Influence of temperature on strain monitoring of degradation in concrete containment buildings
Creators
- 1. Atomic Energy of Canada Limited - AECL, 1 Plant Road, Chalk River, K0J 1J0, ON (Canada)
Description
Concrete containment buildings (CCBs) are important safety structures in a nuclear power plant (NPP). The CCBs can be made of reinforced and post-tensioned (P-T) concrete. Post-tensioning concrete induces compressive stresses, which have to be overcome for the concrete to crack under tensile loads. However, post-tensioned CCBs may undergo pre-stressing losses as they age, which could affect their performance under accident conditions. CANDU 6 reactor buildings contain grouted post-tensioned tendons as the primary reinforcement. The grouting of the tendons makes direct monitoring of pre-stressing losses via lift-off testing impossible. Therefore, instruments have been installed on an existing reactor building to measure and monitor strains and stresses in the concrete and the deformation of the concrete structure to detect aging degradation and indirectly evaluate the pre-stressing losses. However, the instrumentation readings are affected by temporary volume changes in the concrete caused by the influence of environmental factors, particularly temperature, on concrete. In this work, the focus is on developing an understanding of the effect of temperature on the interpretation of instrumentation data from a reactor building. Vibrating Wire Strain Gauge (VWSG) data has been analysed. The influence of concrete coefficient of thermal expansion and temperature distribution within the reactor building walls, on VWSG data, is discussed based on the analysis of the available instrumentation data and available numerical simulation results. The present study demonstrates that temperature distribution within the containment concrete has a significant impact on the VWSG measurements and the coefficient of thermal expansion of concrete is an important factor in the correction of VWSG data for thermal strain. It is recommended that VWSG data obtained over small temperature variations be considered for interpretation to assess pre-stressing losses. (authors)
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 27 p.
- Report number
- INIS-FR--15-0430
Conference
- Title
- Conference on Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance and Reliability
- Acronym
- Fontevraud 8
- Dates
- 15-18 Sep 2014
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 46081725
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CONTAINMENT BUILDINGS; MONITORING; PRESTRESSED CONCRETE; SIMULATION; STRAIN GAGES; STRAINS; TEMPERATURE DEPENDENCE; THERMAL EXPANSION; VALIDATION
- Descriptors DEC
- BUILDING MATERIALS; BUILDINGS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; EXPANSION; HEAVY WATER MODERATED REACTORS; MATERIALS; MEASURING INSTRUMENTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; TESTING; THERMAL REACTORS
Optional Information
- Notes
- 9 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/