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Showing results 43 to 50 of 50
Article
Radiation response of FeCrAl-coated Zircaloy-4SCIESCOPUS

Journal of Nuclear Materials, vol. 536, 2020-08

Article
Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel claddingSCIESCOPUS

Journal of Nuclear Materials, vol. 523, page. 26 - 32, 2019-09

Article
Radius of Contact During Friction Surfacing of Stainless Steel 304L: Effect of Spindle Speed and Rod DiameterSCOPUS

Journal of Manufacturing Science and Engineering, Transactions of the ASME, vol. 146, no. 2, 2024-02

Conference
Recent Approaches for Mitigation and Repair of Chloride-Induced Stress Corrosion Cracking (CISCC) in Stainless-Steel Canisters for Spent Nuclear Fuel

2023 추계학술발표회, 2023-10-27

Article
Structural evolution of oxidized surface of zirconium-silicide under ion irradiationmSCIESCOPUS

Applied Surface Science, vol. 455, page. 333 - 342, 2018-10

Conference
Technical Aspects of Back-end Fuel Cycle of Advanced Accident Tolerant Fuels

제21회 정기총회 및 2023 추계학술발표회, 2023-11-02

Article
Towards Multilayered Coatings of 304L Stainless Steels Using Friction SurfacingSCIESCOPUS

Journal of Manufacturing Science and Engineering, Transactions of the ASME, vol. 145, no. 1, 2023-01

Article
Transient pool boiling heat transfer of oxidized and roughened Zircaloy-4 surfaces during water quenchingSCIESCOPUS

International Journal of Heat and Mass Transfer, vol. 120, page. 435 - 446, 2018-05

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