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In Situ Micropillar Compression of Irradiated HT9

For generation IV reactors, a Ferritic/Martensitic steel known as HT9 is a strong candidate for cladding and structural component materials [1]. Being so close to the nuclear core, cladding and other structural materials will need to be able to withstand the harsh temperature and radiation field. Specifically, the mechanical properties of a candidate material need to be tested at various doses of irradiation to ensure the safety of the reactor and containment of radioactive fuel. Irradiation through neutron damage can often be time consuming and can result in radioactive material through activation [2]. Ion irradiation can be used to overcome the problems associated with neutron irradiation and can easily be controlled in terms of energy and flux via magnetic fields [2]; however, ion irradiation falls short in terms of penetration depth which is limited [2]. The limited depth of ions for irradiation makes bulk mechanical testing impracticable. Hardness test can be used to obtain some mechanical properties of irradiated materials, but does not have the ability to view the response of the irradiated microstructure under mechanical load [3]. In situ micropillar compression tests can be utilized to study the evolution of the microstructure during mechanical testing. The purpose of the study was to conduct micropillar compression tests on ion irradiated HT9 under Transmission Electron Microscopy (TEM) observation.