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Sohn, Dong-Seong (손동성)

Department
School of Mechanical, Aerospace and Nuclear Engineering(기계항공및원자력공학부)
Research Interests
Nuclear fuel design, Nuclear fuel , Nuclear system, Performance analysis
Lab
Innovative Nuclear FUEL(INFUEL)
Website
http://dssohn.unist.ac.kr/
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Issue DateTitleAuthor(s)TypeViewAltmetrics
2019-12Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube”Lee, Cheol Min; Kim, Gyeonghun; Sohn, Dong-Seong, et alARTICLE248 Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube”
2019-09Study of mechanism of oxidation resistance enhancement induced by preformed oxide on zirconium alloysLee, Cheol Min; Han, Young-Soo; Mok, Yong-Kyoon, et alARTICLE95 Study of mechanism of oxidation resistance enhancement induced by preformed oxide on zirconium alloys
2019-08Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materialsKim, Mi Jin; Kim, Wonkyeong; Lee, Deokjung, et alARTICLE163 Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials
2019-07Performance analysis of UO2 fuel rod for low-power research reactor applicationJeong, Gwan Yoon; Cho, Tae Won; Sohn, Dong-Seong, et alARTICLE216 Performance analysis of UO2 fuel rod for low-power research reactor application
2019-03Effect of pre-oxidation temperature on the ductility of a zirconium alloy cladding under simulated accident conditionsLee, Cheol Min; Lee, Hee-Jae; Kim, Hyun-Gil, et alARTICLE174 Effect of pre-oxidation temperature on the ductility of a zirconium alloy cladding under simulated accident conditions
2019-02Corrosion and mechanical properties of hot-rolled 0.5%Gd-0.8%B-stainless steels in a simulated nuclear waste treatment solutionJung, Moo Young; Baik, Youl; Choi, Yong, et alARTICLE188 Corrosion and mechanical properties of hot-rolled 0.5%Gd-0.8%B-stainless steels in a simulated nuclear waste treatment solution
2018-12Dependence of thickness, morphology, and crystallographic properties of Mo and ZrN coatings on U-Mo substrate sizeKim, Ji-Hyeon; Jeong, Gwan Yoon; Kim, Sunghwan, et alARTICLE273 Dependence of thickness, morphology, and crystallographic properties of Mo and ZrN coatings on U-Mo substrate size
2018-08Effect of coating thickness and annealing temperature on ZrN coating failure of U-Mo particles under heat treatmentKim, Ji-Hyeon; Jeong, Gwan Yoon; Kim, Sunghwan, et alARTICLE199 Effect of coating thickness and annealing temperature on ZrN coating failure of U-Mo particles under heat treatment
2018-07Microstructural characteristics and different effects of 800-1200 °C preformed oxides on high-temperature steam oxidation of a zirconium alloy claddingLee, Cheol Min; Jeong, Hu Young; Yoon, Aram, et alARTICLE219 Microstructural characteristics and different effects of 800-1200 °C preformed oxides on high-temperature steam oxidation of a zirconium alloy cladding
2018-07Microstructural analysis of preformed oxides on a zirconium alloy before and after subsequent oxidation at 1000-1200 °CLee, Cheol Min; Jeong, Hu Young; Yoon, Aram, et alARTICLE128 Microstructural analysis of preformed oxides on a zirconium alloy before and after subsequent oxidation at 1000-1200 °C
2018-06Thermophysical properties of sintered aluminum-siliconCho, Tae Won; Kim, Yeon Soo; Sohn, Dong-SeongARTICLE485 Thermophysical properties of sintered aluminum-silicon
2018-04Thermophysical properties of heat-treated U-7Mo/Al dispersion fuelCho, Tae Won; Kim, Yeon Soo; Park, Jong Man, et alARTICLE495 Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel
2018-04Development of PRIME for irradiation performance analysis of U-Mo/Al dispersion fuelJeong, Gwan Yoon; Kim, Yeon Soo; Jeong, Young Jin, et alARTICLE401 Development of PRIME for irradiation performance analysis of U-Mo/Al dispersion fuel
2018-02Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the claddingLee, Cheol Min; Sohn, Dong-SeongARTICLE473 Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the cladding
2017-12Thermal properties of U-7Mo/Al dispersion fuelCho, Tae Won; Kim, Yeon Soo; Park, Jong Man, et alARTICLE488 Thermal properties of U-7Mo/Al dispersion fuel
2017-12High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel claddingLee, Cheol Min; Mok, Yong-Kyoon; Sohn, Dong-SeongARTICLE472 High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding
2017-04Application of a Dynamic-Nanoindentation Method to Analyze the Local Structure of an Fe-18 at.% Gd Cast AlloyChoi, Yong; Baik, Youl; Moon, Byung M., et alARTICLE459 Application of a Dynamic-Nanoindentation Method to Analyze the Local Structure of an Fe-18 at.% Gd Cast Alloy
2017-04Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuelJeong, G.Y.; Kim, Yeon Soo; Jamison, L.M., et alARTICLE490 Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel
2016-09Pore growth in U-Mo/Al dispersion fuelKim, Yeon Soo; Jeong, G.Y; Sohn, Dong-Seong, et alARTICLE627 Pore growth in U-Mo/Al dispersion fuel
2016-02Corrosion and Wear Properties of Cold Rolled 0.087% Gd Lean Duplex Stainless Steels for Neutron Absorbing MaterialChoi, Yong; Baik, Youl; Moon, Byung M., et alARTICLE678 Corrosion and Wear Properties of Cold Rolled 0.087% Gd Lean Duplex Stainless Steels for Neutron Absorbing Material

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