Published 2003 | Version v1
Miscellaneous Open

The reevaluation of seismic safety of existing nuclear power plant

Description

We have carried out additional geological surveys in order to enrich our database on geological faults in the vicinity of Shimane Nuclear Power Plant (NPP). Prior to additional geological surveys, given the social importance of nuclear power plants, we hypothetically assumed that almost the whole length of an area covered by surveys would be an active fault that must be considered in seismic design, and tried to reevaluate the seismic safety of the NPP by applying an input earthquake ground motion larger than the level at the design stage. As a result, we have confirmed that seismic safety of the NPP can be maintained. This paper describes the method that we employed to reevaluate the seismic safety of Shimane NPP. (author)

Files

36071675.pdf

Files (255.9 kB)

Name Size Download all
md5:a8ce713d38e14f98e96e02bca3fc4196
255.9 kB 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. 2298-2305
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
36071675
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; EARTHQUAKES; REACTOR SAFETY; SEISMIC EFFECTS; SEISMIC WAVES; SHIMANE-1 REACTOR
Descriptors DEC
BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; SEISMIC EVENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Presented within section K07: Seismic analysis, design and qualification - Seismic re-evaluation. 11 figs., 7 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