Congratulations to Dr. Zeinab Alsmadi, nuclear engineering postdoctoral scholar, who presented her research work on “Mechanical and shielding properties of alloy 709 advanced austenitic stainless steel” at the 2021 NC State University Postdoctoral Research Symposium (PRS). After 800⁺ playlist views, voting from 50⁺ attendees and guests, and deliberation by the PRS Planning Committee, they announced five category winners. Zeinab’s virtual presentation won in the “most engaging video presentation” category. Collaborators included Drs. Mohamed Bourham and K.L. Murty and her abstract examined the following –

With increasing demand on energy these days and for the near future, there should be a continuous development of lifetime and safety of the energy systems to satisfy the future needs of energy. Generation IV (GEN IV) nuclear reactors are designed to be safer, more reliable, more efficient and have longer lifetimes (60-80 years) than current nuclear reactors. The only possible mid-term available fast reactor is Sodium-Cooled Fast Reactor (SFR) with acceleration in research and development along with reduction in economic competitiveness. Therefore, the structural materials of SFRs should have excellent mechanical properties that can withstand the harsh operating environments such as high temperatures, high radiation doses and corrosive environments. On the other hand, as spent fuel pools reach their capacity limit of stored fuel assemblies in nuclear power plants, the fuel assemblies are removed and stored in storage pools to cool down, following which they are placed in dry casks storage systems in which they emit high levels of radiation. Thus, good shielding, safety, heat removal and physical protection are required by designing the dry casks canisters with materials that can provide such safety requirements. Alloy 709 (Fe-25(wt%)Ni-20Cr), an advanced austenitic stainless steel is developed for high-temperature applications due to its adequate mechanical and shielding properties such as corrosion-resistance, high strength, thermal stability, good creep-fatigue properties, high linear and mass attenuation coefficient, and low exposure rates against gamma-rays. Therefore, the preliminary data nominate Alloy 709 as an excellent structural material for SFR and spent fuel dry casks canisters.

Click here to view the presentation.

The annual Postdoctoral Research Symposium is a conference-style event hosted by the Office of Postdoctoral Affairs (OPA) and the Postdoctoral Research Symposium Committee. The Symposium features the innovative research being conducted by postdoctoral scholars at NC State and around the Triangle. It is a great opportunity to foster collaboration within the Research Triangle Park community. The Postdoc Research Symposium is a free event and open to all interested parties.