Inverse identification of tensile and compressive damage properties of graphite material based on a single four-point bending test

Nuclear graphite is a key material in high-temperature gas-cooled reactors (HTGR). The evaluation of its damage evolution is significant for the safety assessment of nuclear graphite structures. However, it is difficult to characterise the damage properties of nuclear graphite using conventional tes...

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Veröffentlicht in:	Journal of nuclear materials 2018-10, Vol.509, p.445-453
Hauptverfasser:	Liu, Guangyan, Wang, Lu, Yi, Yanan, Sun, Libin, Shi, Li, Jiang, Han, Ma, Shaopeng
Format:	Artikel
Sprache:	eng
Schlagworte:	Bend tests Compression Compression tests Computer simulation Damage Damage assessment Damage detection Digital image correlation Digital imaging Evolution Finite element analysis Finite element method Finite element model updating Graphite High temperature gas cooled reactors High temperature gases Inverse method Inverse optimisation algorithm Iterative methods Mechanical properties Model updating Nuclear accidents & safety Nuclear engineering Nuclear graphite Nuclear reactors Nuclear safety Parameter identification Stress-strain curves Structural damage Tension Tension tests
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