Published 1975
| Version v1
Report
Dynamic analysis of primary reactor coolant system subjected to seismic and LOCA loads, including shield-building interaction
Description
An integrated approach is presented for a linear three-dimensional dynamic analysis of a typical 900MWe PWR nuclear reactor coolant loop, accommodating dynamic-coupling and interaction effects of shield-building including soil-foundation springs and damping parameters. Also included are major influences on sensitive equipment due to their variable support boundary conditions and rigid restraints
Availability note (English)
MF available from INIS under the Report Number.Additional details
Publishing Information
- Imprint Pagination
- F 5/3, 14 p.
- Report number
- INIS-mf--2084
Conference
- Title
- 3. International conference on structural mechanics in reactor technology.
- Dates
- 01 Sep 1975.
- Place
- London, UK.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 7237136
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOSS OF COOLANT; MATHEMATICAL MODELS; P CODES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RESPONSE FUNCTIONS; SEISMIC EFFECTS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; FUNCTIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS