Published 2003
| Version v1
Miscellaneous
Open
The reevaluation of seismic safety of existing nuclear power plant
Creators
- 1. The Chugoku Electric Power Company, Hiroshima (Japan)
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 |
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