Selected Journal Papers  

Journal of Nuclear Materials 593 (2024), "Experimental emulation of 10B(n, α)7Li reaction-induced microstructural evolution of Al-B4C neutron absorber used in the dry storage of spent nuclear fuel", W. Ha, G. Kim, Y. Jung, S. Ahn*.

Journal of Nuclear Materials 587 (2023), "Experimental Estimation of Radiation Damage Induced by 10B(n, α)7Li Reactions in Al-B4C Neutron Absorber Discharged from Spent Nuclear Fuel Pool", Y. Jung, G. Kim, W. Ha, S. Ahn*.

Journal of the American Ceramic Society (2023), "Expedited Spark Plasma Sintering of High-density UN Pellet utilizing U2N3 powder", J. Ahn, G. Kim, C. Nam, W. Ha, S. Ahn*.

Computer Physics Communications 282, 108513 (2023), "SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel pools", G. Kim, Y. Jung, M. Lee, E. Yoon*, S. Ahn*.

Journal of Nuclear Materials 555, (2021), “Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steels“, M. Lee, G. Kim, Y. Jung, S. Ahn*.

Journal of Nuclear Materials 552, (2021), “Accelerated corrosion tests of Al-B4C neutron absorber used in spent nuclear fuel pool“, Y. Jung, Y. Lee, J. Kim, S. Ahn*.

Journal of Nuclear Materials 546, (2021), “Thermal conductivity of gadolinium added uranium mononitride fuel pellets sintered by spark plasma sintering“, G. Kim, S. Ahn*.

Ceramics International 47, 7258-7262 (2021), “Grain growth and densification of uranium mononitride during spark plasma sintering“, G. Kim, J. Ahn, S. Ahn*.

Nuclear Engineering and Technology 53, 583-591 (2021), “Fabrication and thermal conductivity of CeO2-Ce3Si2 composite“, J. Ahn, G. Kim, Y. Jung, S. Ahn*.

Journal of Nuclear Materials 533, (2020), “10B(n, α)7Li reaction-induced gas bubble formation in Al–B4C neutron absorber irradiated in spent nuclear fuel pool“, Y. Jung, M. Lee, K. Kim, S. Ahn*.

Journal of Nuclear Materials 497, 10-15 (2017), “Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction”, S. Irukuvarghula, B. Blamer, S. Ahn, S.C. Vogel, A. Losko, S.M. McDeavitt.

Journal of Alloys and Compounds 681, 6-11 (2016), “Microstructure of α-U and δ-UZr2 phase uranium–zirconium alloys irradiated with 140-keV He+ ion-beam”, S. Ahn*, S. Irukuvarghula, S.M. McDeavitt.

Journal of Nuclear Materials 473, 206-217 (2016), “Decomposition of the γ phase in as-cast and quenched U–Zr alloys”, S. Irukuvarghula, S. Ahn, S.M. McDeavitt.

Journal of Alloys and Compounds 611, 355-362 (2014), “Thermophysical investigations of the uranium-zirconium alloy system”, S. Ahn*, S. Irukuvarghula, S.M. McDeavitt.

Journal of Nuclear Materials 436, 100-104 (2013), “Coexistence of the α and δ phases in an as-cast uranium-rich U–Zralloy”, J.T. McKeown, S. Irukuvarghula, S. Ahn, M.A. Wall, L.L. Hsiung, S.M. McDeavitt, P.E.A. Turchi.

Selected International Conference Proceedings

W. Ha, S. Ahn*, ”Emulation of Radiation Damage in Neutron Absorber Under Dry Storage Environments,” Transactions of the American Nuclear Society 129 (2023).

G. Kim, S. Ahn*, ”Thermal conductivity measurement of non-stoichiometric UO2 pellet for advanced nuclear material accountancy,” Transactions of Global 2019

Y. Jung, S. Ahn*, ”10B(n, α)7Li Reaction-Assisted Corrosion of Al-B4C Metal Matrix Composite Neutron Absorber Irradiated in Spent Nuclear Fuel Pool,” Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials (2019)

J. Ahn, S. Ahn*, ”Thermal conductivity of UO2-U3Si2 composite fuel surrogate,” Transactions of the American Nuclear Society 119 (2018) 553-554.

Y. Jung, S. Ahn*, ”Helium Bubble Formation in Neutron Absorber Material Irradiated in Spent Nuclear Fuel Pool,” Transactions of the American Nuclear Society 119 (2018) 299-300.

J. Ahn, S. Ahn*, ”UO2-based accident-tolerant hybrid fuel: a comparative study of high thermal conductivity additives,” Proceedings of the Water Reactor Fuel Performance Meeting (2017). 

S. Ahn*, S.M. McDeavitt, “An investigation of U-Zr alloy phase diagram using in-situ heating electron diffractometry,” Transactions of the American Nuclear Society 109 (2013) 608-611.

S. Ahn*, S.M. McDeavitt, “Transformation enthalpies of uranium-zirconium alloy system,” Transactions of the American Nuclear Society 106 (2012) 239-241.