A numerical study of internal brick stresses in AGR moderator bricks
- 1. Health and Safety Laboratory, Harpur Hill, Buxton, Derbyshire SK17 9JN (United Kingdom)
- 2. NGRG, School of MACE, University of Manchester, Manchester M13 9PL (United Kingdom)
Description
Highlights: • A methodology for studying the uncertainty in internal brick stresses was developed. • A computationally efficient methodology based upon a surrogate model was utilised. • Uncertainty in material relationships, particularly those related to secondary creep was the dominant source of uncertainty. - Abstract: Physically-based models are often used to model changes in geometry and the associated stress fields of graphite moderator bricks within an advanced gas-cooled reactor (AGR). These models require inputs that describe the loading conditions, and coded relationships describing the behaviour of material properties. Material relationships are primarily based upon data obtained from inspection campaigns at operating reactors. However, the data from trepanning campaigns do not provide information on some of the key relationships and parameters that affect the internal stresses generated within the moderator bricks. In this work we explore how uncertain material property relationships affect the internal brick stresses in early- and late-life. We describe two computer experiments designed to study early- and late-life brick stresses and report the results from global sensitivity analysis of the models. The work makes use of an emulator, a surrogate for the FE model, in order to make the sensitivity analyses computationally feasible.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.09.007Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.09.007;
- PII
- S0029-5493(16)30325-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 309
- Journal Page Range
- p. 277-293
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062438
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- AGR TYPE REACTORS; BRICKS; COMPUTERS; CREEP; EXPERIMENT DESIGN; GRAPHITE; NUMERICAL ANALYSIS; RESIDUAL STRESSES; SENSITIVITY ANALYSIS
- Descriptors DEC
- BUILDING MATERIALS; CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; MATHEMATICS; MECHANICAL PROPERTIES; MINERALS; NONMETALS; REACTORS; STRESSES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.