Inelastic and fracture behaviour of nuclear graphite

• Nuclear graphite grades IG-110, NBG-18 and PCEA were investigated. • Uniaxial compression and splitting tensile tests were performed. • Fine-grained IG-110 graphite has the optimal combination of strength and ductility. • FE simulations using the concrete damaged plasticity (CDP) material model were used. • The CDP model can capture graphite's inelastic and fracture behaviour. Understanding nuclear graphite's inelastic and fracture behaviour is essential for current and future reactor technologies using graphite-based engineering components. This study compares the behaviour of three nuclear graphite grades, fine-grained IG-110, coarse-grained NBG-18 and medium-grained PCEA, subjected to the uniaxial compression (UC) and the splitting tensile (ST) tests. It was found that the IG-110 graphite has a more favourable combination of ultimate strength and ductility when compared to the NBG-18 and PCEA grades containing large pores acting as strain concentrators. The formation of shear cracks was the primary failure mode under compression, while the formation of a main tension crack in the middle of the specimen was the primary failure mode during the ST test. The inelastic and fracture response was modelled using finite element simulations employing the concrete damaged plasticity (CDP) material model with the dilation angle parameter value selected by two different optimisation processes; a decoupled optimisation was run on the UC and ST models separately, and a coupled optimisation was performed on the UC and ST models running simultaneously. The best predictions were obtained when the value from the coupled optimisation was used. The results showed that the CDP model accurately describes the inelastic behaviour and peak force of all graphite grades and could also capture the failure modes observed experimentally in both UC and ST tests. In particular, the numerical model could capture the crack initiation and propagation path observed in the ST test reasonably well for the IG-110 and PCEA graphite grades.

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Publication Details

Journal
International Journal of Mechanical Sciences
Published
2025-05-01
DOI
https://doi.org/10.1016/j.ijmecsci.2025.110339
Citations
2
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
Field-Weighted Citation Impact
1.04

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article

Inelastic and fracture behaviour of nuclear graphite

K. Irman, William E Windes, T.J. Marrow, Jamie J. Kruzic et al.
2 citations
International Journal of Mechanical Sciences
Graphite, nuclear technology, radiation studies
1.04
article

Inelastic and fracture behaviour of nuclear graphite

K. Irman, William E Windes, T.J. Marrow, Jamie J. Kruzic, E.A. Flores‐Johnson, Ondrej Muránsky
article en
2 citations

Abstract

• Nuclear graphite grades IG-110, NBG-18 and PCEA were investigated. • Uniaxial compression and splitting tensile tests were performed. • Fine-grained IG-110 graphite has the optimal combination of strength and ductility. • FE simulations using the concrete damaged plasticity (CDP) material model were used. • The CDP model can capture graphite's inelastic and fracture behaviour. Understanding nuclear graphite's inelastic and fracture behaviour is essential for current and future reactor technologies using graphite-based engineering components. This study compares the behaviour of three nuclear graphite grades, fine-grained IG-110, coarse-grained NBG-18 and medium-grained PCEA, subjected to the uniaxial compression (UC) and the splitting tensile (ST) tests. It was found that the IG-110 graphite has a more favourable combination of ultimate strength and ductility when compared to the NBG-18 and PCEA grades containing large pores acting as strain concentrators. The formation of shear cracks was the primary failure mode under compression, while the formation of a main tension crack in the middle of the specimen was the primary failure mode during the ST test. The inelastic and fracture response was modelled using finite element simulations employing the concrete damaged plasticity (CDP) material model with the dilation angle parameter value selected by two different optimisation processes; a decoupled optimisation was run on the UC and ST models separately, and a coupled optimisation was performed on the UC and ST models running simultaneously. The best predictions were obtained when the value from the coupled optimisation was used. The results showed that the CDP model accurately describes the inelastic behaviour and peak force of all graphite grades and could also capture the failure modes observed experimentally in both UC and ST tests. In particular, the numerical model could capture the crack initiation and propagation path observed in the ST test reasonably well for the IG-110 and PCEA graphite grades.

International Journal of Mechanical SciencesVol. 296
Australian Nuclear Science and Technology Organisation (AU), Idaho National Laboratory (US), UNSW Sydney (AU), University of Oxford (GB)
Australian Institute of Nuclear Science and Engineering, Universiteit Stellenbosch
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Openalex Percentile: Top 26%
Graphite, nuclear technology, radiation studies
1.04
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