Overview
Education/Academic qualification
Eng-Nuclear, Doctorate Degree
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Projects
- 1 Active
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Development of a Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation
Motta, A. A. (PI), Brown, N. R. (CoPI), Chen, L.-Q.L.-Q. (CoPI), Koss, D. D. (CoPI), Kunz, R. R. (CoPI), Tonks, M. R. (CoPI), Zikry, M. A. (CoPI), Downar, T. (CoPI), Manera, A. (CoPI), Petrov, V. (CoPI), Seker, V. (CoPI), Wirth, B. D. (CoPI), Pastore, G. (CoPI), Terrani, K. A. (CoPI), Cinbiz, N. (CoPI), Tomé, C. C. (CoPI), Karoutas, Z. (CoPI), Mitchell, D. D. (CoPI), Romero, J. J. (CoPI), Daymond, M. M. (CoPI), Preuss, M. M. (CoPI) & Mader, E. E. (CoPI)
Nuclear Energy University Program
01/1/17 → …
Project: Research
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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 -
Formation of carbon homonuclear bonds in β-SiC under neutron irradiation at various temperatures and neutron doses
Koyanagi, T., Cinbiz, M. N. & Katoh, Y., Jun 15 2026, In: Acta Materialia. 312, 122252.Research output: Contribution to journal › Article › peer-review
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Benchmark Mechanical Test Results of Westinghouse Zirconium Cladding and Irradiated Testing Readiness
Garrison, B., Pan, G., Blount, E., Sitterson, B., Kendall, J., Harp, J., Cinbiz, M. N., Capps, N., DeAbreu, A., Feldsien, E., Black, C. & Partezana, J. M., 2025, Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. American Nuclear Society, p. 532-541 10 p. (Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Considerations for Thermal Annealing of Zr-Alloy Cladding During Dry Storage
Cantonwine, P., Karkkainen, R., Montgomery, R., Cinbiz, M. N., Sasikumar, Y., Torres, R., Shimskey, R., Petersen, G., Reed, J., Aumand, M., Porter, I., Mitchell, D., Pan, G., Nair, P., Vitto, S. & Faldowski, J., 2025, Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. American Nuclear Society, p. 84-96 13 p. (Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review