Published 2003 | Version v1
Miscellaneous Open

Development of seismic damage assessment system for nuclear power plant structures in Korea

  • 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)
  • 2. Seoul National University, Seoul (Korea, Republic of)

Description

A seismic damage assessment system that analyses in real-time the actual seismic resistance capacity and the damage level of power plant structures has been developed. The system consists of three parts: a 3-D inelastic seismic analysis, a damage assessment using a damage index based on the previous 3-D analysis, and a 3-D graphic representation. PSC containment structures are modelled by finite shell elements using layered method and analysis is performed by means of time history inelastic seismic analysis method, which takes into account material nonlinearities. HHT-α, one kind of direct integration method, is adopted for the seismic analysis. Two damage indices at finite element and structural levels are applied for the seismic damage assessment. 3-D graphical representation of dynamic responses and damage index expedites procedure for evaluating the damage level. The developed system is now being installed at the Earthquake Monitoring Center of KINS (Korea Institute of Nuclear Safety) to support site inspections after an earthquake occurrence, and decisions about effective emergency measures, repair and operations of the plant. (author)

Files

36071665.pdf

Files (1.1 MB)

Name Size Download all
md5:874e5ad47273c2dcef4dabbff8d8b9b8
1.1 MB Preview Download
Part of:
Proceedings of the 17th international conference on structural mechanics in reactor technology

Additional details

Publishing Information

Publisher
Vysoka skola technicka
Imprint Place
Brno (Czech Republic)
Imprint Title
Proceedings of the 17th international conference on structural mechanics in reactor technology
Imprint Pagination
[3216 p.]
Journal Page Range
p. 2061-2066
Report number
INIS-CZ--0039

Conference

Title
17. international conference on structural mechanics in reactor technology
Acronym
SMIRT 17
Dates
17-22 Aug 2003
Place
Prague (Czech Republic)

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
36071665
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT BUILDINGS; DESIGN; EARTHQUAKES; FINITE ELEMENT METHOD; NUCLEAR POWER PLANTS; POWER REACTORS; SEISMIC EFFECTS; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
BUILDINGS; CALCULATION METHODS; CONTAINMENT; MATHEMATICAL SOLUTIONS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; REACTORS; SEISMIC EVENTS; THERMAL POWER PLANTS

Optional Information

Notes
Presented within section K02: Seismic analysis, design and qualification - General seismic issues II. 6 figs., 12 refs. Imprint:Published on CD-ROM in the PDF format for Adobe Acrobat; contact: Prof. S. Vejvoda, Institute of Applied Mechanics, Brno University of Technology, Brno, Czech Republic