Seismic assessment of safety-related structures: laboratory testing of the pressure relief duct frame at pickering NPP
Creators
- 1. McMaster Univ., Hamilton, ON (Canada)
- 2. Atomic Energy Control Board, Ottawa, ON (Canada)
Description
The pressure relief duct (PRD) is a Special safety System in the CANDU-PHW multi-unit nuclear power plants (NPP). It is designed to contain and direct the outflow from the reactor building to the pressure suppression and containing systems in the vacuum building. The PRD is a large elevated reinforced concrete box structure of internal width of 6.1 m, height of 7.6 m, and wall thickness of 0.6 m. The PRD is 662 m long and is supported every 22 m by concrete frames of height of 21 m. Typical frame members are 1.8 m in depth and width. A representative elevation of the frame is presented. The section of the PRD under investigation was designed and constructed before the current seismic design codes were in effect. An assessment of the PRD structure when subjected to various levels of ground motion has shown that the frame has a limited seismic withstand capacity. Its seismic performance is dependent on the ductility of the beams and on the ability of the beam-column joint to transfer bending moments and shear forces. The objectives of this study are to provide the data to validate the frame analysis results through laboratory testing of a scaled specimen of the beam-column joint, and to compare the observed response with the response of a beam-column joint when the shear reinforcement is detailed according to current seismic design codes. (author). 3 refs., 10 figs
Additional details
Publishing Information
- Publisher
- Editora de Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-351-6
- Imprint Title
- Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 3
- Imprint Pagination
- 647 p.
- Journal Page Range
- p. 223-228.
Conference
- Title
- 13. International Conference on Structural Mechanics in Reactor Technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 27053978
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S58: GEOSCIENCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUILDINGS; CANDU TYPE REACTORS; DYNAMIC LOADS; EARTHQUAKES; FOUNDATIONS; GROUND MOTION; MECHANICAL STRUCTURES; MECHANICAL VIBRATIONS; NUCLEAR POWER PLANTS; PICKERING SITE; PRESSURE TUBES; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTORS; SEISMIC EFFECTS; SEISMIC EVENTS; SEISMOLOGY; SITE SELECTION; SOIL-STRUCTURE INTERACTIONS
- Descriptors DEC
- COOLING SYSTEMS; HEAVY WATER MODERATED REACTORS; MOTION; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR SITES; SAFETY; SUPPORTS; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.