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YEOM, HWASUNG(염화성) orcid research gate google scholar scopus

Department: Div. of Advanced Nuclear Engineering(첨단원자력공학부)

Major(s): Advanced Nuclear Fuel and Structural Material ; Surface Coating Technologies ; Safe Management of Spent Nuclear Fuel ; 차세대 핵연료 및 원자력 구조재료 ; 표면코팅기술 ; 사용후핵연료 저장 및 처분 기술

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Publication & Time Cited Count (For the Last 5 years)

Results 1-20 of 39 (Search time: 0.001 seconds).

Article

Fuel performance analysis of Cr-coated Zircaloy-4 cladding during a prototypical LOCA event using BISONSCIESCOPUS

Annals of Nuclear Energy, vol. 200, page. 110411, 2024-06

Article

In situ synchrotron investigation of tensile deformation and failure mechanisms in cold spray Cr-coated Zr-alloy systemSCIESCOPUS

Materials & Design, vol. 239, page. 112755, 2024-03

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

Article

Initial Study on Thermal Stability of Cold Spray Tantalum Coating Irradiated with Deuterium for Fusion ApplicationsSCIESCOPUS

Physica Scripta, vol. 98, no. 11, 2023-11

Article

Cold spray manufacturing of oxide-dispersion strengthened (ODS) steels using gas-atomized and ball-milled 14YWT powdersSCIESCOPUS

Journal of Nuclear Materials, vol. 574, 2023-02

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

Friction surfacing and cold spray deposition for surface crack repair in austenitic stainless steelsSCIESCOPUS

Materials Today Communications, vol. 33, 2022-12

Article

Microstructure and corrosion behavior of friction-surfaced 304L austenitic stainless steelsSCIESCOPUS

International Journal of Advanced Manufacturing Technology, vol. 122, no. 3-4, page. 1641 - 1649, 2022-09

Article

Leak-tight crack repair for 304L stainless steel using friction surfacingSCIESCOPUS

Journal of Manufacturing Processes, vol. 79, page. 532 - 543, 2022-07

Article

Microstructural and nanomechanical studies of PVD Cr coatings on SiC for LWR fuel cladding applicationsSCIESCOPUS

Surface and Coatings Technology, vol. 441, 2022-07

Article

Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubesSCIESCOPUS

Nuclear Materials and Energy, vol. 31, 2022-06

Article

Cold spray technology in nuclear energy applications: A review of recent advancesSCIESCOPUS

Annals of Nuclear Energy, vol. 150, 2021-01

Article

Experimental evaluation of direct current magnetron sputtered and high-power impulse magnetron sputtered Cr coatings on SiC for light water reactor applicationsSCIESCOPUS

Thin Solid Films, vol. 716, 2020-12

Article

Pool boiling critical heat flux studies of accident tolerant fuel cladding materialsSCIESCOPUS

Nuclear Engineering and Design, vol. 370, 2020-12

Article

Cold spray deposition of 304L stainless steel to mitigate chloride-induced stress corrosion cracking in canisters for used nuclear fuel storageSCIESCOPUS

Journal of Nuclear Materials, vol. 538, 2020-09

Article

Radiation response of FeCrAl-coated Zircaloy-4SCIESCOPUS

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

Article

Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout EventSCIESCOPUS

Nuclear Technology, vol. 206, no. 3, page. 467 - 477, 2020-08

Article

Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel claddingSCIESCOPUS

Nuclear Materials and Energy, vol. 21, 2019-12

Article

Evaluation of critical heat flux of ATF candidate coating materials in pool boilingSCIESCOPUS

Nuclear Engineering and Design, vol. 354, 2019-12

Article

High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environmentsSCIESCOPUS

Journal of Nuclear Materials, vol. 526, 2019-12

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