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Ahn, Sangjoon (안상준)

Department
Department of Nuclear Engineering(원자력공학과)
Website
https://sites.google.com/view/uranum
Lab
UNIST RAdioactive NUclear Materials Lab. (핵연료재료 연구실)
Research Keywords
원자력공학, 우라늄, 핵연료재료, 핵연료, Nuclear, Nuclear fuel, Nuclear materials, Nuclear fuel engineering, Radiation materials science
Research Interests
The URANUM is an experimental lab dedicated to nuclear fuel engineering and radiation materials science at Ulsan National Institute of Science and Technology (UNIST). We are mainly interested in metallurgy, thermophysics, and irradiation behavior of uranium alloys and compounds as nuclear fuel in and outside of nuclear reactors. Some other materials that have to suffer radiation damage are also of our interest, such as zirconium alloys, stainless steels, and Al-B4C metal matrix composite (MMC) neutron absorbers.
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Issue DateTitleAuthor(s)TypeViewAltmetrics
2023-12Experimental estimation of radiation damage induced by 10B(n, α)7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel poolJung, Yunsong; Kim, Geon; Ha, Woong, et alARTICLE70 Experimental estimation of radiation damage induced by 10B(n, α)7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel pool
2023-09Expedited spark plasma sintering of high‐density uranium mononitride pellet utilizing U2</sub>N3</sub> powderAhn, Jungsu; Kim, Geon; Nam, Changhyeon, et alARTICLE82 Expedited spark plasma sintering of high‐density uranium mononitride pellet utilizing U<sub>2</sub>N<sub>3</sub> powder
2023-01SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel poolsKim, Geon; Jung, Yunsong; Lee, Myeongkyu, et alARTICLE849 SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel pools
2021-11Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steelsLee, Myeongkyu; Kim, Geon; Jung, Yunsong, et alARTICLE569 Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steels
2021-08Accelerated corrosion tests of Al-B4C neutron absorber used in spent nuclear fuel poolJung, Yunsong; Lee, Yunju; Kim, Ji Hyun, et alARTICLE484 Accelerated corrosion tests of Al-B4C neutron absorber used in spent nuclear fuel pool
2021-08Direct ink writing of three-dimensional thermoelectric microarchitecturesKim, Fredrick; Yang, Seong Eun; Ju, Hyejin, et alARTICLE836 Direct ink writing of three-dimensional thermoelectric microarchitectures
2021-06Cu2Se-based thermoelectric cellular architectures for efficient and durable power generationChoo, Seungjun; Ejaz, Faizan; Ju, Hyejin, et alARTICLE617 Cu2Se-based thermoelectric cellular architectures for efficient and durable power generation
2021-05Doping-induced viscoelasticity in PbTe thermoelectric inks for 3D printing of power-generating tubesLee, Jungsoo; Choo, Seungjun; Ju, Hyejin, et alARTICLE577 Doping-induced viscoelasticity in PbTe thermoelectric inks for 3D printing of power-generating tubes
2021-04Thermal conductivity of gadolinium added uranium mononitride fuel pellets sintered by spark plasma sinteringKim, Gyeonghun; Ahn, SangjoonARTICLE562 Thermal conductivity of gadolinium added uranium mononitride fuel pellets sintered by spark plasma sintering
2021-03Composition-segmented BiSbTe thermoelectric generator fabricated by multimaterial 3D printingYang, Seong Eun; Kim, Fredrick; Ejaz, Faizan, et alARTICLE681 Composition-segmented BiSbTe thermoelectric generator fabricated by multimaterial 3D printing
2021-03Grain growth and densification of uranium mononitride during spark plasma sinteringKim, Gyeonghun; Ahn, Jungsu; Ahn, SangjoonARTICLE599 Grain growth and densification of uranium mononitride during spark plasma sintering
2021-02Fabrication and thermal conductivity of CeO2–Ce3Si2 compositeAhn, Jungsu; Kim, Gyeonghun; Jung, Yunsong, et alARTICLE753 Fabrication and thermal conductivity of CeO2–Ce3Si2 composite
2020-05B-10(n, alpha)Li-7 reaction-induced gas bubble formation in Al-B4C neutron absorber irradiated in spent nuclear fuel poolJung, Yunsong; Lee, Myeongkyu; Kim, Kiyoung, et alARTICLE653 B-10(n, alpha)Li-7 reaction-induced gas bubble formation in Al-B4C neutron absorber irradiated in spent nuclear fuel pool
2017-12Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffractionIrukuvarghula, S.; Blamer, B.; Ahn, Sangjoon, et alARTICLE1168 Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction
2016-10Microstructure of alpha-U and delta-UZr2 phase uranium-zirconium alloys irradiated with 140-keV He+ ion-beamAhn, Sangjoon; Irukuvarghula, Sandeep; McDeavitt, Sean M.ARTICLE1684 Microstructure of alpha-U and delta-UZr2 phase uranium-zirconium alloys irradiated with 140-keV He+ ion-beam
2016-05Decomposition of the γ phase in as-cast and quenched U-Zr alloysIrukuvarghula, S.; Ahn, Sangjoon; McDeavitt, S.M.ARTICLE1322 Decomposition of the γ phase in as-cast and quenched U-Zr alloys
2015-04DESIGN OPTIMIZATION OF RADIATION SHIELDING STRUCTURE FOR LEAD SLOWING-DOWN SPECTROMETER SYSTEMKim, Jeongdong; Ahn, Sangjoon; Lee, Yongdeok, et alARTICLE1654 DESIGN OPTIMIZATION OF RADIATION SHIELDING STRUCTURE FOR LEAD SLOWING-DOWN SPECTROMETER SYSTEM
2014-12DEVELOPMENT OF LEAD SLOWING DOWN SPECTROMETER FOR ISOTOPIC FISSILE ASSAYLee, Yongdeok; Park, Changje; Ahn, Sangjoon, et alARTICLE1486 DEVELOPMENT OF LEAD SLOWING DOWN SPECTROMETER FOR ISOTOPIC FISSILE ASSAY
2014-10Thermophysical investigations of the uranium-zirconium alloy systemAhn, Sangjoon; Irukuvarghula, Sandeep; McDeavitt, Sean M.ARTICLE1771 Thermophysical investigations of the uranium-zirconium alloy system
2013-05Coexistence of the α and δ phases in an as-cast uranium-rich U-Zr alloyMckeown, Joseph T.; Irukuvarghula, Sandeep; Ahn, Sangjoon, et alARTICLE1564 Coexistence of the α and δ phases in an as-cast uranium-rich U-Zr alloy

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