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Post-irradiation Microstructural Characterization on 3.5-MeV Self-ion Irradiated Ferritic/Martensitic Steels at a Radiation Damage Level of 480 dpa

Lee, Myeongkyu , Ahn, Sangjoon

Conference Paper Issue Date2022-05-19 View7

Post-irradiation Microstructural Characterization on 3.5-MeV Self-ion Irradiated Ferritic/Martensitic Steels at a Radiation Damage Level of 480 dpa

Lee, Myeongkyu , Ahn, Sangjoon

Conference Paper Issue Date2022-05-19 View4

Potential utilization of laser flash analysis for on-site measurement of UO2 stoichiometry

Kim, Gyeonghun , Ahn, Jungsu , Ahn, Sangjoon

Conference Paper Issue Date2018-05-30 View6

Radiation resistance of FC.92

Lee, Myeongkyu , Kim, Geon , Ahn, Jungsu , Ahn, Sangjoon

Conference Paper Issue Date2018-05-18 View8

Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steels File

Lee, Myeongkyu , Kim, Geon , Jung, Yunsong , Ahn, Sangjoon

Article Issue Date2021-11 View19

SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel pools File

Kim, Geon , Jung, Yunsong , Lee, Myeongkyu , Yoon, Eisung , Ahn, Sangjoon

Article Issue Date2023-01 View11

Simulation of Radiation Damage and He Accumulation Induced by 10B(n, α)7Li Reactions in Al-B4C Neutron Absorbers Used in Spent Fuel Pools File

Kim, Geon , Lee, Myeongkyu , Jung, Yunsong , Yoon, Eisung , Ahn, Sangjoon

Article Issue Date2024-01 View11

Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction File

Irukuvarghula, S. , Blamer, B. , Ahn, Sangjoon , Vogel, S. C. , Losko, A. S. , McDeavitt, S. M.

Article Issue Date2017-12 View11

Thermal conductivity measurement of non-stoichiometric UO2 pellet for advanced nuclear material accountancy

Kim, Gyeonghun , Ahn, Jungsu , Ahn, Sangjoon

Conference Paper Issue Date2019-09-24 View6

Thermal conductivity of CeO2-Ce3Si2 hybrid ceramic

Ahn, Jungsu , Lee, Myongkyu , Ahn, Sangjoon

Conference Paper Issue Date2018-05-17 View6

Thermal conductivity of gadolinium added uranium mononitride fuel pellets sintered by spark plasma sintering File

Kim, Gyeonghun , Ahn, Sangjoon

Article Issue Date2021-04 View13

Thermal Conductivity of UO2-U3Si2 Composite Fuel Surrogate

Ahn, Jungsu , Kim, Gyeonghun , Ahn, Sangjoon

Conference Paper Issue Date2018-11-15 View4

Thermal Stability of Uranium-rich U-Mo Alloys for Advanced Nuclear Fuels

McKeown, Joseph T. , Ahn, Sangjoon , Wall, Mark A. , Hsiung, Luke L. , McDeavitt, Sean M. , Turchi, Patrice E.A.

Conference Paper Issue Date2014-02-16 View4

Thermodynamic assessment of the uranium-zirconium alloy system for nuclear energy applications

Ahn, Sangjoon , Irukuvarghula, Sandeep , McDeavitt, Sean M.

Conference Paper Issue Date2012-03-12 View6

Thermophysical investigation of uranium-zirconium alloy phase diagram

Ahn, Sangjoon , McDeavitt, Sean M.

Conference Paper Issue Date2012-05-18 View4

Thermophysical investigations of the uranium-zirconium alloy system File

Ahn, Sangjoon , Irukuvarghula, Sandeep , McDeavitt, Sean M.

Article Issue Date2014-10 View12

Transformation enthalpies of uranium-zirconium alloy system

Ahn, Sangjoon , McDeavitt, Sean M.

Conference Paper Issue Date2012-06-28 View5

UO2-BASED ACCIDENT-TOLERANT HYBRID FUEL: A COMPARATIVE STUDY OF HIGH THERMAL CONDUCTIVITY ADDITIVES

Ahn, Jungsu , Lee, Myeongkyu , Ahn, Sangjoon

Conference Paper Issue Date2017-10-10 View6

규화우라늄을 함유한 이산화우라늄 핵연료의 제조 방법

안정수 , 김용희 , 안상준

Patent Issue Date View4

스파크 플라즈마 소결을 이용한 고밀도 핵연료 소결체 제조방법

안상준 , 김용희 , 안정수

Patent Issue Date View4

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