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10B(n, α)7Li Reaction-Assisted Corrosion of Al-B4C Metal Matrix Composite Neutron Absorber Irradiated in Spent Nuclear Fuel Pool

Jung, Yunsong , Kim, Kiyoung , Ahn, Sangjoon

Conference Paper Issue Date2019-08-07 View13

3D printing of compositionally segmented BiSbTe legs for high performance power generation

Yang, Seong Eun , Kim, Fredrick , Ejaz, Faizan , Lee, Gi Seung , Ju, Hyejin , Choo, Seungjun , Lee, Jungsoo , Kim, Gyeonghun , Jung, Soo-ho , Ahn, Sangjoon , et al

Conference Paper Issue Date2020-07-21 View12

Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam, and Modeling

McKeown, Joseph T. , Ahn, Sangjoon , Wall, Mark A. , Hsiung, Luke L. , Fluss, Michael , Tumey, Scott , Brown, Thomas , McDeavitt, Sean M. , Turchi, Patrice E.A.

Conference Paper Issue Date2014-02-16 View5

Alloys for Dispersion-type Inert-Matrix Nuclear Fuels

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

Conference Paper Issue Date2013-09-15 View5

An investigation of U-Zr alloy phase diagram using in-situ heating electron diffractometry

Ahn, Sangjoon , McDeavitt, Sean M.

Conference Paper Issue Date2013-11-14 View6

Characterization of U-Zr alloys for ultrahigh burn-up nuclear fuels

Mckeown, Joseph T. , Ahn, Sangjoon , Irukuvarghula, Sandeep , Wall, Mark A. , Hsiung, Luke L. , McDeavitt, Sean M. , Turchi, Patrice Erne A.

Conference Paper Issue Date2012-10-08 View6

Compatibility demonstration of centrally shileded burnable absorber imbedded UO2-U3Si2 fuel for soluble-boron-free i-SMR development

Ahn, Sangjoon

Conference Paper Issue Date2022-11-10 View9

Direct ink writing of 3D thermoelectric architectures for fabrication of micro power generators

Yang, Seong Eun , Kim, Fredrick , Ju, Hyejin , Choo, Seungjun , Lee, Jungsoo , Kim, Gyeonghun , Jung, Soo-ho , Kim, Suntae , Cha, Chaenyung , Kim, Kyung Tae , et al

Conference Paper Issue Date2021-11-09 View6

Doping-Induced Viscoelasticity in PbTe Thermoelectric Inks for 3D Printing of Power-Generating Tubes

Lee, Jungsoo , Choo, Seungjun , Ju, Hyejin , Hong, Jaehyung , Yang, Seong Eun , Kim, Fredrick , Gu, Da Hwi , Jang, Jeongin , Kim, Gyeonghun , Ahn, Sangjoon , et al

Conference Paper Issue Date2021-11-09 View7

Doping-induced Viscoelasticity in PbTe Thermoelectric Inks for 3D printing of Power-generating Tubes

Lee, Jungsoo , Choo, Seungjun , Ju, Hyejin , Hong, Jaehyung , Yang, Seong Eun , Kim, Fredrick , Gu, Da Hwi , Jang, Jeongin , Kim, Gyeonghun , Ahn, Sangjoon , et al

Conference Paper Issue Date2021-07-22 View7

Emulation of Radiation Damage in Al-B4C Neutron Absorber Used in Temporary/Interim Spent Nuclear Fuel Storage Facility

Ha, Woong , Ahn, Sangjoon

Conference Paper Issue Date2023-06-02 View11

Emulation of Radiation Damage in Neutron Absorber under Dry Storage Environments

Ha, Woong , Ahn, Sangjoon

Conference Paper Issue Date2023-11-15 View13

Enhanced Fabrication of UN Pellet from U2N3 Powder using Spark Plasma Sintering

Ahn, Jungsu , Ahn, Sangjoon

Conference Paper Issue Date2022-05-19 View8

Estimation of Radiation Damage and Gaseous Ion Accumulation in Neutron Absorbers

Kim, Geon , Yoon, Eisung , Ahn, Sangjoon

Conference Paper Issue Date2022-05-19 View6

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 View5

Expedited Experimental Simulation of High Burnup Microstructure of Advanced Ferritic/martesitic Steel Claddings for Sodium-cooled Fast Reactor

Lee, Myeonghkyu , Kim, Geon , Ahn, Jungsu , Ahn, Sangjoon

Conference Paper Issue Date2016-10-28 View4

Helium Bubble Formation in Neutron Absorber Material Irradiated in Spent Nuclear Fuel Pool

Jung, Yunsong , Kim, Kiyoung , Ahn, Sangjoon

Conference Paper Issue Date2018-11-15 View8

Metallurgical characterization of the delta phase formation in uranium-zirconium alloy fuels

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

Conference Paper Issue Date2012-03-12 View26

Microstructural assessment of U-rich U-Zr alloys for advanced nuclear fuels

Mckeown, Joseph T. , Irukuvarghula, Sandeep , Ahn, Sangjoon , Wall, Mark A. , Hsiung, Luke L. , McDeavitt, Sean M. , Turchi, Patrice Erne A.

Conference Paper Issue Date2013-03-04 View2

Microstructure Evolution and Performance of Neutron Absorber in Spent Nuclear Fuel Pool

Jung, Yunsong , Ha, Woong , Kim, Kiyoung , Ahn, Sangjoon

Conference Paper Issue Date2019-03-24 View7

Neutron source design for lead slowing down time spectrometer

Ahn, Sangjoon , Kim, Jeongdong , Kim, Younggook , Lee, Yongdeok , Park, Changje

Conference Paper Issue Date2014-11-11 View6

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 View8

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 View5

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 View9

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 View11

Thermal conductivity of CeO2-Ce3Si2 hybrid ceramic

Ahn, Jungsu , Lee, Myongkyu , Ahn, Sangjoon

Conference Paper Issue Date2018-05-17 View6

Thermal Conductivity of UO2-U3Si2 Composite Fuel Surrogate

Ahn, Jungsu , Kim, Gyeonghun , Ahn, Sangjoon

Conference Paper Issue Date2018-11-15 View10

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 View7

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 View10

Thermophysical investigation of uranium-zirconium alloy phase diagram

Ahn, Sangjoon , McDeavitt, Sean M.

Conference Paper Issue Date2012-05-18 View5

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 View9

조사손상 관점에서의 용융염고속로 재료 이슈 예측

안상준

Conference Paper Issue Date2022-11-24 View7

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