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Showing results 1 to 9 of 9

Issue DateTitleAuthor(s)TypeView
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; Ahn, SangjoonARTICLE639
2016-10-28Expedited Experimental Simulation of High Burnup Microstructure of Advanced Ferritic/martensitic Steel Claddings for Sodium-cooled Fast ReactorLee, Myeongkyu; Kim, Geon; Ahn, Junsu; Ahn, SangjoonCONFERENCE319
2021-08MICROSTRUCTURAL INSTABILITY EVOLVED IN ION-IRRADIATED FERRITIC/MARTENSITIC STEELS AT HIGH RADIATION DAMAGE LEVELSAhn, Sangjoon; Lee, MyeongkyuDoctoral thesis1198
2022-05-19Post-irradiation Microstructural Characterization on 3.5-MeV Self-ion Irradiated Ferritic/Martensitic Steels at a Radiation Damage Level of 480 dpaLee, Myeongkyu; Ahn, SangjoonCONFERENCE115
2022-05-19Post-irradiation Microstructural Characterization on 3.5-MeV Self-ion Irradiated Ferritic/Martensitic Steels at a Radiation Damage Level of 480 dpaLee, Myeongkyu; Ahn, SangjoonCONFERENCE103
2018-05-18Radiation resistance of FC.92Lee, Myeongkyu; Kim, Geon; Ahn, Jungsu; Ahn, SangjoonCONFERENCE340
2021-11Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steelsLee, Myeongkyu; Kim, Geon; Jung, Yunsong; Ahn, SangjoonARTICLE559
2023-01SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel poolsKim, Geon; Jung, Yunsong; Lee, Myeongkyu; Yoon, Eisung; Ahn, SangjoonARTICLE835
2017-10-10UO2-BASED ACCIDENT-TOLERANT HYBRID FUEL: A COMPARATIVE STUDY OF HIGH THERMAL CONDUCTIVITY ADDITIVESAhn, Jungsu; Lee, Myeongkyu; Ahn, SangjoonCONFERENCE397
Showing results 1 to 9 of 9

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