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B-10(n, alpha)Li-7 reaction-induced gas bubble formation in Al-B4C neutron absorber irradiated in spent nuclear fuel pool File

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

Article Issue Date2020-05 View149
Expedited Experimental Simulation of High Burnup Microstructure of Advanced Ferritic/martensitic Steel Claddings for Sodium-cooled Fast Reactor

Lee, Myeongkyu , Kim, Geon , Ahn, Junsu , Ahn, Sangjoon

Conference Paper Issue Date2016-10-28 View86
MICROSTRUCTURAL INSTABILITY EVOLVED IN ION-IRRADIATED FERRITIC/MARTENSITIC STEELS AT HIGH RADIATION DAMAGE LEVELS File File

Lee, Myeongkyu

Thesis Issue Date2021-08 View59
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 View74
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 View37
Radiation resistance of FC.92

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

Conference Paper Issue Date2018-05-18 View75
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 View122
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 View130
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 View173
Swelling at high radiation damage levels of 120 and 240 dpa in 3.5 MeV self-ion irradiated ferritic/martensitic steels File

Lee, Myeongkyu , Kim, Geon , Ahn, Sangjoon

Article Issue Date2024-10 View91
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 View70
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