A model to describe the fracture of porous polygranular graphite subject to neutron damage and radiolytic oxidation

Journal article (2016)

Authors

G Smith University of Bristol
E. Schlangen Materials and Environment - CEG
P.E.J. Flewitt University of Bristol
A. G. Crocker University of Surrey
Research Group
Coastal Engineering (CEG) (TU Delft)
Fracture strength Crack path FE lattice model Modelling microstructure Reactor core graphite
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Published Date

2016

Language

English

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Faculty

Civil Engineering & Geosciences

Department

Hydraulic Engineering

Research Group

Coastal Engineering

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 particles, typical of needle coke, in a porous matrix have been explored. The purpose was to isolate the contributions of filler particles and porosity to fracture strength and crack paths and consider their implications for the overall failure of reactor core graphite.