발행물
컨퍼런스
Global/Top Fuel 2019
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Thermal conductivity measurement of non-stoichiometric UO2 pellet for advanced nuclear material accountancy
19th International Symposium on the Packaging and Transportation of Radioactive Materials
10B(n, α)7Li Reaction-Assisted Corrosion of Al-B4C Metal Matrix Composite Neutron Absorber Irradiated in Spent Nuclear Fuel Pool
Korean Nuclear Society Spring Meeting
Microstructure Evolution and Performance of Neutron Absorber in Spent Nuclear Fuel Pool
2018 Transactions of the American Nuclear Society, ANS 2018
Helium Bubble Formation in Neutron Absorber Material Irradiated in Spent Nuclear Fuel Pool
Thermal Conductivity of UO2-U3Si2 Composite Fuel Surrogate