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Sangjoon Ahn
Sangjoon Ahn
Ulsan National Institute of Science and Engineering
Verified email at unist.ac.kr - Homepage
Title
Cited by
Cited by
Year
Direct ink writing of three-dimensional thermoelectric microarchitectures
F Kim, SE Yang, H Ju, S Choo, J Lee, G Kim, S Jung, S Kim, C Cha, ...
Nature Electronics 4 (8), 579-587, 2021
652021
Coexistence of the á and ä 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
592013
Composition-segmented BiSbTe thermoelectric generator fabricated by multimaterial 3D printing
SE Yang, F Kim, F Ejaz, GS Lee, H Ju, S Choo, J Lee, G Kim, S Jung, ...
Nano Energy 81, 105638, 2021
522021
Cu2Se-based thermoelectric cellular architectures for efficient and durable power generation
S Choo, F Ejaz, H Ju, F Kim, J Lee, SE Yang, G Kim, H Kim, S Jo, S Baek, ...
Nature communications 12 (1), 3550, 2021
482021
Decomposition of the ã phase in as-cast and quenched U–Zr alloys
S Irukuvarghula, S Ahn, SM McDeavitt
Journal of Nuclear Materials 473, 206-217, 2016
432016
Thermophysical investigations of the uranium–zirconium alloy system
S Ahn, S Irukuvarghula, SM McDeavitt
Journal of alloys and compounds 611, 355-362, 2014
392014
Doping‐induced viscoelasticity in PbTe thermoelectric inks for 3D printing of power‐generating tubes
J Lee, S Choo, H Ju, J Hong, SE Yang, F Kim, DH Gu, J Jang, G Kim, ...
Advanced Energy Materials 11 (20), 2100190, 2021
332021
10B (n, á) 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 533, 152077, 2020
252020
Microstructure of á-U and ä-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
162016
Accelerated corrosion tests of Al-B4C neutron absorber used in spent nuclear fuel pool
Y Jung, Y Lee, JH Kim, S Ahn
Journal of Nuclear Materials 552, 153011, 2021
112021
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
92017
Grain growth and densification of uranium mononitride during spark plasma sintering
G Kim, J Ahn, S Ahn
Ceramics International 47 (5), 7258-7262, 2021
82021
Thermal conductivity of gadolinium added uranium mononitride fuel pellets sintered by spark plasma sintering
G Kim, S Ahn
Journal of Nuclear Materials 546, 152785, 2021
62021
Comprehensive investigation of the uranium-zirconium alloy system: Thermophysical properties, phase characterization and ion implantation effects
S Ahn
Texas A&M University, 2013
62013
Transformation enthalpies of uranium-zirconium alloy system
S Ahn, SM McDeavitt
AMERICAN NUCLEAR SOCIETY, 2012
52012
SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel pools
G Kim, Y Jung, M Lee, E Yoon, S Ahn
Computer Physics Communications 282, 108513, 2023
42023
Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steels
M Lee, G Kim, Y Jung, S Ahn
Journal of Nuclear Materials 555, 153137, 2021
32021
Fabrication and thermal conductivity of CeO2–Ce3Si2 composite
J Ahn, G Kim, Y Jung, S Ahn
Nuclear Engineering and Technology 53 (2), 583-591, 2021
32021
Experimental estimation of radiation damage induced by 10B (n, á) 7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel pool
Y Jung, G Kim, W Ha, S Ahn
Journal of Nuclear Materials 587, 154728, 2023
12023
UO2-based accident-tolerant hybrid fuel: a comparative study of high thermal conductivity additives
J Ahn, M Lee, S Ahn
Korean Nuclear Society, 2017
12017
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Articles 1–20