Jun‐Hwa Hong

Application of intercritical heat treatment to improve toughness of SA508 Cl.3 reactor pressure vessel steel

Y. S. Ahn, Hong-Deok Kim, Thak‐Sang Byun et al. · Nuclear Engineering and Design · 1999 · 68 citations

Materials Science, Engineering, Corrosion +6

Evaluation of thermal recovery of neutron-irradiated SA508-3 steel using magnetic property measurements

Duck-Gun Park, Jun‐Hwa Hong, In-Sup Kim et al. · Journal of Materials Science · 1997 · 27 citations

Calculation of α/γ equilibria in SA508 grade 3 steels for intercritical heat treatment

Byeong‐Joo Lee, Hong-Deok Kim, Jun‐Hwa Hong · Metallurgical and Materials Transactions A · 1998 · 22 citations

Engineering, Corrosion, Mechanical Engineering +7

Master curve techniques to evaluate an irradiation embrittlement of nuclear reactor pressure vessels for a long-term operation

Bong‐Sang Lee, Min-Chul Kim, Maan-Won Kim et al. · International Journal of Pressure Vessels and Piping · 2007 · 18 citations

Engineering, Long-term Operation, Irradiation Embrittlement +6

The Effect of BCC-Cu Precipitation on Magnetism in Thermally Aged Fe-1wt.%Cu Model Alloys

Yasuhiro Kamada, Duck-Gun Park, S. Takahashi et al. · IEEE Transactions on Magnetics · 2007 · 17 citations

Materials Engineering, Materials Science, Ferromagnetism +13