Sangjoon Ahn
Sangjoon Ahn
Ulsan National Institute of Science and Engineering
Verified email at unist.ac.kr - Homepage
Title
Cited by
Cited by
Year
Coexistence of the and phases in an as-cast uranium-rich U–Zr alloy
JT Mckeown, S Irukuvarghula, S Ahn, MA Wall, LL Hsiung, S McDeavitt, ...
Journal of nuclear materials 436 (1-3), 100-104, 2013
362013
Thermophysical investigations of the uranium–zirconium alloy system
S Ahn, S Irukuvarghula, SM McDeavitt
Journal of alloys and compounds 611, 355-362, 2014
262014
Decomposition of the phase in as-cast and quenched U–Zr alloys
S Irukuvarghula, S Ahn, SM McDeavitt
Journal of Nuclear Materials 473, 206-217, 2016
202016
Microstructure of -U and -UZr2 phase uranium–zirconium alloys irradiated with 140-keV He+ ion-beam
S Ahn, S Irukuvarghula, SM McDeavitt
Journal of Alloys and Compounds 681, 6-11, 2016
52016
Transformation Enthalpies of Uranium-Zirconium Alloy System
S Ahn, SM McDeavitt
Transactions 106 (1), 239-241, 2012
52012
Texture evolution during annealing of hot extruded U-10wt% Zr alloy by in situ neutron diffraction
S Irukuvarghula, B Blamer, S Ahn, SC Vogel, AS Losko, SM McDeavitt
Journal of Nuclear Materials 497, 10-15, 2017
42017
An Investigation of U-Zr Alloy Phase Diagram Using In-Situ Heating Electron Diffractometry
S Ahn, SM McDeavitt
Transactions 109 (1), 608-611, 2013
12013
Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects
S Ahn
12013
Fabrication and thermal conductivity of CeO2–Ce3Si2 composite
J Ahn, G Kim, Y Jung, S Ahn
Nuclear Engineering and Technology, 2020
2020
10B (n, ) 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, 152077, 2020
2020
Thermal conductivity measurement of non-stoichiometric UO2 pellet for advanced nuclear material accountancy
G Kim, J Ahn, S Ahn
American Nuclear Society, 2019
2019
10B (n, ) 7Li Reaction-Assisted Corrosion of Al-B4C Metal Matrix Composite Neutron Absorber Irradiated in Spent Nuclear Fuel Pool
Y Jung, K Kim, S Ahn
Institute of Nuclear Materials Management, 2019
2019
Helium Bubble Formation in Neutron Absorber Material Irradiated in Spent Nuclear Fuel Pool
Y Jung, K Kim, S Ahn
Transactions 119 (1), 299-300, 2018
2018
Thermal Conductivity of UO2-U3Si2 Composite Fuel Surrogate
J Ahn, G Kim, S Ahn
Transactions 119 (1), 553-554, 2018
2018
Radiation resistance of FC. 92
M Lee, G Kim, J Ahn, S Ahn
Korean Nuclear Society, 2018
2018
Packaging and Transportation of Radioactive Materials PATRAM 2019 August 4-9, 2019, New Orleans, LA, USA
T BANDE, MHV LEBLANC, G LOURTIE
Official Journal on, 2018
2018
Potential Utilization of Laser Flash Analysis for On-Site Measurement of UO2 Stoichiometry
G Kim, J Ahn, S Ahn
Proceedings of the Korean Radioactive Waste Society Conference, 21-22, 2018
2018
UO2-based accident-tolerant hybrid fuel: a comparative study of high thermal conductivity additives
J Ahn, M Lee, S Ahn
Korean Nuclear Society, 2017
2017
Expedited Experimental Simulation of High Burnup Microstructure of Advanced Ferritic/martensitic Steel Claddings for Sodium-cooled Fast Reactor
M Lee, G Kim, J Ahn, S Ahn
2016
Thermal Stability of Uranium-rich U-Mo Alloys for Advanced Nuclear Fuels
JT McKeown, S Ahn, MA Wall, LL Hsiung, SM McDeavitt, PEA Turchi
The Minerals, Metals and Materials Society, 2014
2014
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