• Analysis of High Burnup Fuel Behavior Under Rod Ejection Accident in the Westinghouse-Designed 950 M...

• Lee, Chan Bock

• Cho, Byung Oh/Kim, Oh Hwan/Kim, Young Baik/Chung, Jin Gon

• Nuclear Engineering and Technology   1998  Volume.30  No.3 273 ~ 286

• A Review of Pressure Tube Failure Accident in the CANDU Reactor and Methods for Improving Reactor Pe...

• Yoo Ho-Sik

• Chung Jin-Gon

• Nuclear Engineering and Technology   1998  Volume.30  No.3 262 ~ 272

• A Study on Validation of Variable Aperture Channel Model

• Keum, D.K.

• Hahn, P.S./Vandergraaf, T.T.

• Nuclear Engineering and Technology   1998  Volume.30  No.3 245 ~ 261

• Use of MAAP in Generating Accident Source Term Parameters

• Kim, Jong Wok

• Yun, Joeng Ik/Kang, Chang Sun

• Nuclear Engineering and Technology   1998  Volume.30  No.3 235 ~ 244

• On-line Estimation of DNB Protection Limit via a Fuzzy Neural Network

• Na Man-Gyun

• Nuclear Engineering and Technology   1998  Volume.30  No.3 222 ~ 234

• Structural Integrity of PWR Fuel Assembly for Earthquake

• Jhung M.-J.

• Nuclear Engineering and Technology   1998  Volume.30  No.3 212 ~ 221

• A Study on the Improvement of Stress Field Analysis in a Domain Composed of Dissimilar Materials

• Song Kee-Nam

• Lee Jin-Seok

• Nuclear Engineering and Technology   1998  Volume.30  No.3 202 ~ 211

• Application of Dynamic Reliability Analysis Method to the CANDU Pressurizer System

• Lee Sook-Hyung

• Oh Se-Ki

• Nuclear Engineering and Technology   1998  Volume.30  No.3 194 ~ 201

• Improvement of Liquid Droplet Entrainment Model in the COBRA-TF Code

• Ha, Kwi-Seok

• Jeong, Jae-Jun/Sim, Suk Ku

• Nuclear Engineering and Technology   1998  Volume.30  No.3 181 ~ 193