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Medientyp:
E-Artikel
Titel:
Modelling Porosity in Quasi-Brittle Reactor Core Graphite
Beteiligte:
Smith, G.E.;
Flewitt, Peter E.J.;
Hodgkins, A.
Erschienen:
Trans Tech Publications, Ltd., 2013
Erschienen in:Key Engineering Materials
Sprache:
Nicht zu entscheiden
DOI:
10.4028/www.scientific.net/kem.577-578.337
ISSN:
1662-9795
Entstehung:
Anmerkungen:
Beschreibung:
<jats:p>Some designs of nuclear reactors involve a graphite moderator within their core. Different forms of graphite have been adopted in the UK gas-cooled reactors but all have a complex structure of filler particles, matrix and pores. Changes occur in the graphite during service and in particular, porosity increases from that found in the virgin material. As part of a structural assessment, it is important to analyse the effects of this change in porosity. Software has been developed to represent the microstructure of pile grade A (PGA) and Gilsocarbon graphite with a range of porosities, to support finite element determination of material properties. The models are three dimensional geometric and voxel models based on the observed microstructures of these different graphites. Creating a sequence of model specimens with increasing porosities while holding other parameters constant, provides a representative microstructure to test the effect of increasing porosity on mechanical and physical properties.</jats:p>