G. Smith1, E. Schlangen2, P.E.J. Flewitt3, A.G. Crocker4, A. Hodgkins5
CMC-Computers, Materials & Continua, Vol.51, No.3, pp. 163-185, 2016, DOI:10.3970/cmc.2016.051.163
Abstract Two linked models have been developed to explore the relationship between the amount of porosity arising in service from both radiolytic oxidation and fast neutron damage that influences both the strength and the force-displacement (load-displacement) behaviour and crack propagation in pile grade A graphite used as a nuclear reactor moderator material. Firstly models of the microstructure of the porous graphite for both unirradiated and irradiated graphite are created. These form the input for the second stage, simulating fracture in lattice-type finite element models, which predicts force (load)-displacement and crack propagation paths. Microstructures comprising aligned filler More >
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