• Analysis of Corrosion Behavior of KOFA Zircaloy-4 Cladding

• Lee Chan-Bock

• Kim Ki-Hang

• Nuclear Engineering and Technology   1998  Volume.30  No.2 173 ~ 179

• Modelling of RV Ledge Region for Dynamic Analysis of Coupled Reactor Vessel Internals and Core

• Jhung Myung-J.

• Nuclear Engineering and Technology   1998  Volume.30  No.2 164 ~ 172

• Flow Induced Material Degradation In Power Plant Secondary Systems-A Review

• Kim, I.S.

• Helm, M.Van Der/Ballinger, R.G.

• Nuclear Engineering and Technology   1998  Volume.30  No.2 148 ~ 163

• Conceptual Study for the Moderator Selection of the Cold Neutron Source Facility for HANARO

• Cho, Young-Sik

• Chang, Jonghwa/Choi, Chang-Oong

• Nuclear Engineering and Technology   1998  Volume.30  No.2 140 ~ 147

• Effect of UO©ü Powder Property and Oxygen Potential on Sintering Characteristics of UO©ü-Gd©üO©ý Fue...

• Song, Kun Woo

• Kim, Keon Sik/Yoo, Ho Sik/Jung, Youn Ho

• Nuclear Engineering and Technology   1998  Volume.30  No.2 128 ~ 139

• Analysis of Reflux Cooling in the SG U-Tubes Under Loss of RHRS During Midloop Operation with Primar...

• Son, Young-Seok

• Kim, Won-Seok/Kim, Kyung-Doo/Chung, Young-Jong/Chang, Won-Pyo

• Nuclear Engineering and Technology   1998  Volume.30  No.2 112 ~ 127

• Microstructural Properties of the Insoluble Residue in a Simulated Spent Fuel

• Kim, J. S.

• Song, B. C./Jee, K. Y./Kim, J. G./Chun, K. S.

• Nuclear Engineering and Technology   1998  Volume.30  No.2 99 ~ 111

• Three-Dimensional Seismic Analysis for Spent Fuel Storage Rack

• Lee, Gyu Mahn

• Kim, Kang Soo/Park, Keun Bae/Park, Jong Kyun

• Nuclear Engineering and Technology   1998  Volume.30  No.2 91 ~ 98

• A Feasibility Study of Seismic Isolation for Wolsong Reactor Building

• Kim, Kang Soo

• Kim, Tae Wan/Lee, Jeong Yoon

• Nuclear Engineering and Technology   1998  Volume.30  No.2 83 ~ 90