Accelerated Discovery and Qualification of Nuclear Materials for Energy Applications: High Throughput Testing, Advanced Characterization and Property Measurement
Sponsored by: TMS Structural Materials Division, TMS Materials Processing and Manufacturing Division, TMS: Integrated Computational Materials Engineering Committee, TMS: Nuclear Materials Committee, TMS: Additive Manufacturing Committee
Program Organizers: Yongfeng Zhang, University of Wisconsin; Adrien Couet, University of Wisconsin-Madison; Michael Tonks, University of Florida; Jeffery Aguiar, Lockheed Martin; Andrea Jokisaari, Idaho National Laboratory; Karim Ahmed, Texas A&M University
Tuesday 2:00 PM
March 16, 2021
Room: RM 48
Location: TMS2021 Virtual
Session Chair: Janelle Wharry , Purdue University ; Tiankai Yao, Idaho National Laboratory
2:00 PM Invited
A Standards Perspective on Nanomechanical Testing to Accelerate Nuclear Materials Development & Qualification: Janelle Wharry1; Priyam Patki1; George Warren1; Patrick Warren1; J Hall2; 1Purdue University; 2Westinghouse Electric Company, LLC
The objective of this talk is to explore how to effectively bridge length scales in mechanical testing standards, to accelerate nuclear materials qualification. In practice, nuclear materials surveillance and qualification requires adherence to established ASTM standards. Standardized mechanical tests inherently bridge length scales by assessing the embrittlement of a heavy component having dimensions ~meters, using a specimen with dimensions ~cm. Research advancements over the past decade have pushed dimensional limits, such that some elasto-plastic quantities can be ascertained from nanomechanical test specimens ~nano-micrometers. Such nanomechanical tests offer tremendous potential for accelerating nuclear alloy development by testing small material volumes readily accommodated in-reactor. But standardizing nanomechanical tests is a long overlooked challenge with few precedents. This talk will review recent research in bridging the length scales from nano to standardized "bulk" specimens. We will then consider how we can translate research advancements into a standards framework.
2:30 PM
A Rapid Turnaround Approach Studying Helium Effects in Materials: Peter Hosemann1; Andrew Scott1; Sarah Stevenson1; Mehdi Balooch1; 1University of California Berkeley
Helium effects in materials are relevant for fission and fusion applications. Bulk materials damage is considered in fission applications while surface near damage is a result of materials exposure to a fusion environment. Traditionally we perform these studies either in reactor, spallation or ion beam accelerator environments. However, the helium ion beam microscope allows for direct Helium implantation in a surface on a very localized scale. This allows to examine several doses at one single material in the same session greatly accelerating the process. Furthermore, the post irradiation characterization via AFM and nanoindentation generates large number of data on different materials providing swelling and Helium induced hardening information. Selected materials will be investigated using TEM to evaluate the mechanisms. We show data on Cu, V, W, Ti and SiC in this study.
2:50 PM
High-throughput Heavy Ion Irradiation of CrFeMnNi Magnetron-sputtered Combinatorial Thin Film: Calvin Parkin1; Michael Moorehead1; Mohamed Elbakhshwan1; Kumar Sridharan1; Chuan Zhang2; Alan Savan3; Alfred Ludwig3; Adrien Couet1; 1University of Wisconsin Madison; 2Computherm, LLC; 3Ruhr-Universität Bochum
In-core structural materials for sodium fast reactors are expected to demonstrate radiation tolerance up to several hundreds of displacements per atom (dpa) over the operating lifetime. Compositionally complex alloys (CCAs) consisting of four or more principle alloying elements in single-phase solid solution are theorized to resist radiation due to unique energy and mass transport properties. Due to the vast range of the CCA compositional space, rapid screening of compositions for nuclear reactors must adopt high-throughput experimental techniques to generate libraries of data to link trends in resistance to irradiation with composition. 4” diameter thin films, compositionally graded in CrFeMnNi, have been fabricated by magnetron co-sputtering and irradiated to 5 dpa using an automated stage. Libraries were characterized before and after irradiation using XRD, nano-indentation, four-point probe, profilometry, and for select compositions, TEM. These high-throughput results are discussed alongside the limitations of using thin films in irradiation experiments.
3:10 PM
Accelerated Study of Thermal and Irradiation Creep in Fe-based Multi-principal Element Alloys: Marcus Parry1; Colin Judge2; Cheng Sun2; Wen Jiang2; Boopathy Kombaiah2; Gary Was3; Jeffery Aguiar2; Taylor Sparks1; 1University of Utah; 2Idaho National Laboratory; 3University of Michigan
The development of advanced structural materials is key to the implementation of advanced nuclear reactor design concepts, as well as to the life-extension of light-water reactors. Central to the development of new structural material classes is the evaluation of thermal and irradiation creep properties. Traditionally, these properties are measured using bulk specimens held at temperature under static loads for long periods of time. However, recent advances in thermal and mechanical testing creates an opportunity for the accelerated assessment of small-scale specimens. Utilizing accelerator technologies, combined thermal, irradiation, and mechanical testing is performed on small-scale specimens to efficiently study degradation mechanisms and creep properties. Specifically, four Co-free Fe-based multi-principal element alloys (MPEAs), with potentially desirable thermal and mechanical properties for structural applications in nuclear environments, are evaluated. Results are related to alloy chemistry, microstructure, and irradiation damage.
