OFFER Tomasz Stasiak
Acronym of the project proposal
CreepAlloy
Complete name of the proposal
Evaluation of the irradiation resistance of high-temperature resistance alloys via ion implantation after creep test and prolonged annealing
Abstract
The requirements for materials for the construction of Generation IV nuclear reactors are very high in terms of high-temperature strength and irradiation resistance. Nevertheless, there are many candidate materials for these applications. However, the irradiation resistance is mainly studied by ion implantation of the materials after fabrication. Other factors, such as mechanical loads or high-temperature exposure that affect microstructure during operation in a nuclear reactor are often disregarded as factors modifying irradiation response.
This project aims to fill the gap in understanding the irradiation resistance of materials submitted to operation conditions. Three different alloys will be studied, i.e., Inconel 617, 316L stainless steel, and Fe12Cr5Al oxide dispersion strengthened (ODS) alloys. Self-ion irradiation (Ni or Fe) will be conducted on alloys in as-fabricated conditions or after a creep test, either after prolonged high-temperature annealing. Moreover, the irradiation response of Inconel 617 produced by traditional metallurgy methods will be compared with the irradiation behavior of Inconel 617 prepared by additive manufacturing using directed energy deposition techniques. The ion implantation, which will mimic the neutron irradiation occurring in a nuclear reactor, will be performed with an energy of 5 MeV and a fluence of 5·1015 ion/cm2. Two selected samples will be irradiated with a higher fluence to understand irradiation resistance further. It should be noted that the implantation will be performed at 650 °C, which is close to the actual operating conditions. The ion-implanted layers in studied materials will be later investigated at NCBJ using nanoindentation, GIXRD, and TEM.
Budget 26 250.00 €

