[Seminar] Building Future Faculty Departmental Experience - Department of Nuclear Engineering [Seminar] Building Future Faculty Departmental Experience - Department of Nuclear Engineering

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[Seminar] Building Future Faculty Departmental Experience

March 31, 2022 @ 4:00 pm - 5:00 pm

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Dr. Zeinab Alsmadi
Postdoctoral Research Scholar
Department of Nuclear Engineering
North Carolina State University

 

Mechanical and Shielding Properties of the Alloy 709 Advanced Austenitic Stainless Steel: Application for Nuclear Energy Systems

Abstract

With increasing demand on energy these days and for the near future, there should be a continuous development of the lifetime and safety of the energy systems to satisfy the future needs of energy. Generation IV nuclear reactors are designed to be safer, more reliable, more efficient and have longer lifetimes than current nuclear reactors and therefore, their structural materials 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, the structural materials of spent nuclear fuel storage systems must exhibit good shielding, safety, heat removal and physical protection, as spent fuel can emit high-levels of irradiation in which impose great risk to the environment and personnel. The Alloy 709 advanced austenitic stainless steel is derived from NF709 (Fe-20Cr-25Ni), which is a commercial heat- and corrosion- resistant austenitic stainless steel developed by Nippon Steel Corporation in Japan for boiler tubing applications. Preliminary data revealed that the Alloy 709 is an excellent high-performance candidate as a structural material for high-temperature nuclear reactors like Sodium-Cooled Fast Reactors (SFRs) and spent fuel dry casks as compared to other austenitic stainless steels, due to its adequate mechanical and shielding properties such as creep-fatigue properties, high linear and mass attenuation coefficients and low exposure rates against gamma radiation.

Biography

Dr. Alsmadi received her B.Sc. in Nuclear Engineering from Jordan University of Science and Technology in 2016, MMSE in Materials Science and Engineering from North Carolina State University in 2020 and Ph.D. in Nuclear Engineering from North Carolina State University in 2020. Her research areas of interest involve nuclear material, radiation shielding and nuclear waste management. Her Ph.D. research focused on understanding the relationship between microstructure, processing, mechanical properties and functionality of materials for developing the structural materials of future nuclear energy systems. Her current research as a Postdoctoral Research Scholar focuses on investigating the shielding and corrosion properties of the inner canister material and canister coating of the spent nuclear fuel waste storages such as dry casks, to enhance the shielding efficiency and corrosion resistance of spent nuclear fuel storage systems.

 

Amanda Bachmann
PhD Candidate
Nuclear, Plasma & Radiological Engineering
University of Illinois at Urbana-Champaign

 

Impacts of HALEU on the Nuclear Fuel Cycle

Abstract

Many new advanced reactor designs will require High-Assay Low Enriched Uranium (HALEU) for fuel, which will allow for longer cycle times and higher burnups. However, there is no commercial supplier of HALEU in the US right now, and there is an expected need for HALEU by the end of the decade. The need for HALEU will depend on a number of variables: the type of advanced reactor(s) deployed, the timeline on which they are deployed, the energy demand of the advanced reactor(s), and the fuel cycle option used. This work looks at the transition from the current fleet of Light Water Reactors to HALEU-fueled advanced reactors to understand the material requirements of the transition. The material requirements of interest include the number of reactors that are deployed, the mass of uranium supplied to reactors for fuel, and the Separative Work Units required to enrich the uranium.

Biography

Amanda Bachmann is an NEUP Fellow in the Advanced Reactors and Fuel Cycles group at the University of Illinois Urbana-Champaign. She is currently pursuing her PhD in Nuclear, Plasma, and Radiological Engineering. Her research focuses on modeling and simulation of the nuclear fuel cycle and the transitions between different fuel cycle options. Amanda is an active member of U.S Women in Nuclear and the American Nuclear Society, currently serving as a Co-Chair for the 2022 ANS Student Conference and the Student Director. Amanda holds a BS (2019) and an MS (2020) in Nuclear Engineering from the University of Tennessee, Knoxville.

 

Thursday, March 31. 2022
4:00 pm seminar

Hybrid Option  (Speakers are in person)

zoom (link upon request)
or
Room 1202 Burlington Labs

Details

Date:
March 31, 2022
Time:
4:00 pm - 5:00 pm
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