Assessment of degradation and aging of nuclear power plants concrete structures
Creators
- 1. Oak Ridge National laboratory - ORNL, 1 Bethel Valley Rd, Oak Ridge, TN (United States)
- 2. Nuclear Regulatory Commission, Washington, DC 20555-0001 (United States)
- 3. EPRI, Charlotte, NC 28262 (United States)
- 4. ANATECH-SIA, 5425 Oberlin Drive, San Diego, CA-92121 (United States)
- 5. University of Colorado, ECOT 441, UCB 428, Boulder, CO 80309-0428 (United States)
- 6. Electric Power Research Institute, 1300 W. William T. Harris Blvd, Charlotte, NC 28262 (United States)
Description
This paper summarizes the results of an expert-panel assessment of ageing degradation modes and mechanisms of concrete structures in NPPs, where, based on specific operating environments, degradation is likely to occur, or may have occurred; to define relevant aging and degradation modes and mechanisms; and to perform systematic assessment of the effects of these age-related degradation mechanisms on the future life of those materials and structures. The following 7 degradation modes and mechanisms have been identified as having the greatest potential impact on the ability of concrete structures to fulfill their safety related functions during long-term NPP operation. 1) Corrosion of conventional reinforcement is difficult to assess because of inaccessibility to inspection; 2) Creep of pre-stressed concrete containments continuously affects the internal stress state and adds to tendon relaxation and gradual loss of prestress; 3) Irradiation of concrete lacks sufficient data to for a clear evaluation of its effects on long-term operations; 4) Alkali-silica reaction potential consequences on the structural integrity of the containment; 5) Fracture/cracking, which is a well understood behavior characteristic of concrete structures and is accounted for in structural design, plays a unique role in post-tensioned containments during de-tensioning and re-tensioning operations which may be undertaken as part of life extension retrofit work, resulting in delamination, and may evolve with time as a creep-cracking interaction mechanism; 6) Boric acid attack of concrete in the spent fuel pool involves knowledge gaps related to the kinetics and the extent of the attack (role of the concrete mix design); 7) Corrosion of the inaccessible side of the spent fuel pool and containment liners and the stress corrosion cracking of the tendons are important degradation modes due to the absence of in-service inspection. The potential impact of these mechanisms may be mitigated by improving the overall level of knowledge about the identified degradation modes in order to better predict and mitigate possible consequences; and/or, by identifying and implementing acceptable mitigation strategies (replacement, treatments, etc.). (authors)
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 28 p.
- Report number
- INIS-FR--15-0431
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
- 46081726
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CORROSION; CRACKS; CREEP; PRESTRESSED CONCRETE
- Descriptors DEC
- BUILDING MATERIALS; CHEMICAL REACTIONS; COMPOSITE MATERIALS; CONCRETES; MATERIALS; MECHANICAL PROPERTIES
Optional Information
- Notes
- 2 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/