3:30 PM
High-temperature, High-throughput Ion Irradiation Enabled by Additive Technologies: Michael Moorehead1; Calvin Parkin1; Phalgun Nelaturu1; Michael Niezgoda1; Mohamed Elbakhshwan1; Kumar Sridharan1; Dan Thoma1; Adrien Couet1; 1University of Wisconsin - Madison
Despite recent progress developing more corrosion-resistant, radiation-resistant, and accident-tolerant materials, most next-generation reactors are still designed with materials from the 20th century due to the resource-intensive process of developing and qualifying new materials. The time and resource demand of alloy development increases with the number of alloys examined, further challenging the exploration of broad composition ranges, such as those occupied by compositionally complex alloys (CCAs). To accelerate both the synthesis, irradiation, and characterization of novel alloy compositions for nuclear applications, additive manufacturing has been employed to print bulk arrays of Cr-Fe-Mn-Ni compositions which can be processed and tested in a high-throughput manner. To perform high-temperature ion irradiations, a unique infrared laser heating system combined with an additively manufactured, water-cooled stage has been developed to uniformly cool entire compositional arrays while single coupons are heated. Discussion will include alloy synthesis, development of high-throughput capabilities, and ion irradiation results.
3:50 PM
In-situ TEM Heating Chip Experiments to Study Thermal Behavior of U-Zr Metallic Fuel: Tiankai Yao1; Fei Teng1; Daniel Murray1; JIan Gan1; Michael Benson1; Lingfeng He1; 1Idaho National Laboratory
U-Zr based metallic fuel is being investigated as a candidate for the sodium-cooled fast reactor. Transmission electron microscopy (TEM) based characterization is being increasingly used to reveal microstructural features at the nanometer scale and to provide novel insights to correlate these microstructural features with bulk properties for the U-Zr system. The value of the TEM method is being increased by using an in-situ TEM heating chip to observe the microstructural evolution in U-Zr alloys during the heat treatment. This is in contrast to analyzing a static sample after a furnace anneal that shows the results of the anneal, but not the process. A series of U-Zr alloys have been investigated using the in-situ heating chip, including U-10Zr, U-20Zr, U-50Zr, and U-80Zr. Unprecedented phenomena have been observed in these alloys and will be discussed along with implications for the U-Zr based metallic fuel system.
4:10 PM
Multiscale Characterization of Defects in Ion Irradiated Ceramics for Validation of Atomistic Models: Marat Khafizov1; Vinay Chauhan1; Lingfeng He2; Janne Pakarinen3; David Hurley2; 1Ohio State University; 2Idaho National Laboratory; 3Studsvik
Validation of the first principles models for microstructure evolution under irradiation has been hindered by availability of table-top experimental methods suitable for defect characterization at the atomic level. We discuss extensive characterization of defects in proton irradiated ceria. Ceria has a fluorite crystalline structure and is used a model oxide fuel system. Irradiations at 600 C to a dose of 0.1 dpa at different rates is found to provide optimal conditions for producing both point and extended defects. Electron microscopy is used to characterize dislocation loops, while optical and Raman spectroscopies are used to characterize point defects. Quantitative analysis of dislocation loops using rate equations provides means for measuring mobility of defects. Raman and optical spectroscopies probe vibrational and electronic properties of defects all tightly coupled to atomic structure. Presented methods offer an attractive solution for validation of atomistic models critical for development of material performance codes with predictive capability.
4:30 PM
In-situ Thermal Conductivity Measurement of SiC Composite: Di Chen1; Wei-Kan Chu1; Piyush Sabharwall2; 1University of Houston; 2Idaho National Laboratory
The SiC composite has attracted extensive attention as a potential candidate material in the next generation nuclear energy applications, due to its excellent stability under long term irradiation. In order to achieve better irradiation resistance, it is necessary to validate SiC composite's performance under irradiation and prototypic conditions. The study focuses on a unique in-situ thermal property measurement technique, coupling with ion irradiation, laser beam, and infrared detection, to investigate the influence of radiation and other fission gases on SiC composite. By means of the in-situ thermal conductivity measurement system, the SiC composite specimens are irradiated by C, Si, He and Xe ions, respectively, with in-situ thermal measurement to study influence from irradiation, also fission gases detention. The results are discussed, and details on the in-situ measurement technique are provided, which can serve as a platform for rapid irradiation testing for determining the thermal properties of materials.