METHODS; MATHEMATICAL SOLUTIONS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; THERMAL POWER PLANTS; TUBES