NSUF 18-1380: TEM and APT Characterization of Ion-Irradiated High-Entropy Alloys for Sodium-Cooled Fast Reactors

Technical Abstract

Methods to be Employed: To investigate the enhanced irradiation resistance of high-entropy alloys (HEAs), two alloy compositions have been selected (Cr0.66FeMnNi and NbTaTiV) and samples have been produced through arc melting. The proposed experiment uses samples of each alloy which have been ion irradiated at the PI’s home facility using both protons and Fe2+ ions to reproduce irradiation damage levels at several points in an SFR core lifetime (0.1, 0.5, 10, 100, 200 dpa) at two temperatures, 100 °C and 700 °C. As part of the RTE, the samples would be sent to the Materials and Characterization Suite at CAES. There, transmission electron microscopy (TEM) and atom-probe tomography (APT) samples will be prepared by the PI using the FEI QUANTA 3D FEG dual beam focused ion beam (FIB). TEM samples will then be examined using the FEI Technai TF-30-FEG STwin scanning transmission electron microscope to measure the size distribution and density of radiation-induced voids in the irradiated HEAs. To assess the presence and extent of chemical ordering following irradiation, APT samples will be examined using the Cameca 4000X HR local electrode atom probe (LEAP). The INL senior staff scientist collaborating with for work will assist the PI in data acquisition using the TEM and LEAP as well as interpreting data collected.

Potential Impact: Current alloy development for nuclear applications relies primarily on microstructure optimization (e.g. cold-working, nano-sized grains, etc.) to produce a higher density of sinks for radiation-induced defects to be eliminated at. In contrast, rather than increased sink densities, HEAs are expected to have lower defect mobility which would result in increased defect recombination locally with respect to the initial damage cascade. Understanding the mechanisms behind and the extent of the enhanced irradiation resistance of HEAs may be transformative in the way alloys are developed for nuclear applications.

Expected Period of Performance: A total of twelve (12) days of machine time is expected to be needed for this experiment, to be executed at the Materials and Characterization Suite in CAES. Below is breakdown of the anticipated machine time usage:

FEI QUANTA 3D FEG dual beam focused ion beam [FIB]: Six (6) days FEI Technai TF-30-FEG STwin scanning transmission electron microscope [TEM]: Three (3) days Cameca 4000X HR local electrode atom probe (LEAP) [APT]: Three (3) days

Anticipated Scientific Outcome: At the conclusion of this RTE, several TEM and APT samples will be produced and analyzed. TEM samples will be used to study the size distribution and number density of radiation-voids, as well as the formation of second-phase precipitates, and any macroscopic chemical repartitioning as a result of ion irradiation. Analysis of the APT from samples originating within the bulk of the HEA samples (i.e. away from any grain boundaries or second-phase precipitates) should yield insight into the presence and extent of any chemical ordering caused by ion irradiation. Together, these complimentary characterization techniques should elucidate the mechanisms behind the enhanced irradiation resistance of HEAs for nuclear applications, and more specifically, next-generation SFR cladding.

מידע נוסף

שדה ערך
Awarded Institution University of Wisconsin
Embargo End Date 2019-12-30
Facility Tech Lead Alina Montrose, Mukesh Bachhav
NSUF Call FY 2018 RTE 2nd Call
PI Michael Moorehead
Project Member Dr. Lingfeng He, Associate Professor - North Carolina State University (https://orcid.org/0000-0003-2763-1462)
Project Member Professor Adrien Couet, Assistant Professor - University of Wisconsin (https://orcid.org/0000-0002-7330-5150)
Project Member Dr. Michael Moorehead, Russell L. Heath Distinguished Postdoc - Idaho National Laboratory (https://orcid.org/0000-0001-8216-5244)
Project Notes Awarded on 05/17/2018
Project Type RTE
Publication Multiscale modeling of fission gas bubble evolution in UO2 under nominal operating conditions Brian Wirth NUMAT 2018 2018-10-15 - 2018-10-18
Publication In situ and ex situ heavy ion irradiation of FCC high-entropy alloys at cryogenic and high temperatures Calvin Parkin NuMat 2020 2021-01-26 - 2021-01-29
Publication Ion irradiation effects in face-centered cubic complex concentrated solid solution alloys at high temperature Calvin Parkin ANS Winter Meeting 2020 2020-11-16 - 2020-11-19
Publication In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation Michael Moorehead, Calvin Parkin, Mohamed Elbakhshwan, Jing Hu, Wei-Ying Chen, Meimei Li, Lingfeng He, Kumar Sridharan, Adrien Couet Acta Materialia 198 2020-10-01 https://doi.org/10.1016/j.actamat.2019.01.006
Publication Phase stability, mechanical properties, and ion irradiation effects in face-centered cubic CrFeMnNi compositionally complex solid-solution alloys at high temperatures Calvin Parkin Journal of Nuclear Materials 565 2022-04-17 https://doi.org/10.1016/j.jnucmat.2022.153733
Publication Predicting neutron damage using TEM with in situ ion irradiation and computer modeling Brian Wirth, Donghua Xu, Meimei Li Journal of Nuclear Materials 498 2017-11-12 https://www.sciencedirect.com/science/article/pii/S0022311517308358
RTE Number 1380