Reserve seismic capacity determination of a nuclear power plant braced frame with piping
Description
A typical diagonal braced steel frame was developed to determine the amount of reserve capacity that is available beyond elastic design levels. The frame was analyzed first using elastic static and dynamic analyses. The loadings included dead and live load, an equivalent static lateral earthquake load, two response spectra and a suite of eight earthquake time history records. The response spectra used were the Housner and Regulatory Guide 1.60. The time histories represented different site conditions, distances to causative faults and magnitudes. The lateral static load and Housner spectrum represent vintage design criteria, while the R.G. 1.60 and time history analyses reflect current methodology. The elastic limit responses of the structure were determined along with the accompanying threshold peak ground accelerations (threshold g values). The frame was then analyzed using the program DRAIN-2D to perform two-dimensional elastic--plastic analyses for the eight time histories
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- UCRL--82423
Conference
- Title
- International conference on structural mechanics in reactor technology.
- Dates
- 13 - 17 Aug 1979.
- Place
- Berlin, F.R. Germany.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11500176
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; NUCLEAR POWER PLANTS; PIPES; SEISMIC EFFECTS; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-790802--35.