Reliability-based assessment of integrity of bonded prestressed concrete containment structures
Description
The main function of a nuclear containment structure is to prevent the leakage of radioactive materials from the reactor in the event of a serious failure in the process system. To maintain a high level of leak integrity, prestressed concrete is widely utilized in containment construction. In bonded prestressing systems, excessive prestressing losses caused by unexpected material deformations and degradation of tendons could result in the loss of leak integrity under an accident. To safeguard against this, the Canadian Standard, CSA N287.7 (1995), recommends periodic inspection and evaluation of prestressing systems of CANDU containments. As bonded tendons are not amenable to direct inspection, the evaluation is based on the testing of a set of beams with features identical to the containment. The paper presents a quantitative reliability-based approach to evaluate the containment integrity in terms of the condition of bonded prestressing systems. The proposed approach utilizes the results of lift-off, destructive, and flexural tests to update the probability distribution of prestressing force, and to revise the calculated reliability against through-wall cracking of containment elements. An acceptable criterion for the results of beam tests is established on the basis of maintaining adequate reliability throughout the service life of the containment. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 176
- Journal Issue
- 3
- Journal Page Range
- p. 247-260.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 29018889
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENDING; CANADIAN ORGANIZATIONS; CANDU TYPE REACTORS; CONTAINMENT BUILDINGS; CRACKS; FISSION PRODUCT RELEASE; INSPECTION; MATERIALS TESTING; PRESTRESSED CONCRETE; REACTOR ACCIDENTS; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SAFETY STANDARDS; SERVICE LIFE
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; BUILDINGS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; DEFORMATION; HEAVY WATER MODERATED REACTORS; LIFETIME; MATERIALS; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; STANDARDS; TESTING; THERMAL REACTORS
Optional Information
- Notes
- 21 refs.