The seismic assessment of radially keyed graphite moderator cores
Creators
- 1. Nuclear Electric plc, Berkeley (United Kingdom). Berkeley Technology Centre
Description
The modelling of AGR and Magnox cores has to deal with the very large number of components that make up the core, and the non-linear response due to the clearances in the keying system. This paper examines the conditions under which it is permissible to linearise the response. By comparing the results of discrete and continuum models of the core, the paper also shows that the number of components in the core is sufficiently large that the core can be approximated satisfactorily by an anisotropic solid material. The material has unusual properties, but these can be handled within the standard framework for the description of the elastic properties of an anisotropic solid. This description of the core by an equivalent solid material can readily be incorporated into finite element models of the reactor internal structure. Such models have been set up for both AGR and Magnox reactors. The models are being used to assess the seismic response of these reactors. (author). 5 refs, 6 figs
Files
28008813.pdf
Files
(226.8 kB)
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Additional details
Publishing Information
- Imprint Title
- Graphite moderator lifecycle behaviour. Proceedings of a specialists meeting
- Imprint Pagination
- 367 p.
- Journal Page Range
- p. 151-159.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--901
Conference
- Title
- Specialists meeting on graphite moderator lifecycle behaviour.
- Dates
- 24-27 Sep 1995.
- Place
- Bath (United Kingdom).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28008813
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGR TYPE REACTORS; ANISOTROPY; FINITE ELEMENT METHOD; MAGNOX TYPE REACTORS; REACTOR CORES; SEISMIC EFFECTS; SIMULATION
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; NATURAL URANIUM REACTORS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTORS