Seismic response of the ACRTM reactor building
Creators
- 1. Atomic Energy of Canada Limited (Canada)
Description
The Advanced CANDU Reactor or the ACR. is developed by Atomic Energy of Canada Limited (AECL) to be the next step in the evolution of the CANDU product line. It is based on the proven CANDU technology and incorporates advanced design technologies. Two standard designs of the ACR are developed: ACR-1000 and ACR-700. The ACR is designed to incorporate the latest advances in design and construction techniques and to be cost competitive while achieving higher safety and performance standards. This paper describes the methodology of the seismic qualification of the ACR reactor buildings. The ACR standard plant is conservatively qualified for a design basis earthquake with peak horizontal ground acceleration of 0.3 g and for a wide range of soil/rock foundation conditions. The input design ground response spectra address current technical issues such as earthquake input motions with high frequency content and near field effects. The structural behavior of the ACR-700 reactor building under the design earthquake is determined using two dynamic models. The dynamic characterizes of the reactor building are established using a stick model and a three-dimensional finite element model. In developing the dynamic models, considerations are given to the details of both the containment and internal structures, and to location and weight of major equipment and systems. The soil-structure-interaction effects are considered in the seismic analysis. The structural responses of the reactor building due to the design basis earthquake are determined and are used for the assessment of the reactor building stability. The seismic responses of the reactor building include displacement and acceleration responses and base shear and overturning moments. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 7-5022-3421-7
- Imprint Title
- Proceedings of 18th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 4896 p.
- Journal Page Range
- p. 3300-3307
Conference
- Title
- 18. international conference on structural mechanics in reactor technology
- Dates
- 7-12 Aug 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43021633
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S58: GEOSCIENCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATION; ATOMIC ENERGY OF CANADA LTD; BUILDINGS; CANDU TYPE REACTORS; CONSTRUCTION; CONTAINMENT BUILDINGS; DESIGN; EARTHQUAKES; FOUNDATIONS; GROUND MOTION; NUCLEAR ENERGY; PEAKS; PERFORMANCE; REACTOR COMPONENTS; ROCKS; SAFETY; SHEAR; SOILS; SOIL-STRUCTURE INTERACTIONS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BUILDINGS; CANADIAN ORGANIZATIONS; CONTAINMENT; ENERGY; HEAVY WATER MODERATED REACTORS; MECHANICAL STRUCTURES; MOTION; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SEISMIC EVENTS; SUPPORTS; THERMAL REACTORS
Optional Information
- Notes
- 20 figs., 2 tabs., 7 refs.