Ultimate analysis of PWR prestressed concrete containment under long-term prestressing loss
Creators
Description
Highlights: • Analyses are carried out to predict the ultimate capacity of the PWR containment. • Material nonlinearities are all simulated with proper constitutive models. • After the 40 years of service, the prestresses would lose about 19% amount. • Ultimate capacity of the containment is higher than the design pressure by 58%. - Abstract: Numerical analyses are carried out by using the Abaqus finite element program to predict the ultimate pressure capacity and the failure mode of the PWR prestressed concrete containment at Maanshan Nuclear Power Plant, Taiwan, R.O.C. under long term prestressing loss. Material nonlinearity such as concrete cracking, tension stiffening, shear retention, concrete plasticity, yielding of prestressing tendon, yielding of steel reinforcing bar, yielding of liner plate and relaxation of prestressing tendon are all simulated with proper constitutive models. The results of the numerical analysis show that after the 40 years of service, the prestresses in the prestressing tendons would lose about 19% of their initial values. However, under long term prestressing loss, the ultimate pressure capacity of the containment is still higher than the design pressure 482 kPa by 58%.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2015.10.005Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2015.10.005;
- PII
- S0306-4549(15)00484-3;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 87
- Journal Issue
- Part 2
- Journal Page Range
- p. 500-510
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47125046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CAPACITY; CONTAINMENT; CRACKING; FAILURES; FINITE ELEMENT METHOD; MAANSHAN-1 REACTOR; NONLINEAR PROBLEMS; NUCLEAR POWER; NUCLEAR POWER PLANTS; NUMERICAL ANALYSIS; PLASTICITY; PRESTRESSED CONCRETE; REINFORCED MATERIALS; RETENTION; STEELS
- Descriptors DEC
- ALLOYS; BUILDING MATERIALS; CALCULATION METHODS; CARBON ADDITIONS; CHEMICAL REACTIONS; COMPOSITE MATERIALS; CONCRETES; DECOMPOSITION; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATHEMATICAL SOLUTIONS; MATHEMATICS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; PYROLYSIS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.