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Researcher collaborations from the last five years
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Compatibility studies of uranium nitride fuel with advanced cladding materials using multimodal diffusion experiments
He, L. F. (PI), Sohn, Y. (CoPI), White, J. T. (CoPI), Massey, C. (CoPI), Adorno Lopes, D. (CoPI), Lahoda, E. J. (CoPI) & Choi, H. (CoPI)
Nuclear Energy University Program
01/1/25 → …
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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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
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 Standardized Analysis Process Using Digital Image Correlation to Calculate In Situ Cladding Strain from Modified Burst Tests for Fuel Performance Code Validation
Espersen, J. I., Cinbiz, M. N., Capps, N. A. & Brown, N. R., 2026, In: Nuclear Science and Engineering. 200, 6, p. 1381-1397 17 p.Research output: Contribution to journal › Article › peer-review
1 Scopus citations -
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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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