• Benefits of the S/F Cask Impact Limiter Weldment Imperfection

• Jeong-Hoe Ku

• Ju-Chan Lee/Jong-Hun Kim/Seong-Won Park/Hyun-Soo Park

• Nuclear Engineering and Technology   2000  Volume.32  No.2 191 ~ 203

• Nonlinear Flexural Analysis of PSC Test Beams in CANDU Nuclear Power Plants

• In-Hwan BAE

• In-Kil CHOI/Jeong-Moon SEO

• Nuclear Engineering and Technology   2000  Volume.32  No.2 180 ~ 190

• Numerical Analysis of Evolution of Thermal Stratification in a Curved Piping System

• Seok Ki Choi

• Ho Yun Nam/Jong Chull Jo

• Nuclear Engineering and Technology   2000  Volume.32  No.2 169 ~ 179

• The Level Control System Design of the Nuclear Steam Generator for Robustness and Performance

• Yoon Joon Lee

• Heon Ju Lee/Kyuns Yeon Kim

• Nuclear Engineering and Technology   2000  Volume.32  No.2 157 ~ 168

• Interfacial Condensation Heat Transfer for Countercurrent Steam-Water Stratified Flow in a Circular ...

• In-Cheol Chu

• Moon Ki Chung/Seon-Oh Yu/Moon-Hyun Chun

• Nuclear Engineering and Technology   2000  Volume.32  No.2 142 ~ 156

• Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures 0.57 to 15.0...

• Se-Young Chun

• Heuns-June Chung/Sung-Deok Hong/Sun-Kyu Yang/Moon-Ki Chung

• Nuclear Engineering and Technology   2000  Volume.32  No.2 128 ~ 141

• An Experimental Study on the Mass and Energy Release for a Hot Leg Break LBLOCA During Post Blowdown

• S.J. Hong

• J.H. Kim/G.C Park

• Nuclear Engineering and Technology   2000  Volume.32  No.2 108 ~ 127

• Probabilistic Structural Integrity Assessment of a Reactor Vessel Under Pressurized Thermal Shock

• Ji-Ho Kim

• Yong-Wan Kim/Tae-Wan Kim/Hyung Huh/Jong-ln Kim

• Nuclear Engineering and Technology   2000  Volume.32  No.2 99 ~ 107