Projects per year
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Researcher collaborations from the last five years
Profiles
Projects
- 3 Active
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Improving Reliability of Novel TRISO Fuel Forms for Advanced Reactors via Multiscale, High-Throughput Characterization and Modeling
Munro, T. T. (PI), Johnson, O. O. (CoPI), Gerczak, T. (CoPI) & Brown, D. D. (CoPI)
Nuclear Energy University Program
01/1/23 → …
Project: Research
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Statistical modeling of the effect of microstructural heterogeneity on the irradiation behavior of TRISO fuel buffer layer
Zhang, Y. Y. (PI), Thevamaran, R. (CoPI), Sridharan, K. K. (CoPI), Ahmed, K. K. (CoPI), Gerczak, T. (CoPI), Jiang, W. W. (CoPI), Labrier, D. D. (CoPI) & Gougar, M. L. D. M. L. D. (CoPI)
Nuclear Energy University Program
01/1/20 → …
Project: Research
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High Power Irradiation Testing of TRISO Fuel Particles with UCO and UO2 Kernels in Miniature Fuel Specimen Capsules in HFIR
Latta, R. (PI), Hackett, M. (CoPI), Collin, B. (CoPI), Brown, N. R. (CoPI), Gerczak, T. (CoPI), Petrie, C. (CoPI), Hunn, J. (CoPI) & Helmreich, G. (CoPI)
Nuclear Energy University Program
01/1/19 → …
Project: Research
Research output
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Influence of temperature, oxygen partial pressure, and microstructure on the high-temperature oxidation behavior of the SiC Layer of TRISO particles
Jalan, V., Bratten, A., Shi, M., Gerczak, T., Zhao, H., Poplawsky, J. D., He, X., Helmreich, G. & Wen, H., Feb 2025, In: Journal of the European Ceramic Society. 45, 2, 116913.Research output: Contribution to journal › Article › peer-review
4 Scopus citations -
Interface stability of ultrasonic additively manufactured Zircaloy-4 during hydrothermal corrosion
Ridley, M., Parker, C., Helmreich, G., Massey, C., Nelson, A. & Pint, B., Jan 2025, In: Journal of Nuclear Materials. 603, 155376.Research output: Contribution to journal › Article › peer-review
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Investigation of UO2 doped with Fe2O3 sintered under a reducing atmosphere
Ulrich, T. L., Spano, T. L., Sadergaski, L., Shields, A. E., Lopez-Honorato, E., Helmreich, G., Manard, B. T., Harp, J. & Nelson, A. T., Mar 2025, In: Journal of Nuclear Materials. 607, 155684.Research output: Contribution to journal › Article › peer-review
1 Scopus citations