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Dive into the research topics where Advanced Fuel Fabrication and Instrument is active. These topic labels come from the works of this organization's members. Together they form a unique fingerprint.
Researcher collaborations from the last five years
Based on publications and projects (not datasets). Dive into details by clicking on the dots or
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Evolution of Heterogeneous 316LSS Microstructures Under Neutron Irradiation, Nuclear Science User Facilities
Kumari, G. (PI), Lach, T. (CoPI), Taller, S. (CoPI) & Massey, C. (CoPI)
01/1/24 → …
Project: Research
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The Role of Dislocation Cell Walls on Cavity Nucleation in Additively Manufactured 316H Steel, Nuclear Science User Facilities
Taller, S. (PI), Massey, C. (CoPI), Zinkle, J. S. (CoPI), Lenertz, M. (CoPI) & Sun, K. (CoPI)
01/1/24 → …
Project: Research
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Co-Location of Solute Clusters and Dislocations in Additively Manufactured 316L Stainless Steels, Nuclear Science User Facilities
Taller, S. (CoPI), Lach, T. (PI) & Massey, C. (CoPI)
01/1/24 → …
Project: Research
Research output
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A model to assess Zircaloy’s mechanical property changes following a transient beyond critical heat flux
Capps, N., Ridley, M., Bell, S., Beale, J., Schrire, D., Phillippe, A., Sarikaya, B., Sakamoto, K. & Cinbiz, N., Jan 2026, In: Nuclear Engineering and Design. 446, 114563.Research output: Contribution to journal › Article › peer-review
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A strategy for automated core design to increase economic viability and minimize fuel fragmentation, relocation, and dispersal susceptibility in high-burnup cores
Gorton, J. P., Gurecky, W. L., Kropaczek, D. J. & Capps, N. A., Jan 2026, In: Nuclear Engineering and Design. 446, 114544.Research output: Contribution to journal › Article › peer-review
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Mechanical properties, strain hardening, and fracture behavior of ultrasonic additively manufactured Zircaloy-4 after low-temperature neutron irradiation
Massey, C. P., Taller, S., Gussev, M., Smith, K., Havrilak, C. & Nelson, A., Jan 2026, In: Journal of Nuclear Materials. 619, 156277.Research output: Contribution to journal › Article › peer-review
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Improving the Nuclear Materials Development Cycle with High Throughput Microscopy and Machine Learning
Taller, S. (Invited speaker)
Jun 2023Activity: Talk or presentation › Oral presentation
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Examining Microstructural Effects on Tensile Properties in Irradiated Inconel 718 Using Miniaturized Tensile Specimens
Taller, S. (Invited speaker) & Massey, C. (Invited speaker)
Mar 2023Activity: Talk or presentation › Oral presentation
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Improving the Nuclear Materials Development Cycle with High Throughput Microscopy and Machine Learning
Taller, S. (Participant)
Aug 2022Activity: Other