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Showing results 1 to 9 of 9

Issue DateTitleAuthor(s)TypeView
2023-02A Safety Analysis Code for Al-B4C Neutron Absorbers Used in Spent Nuclear Fuel PoolAhn, Sangjoon; Kim, GeonDoctoral thesis552
2022-05-19Estimation of Radiation Damage and Gaseous Ion Accumulation in Neutron AbsorbersKim, Geon; Yoon, Eisung; Ahn, SangjoonCONFERENCE125
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, SangjoonCONFERENCE325
2016-10-28Expedited Experimental Simulation of High Burnup Microstructure of Advanced Ferritic/martesitic Steel Claddings for Sodium-cooled Fast ReactorLee, Myeonghkyu; Kim, Geon; Ahn, Jungsu; Ahn, SangjoonCONFERENCE347
2023-09Expedited spark plasma sintering of high‐density uranium mononitride pellet utilizing U2</sub>N3</sub> powderAhn, Jungsu; Kim, Geon; Nam, Changhyeon; Ha, Woong; Ahn, SangjoonARTICLE82
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; Ahn, SangjoonARTICLE70
2018-05-18Radiation resistance of FC.92Lee, Myeongkyu; Kim, Geon; Ahn, Jungsu; Ahn, SangjoonCONFERENCE348
2021-11Radiation-induced swelling and precipitation in Fe++ ion-irradiated ferritic/martensitic steelsLee, Myeongkyu; Kim, Geon; Jung, Yunsong; Ahn, SangjoonARTICLE569
2023-01SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel poolsKim, Geon; Jung, Yunsong; Lee, Myeongkyu; Yoon, Eisung; Ahn, SangjoonARTICLE849
Showing results 1 to 9 of 9

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