• Flow-Induced Vibration Test in the Preheater Region of a Steam Generator Tube Bundle

• Kim Beom-Shig

• Hwang Jong-Keun

• Nuclear Engineering and Technology   1997  Volume.29  No.1 85 ~ 91

• Development of the Numerical Guide for Cost-Benefit Analysis of Occupational Radiation Exposure in t...

• Sohn Ki-Yoon

• Nuclear Engineering and Technology   1997  Volume.29  No.1 78 ~ 84

• Determination of the Weighting Parameters of the LQR System for Nuclear Reactor Power Control Using ...

• Lee Yoon-Joon

• Nuclear Engineering and Technology   1997  Volume.29  No.1 68 ~ 77

• A Numerical Study on Mixing Characteristics of the Chemical Injection Tank

• Chang Keun-Sun

• Park Byeong-Ho

• Nuclear Engineering and Technology   1997  Volume.29  No.1 58 ~ 67

• An Experimental Investigation of Direct Condensation of Steam Jet in Subcooled Water

• Kim, Yeon Sik

• Chung, Moon Ki/Park, Jee Won/Chun, Moon-Hyun

• Nuclear Engineering and Technology   1997  Volume.29  No.1 45 ~ 57

• An Empirical Correlation for Critical Flow Rates of Subcooled Water Through Short Pipes with Small D...

• Park, Choon-Kyung

• Park, Jee-Won/Chung, Moon-Ki

• Nuclear Engineering and Technology   1997  Volume.29  No.1 35 ~ 44

• Expert Opinion Elicitation Process Using a Fuzzy Probability

• Yu Donghan

• Nuclear Engineering and Technology   1997  Volume.29  No.1 25 ~ 34

• Design and Evaluation of the Model Based Controller for a U-tube Steam Generator Level

• Kim Keung-Koo

• Lee Doojeong

• Nuclear Engineering and Technology   1997  Volume.29  No.1 15 ~ 24

• Tracer Concentration Contours in Grain Lattice and Grain Boundary Diffusion

• Kim Yong-Soo

• Donald R. Olander

• Nuclear Engineering and Technology   1997  Volume.29  No.1 7 ~ 14

• Assessing the Feasibility of an Accident Management Strategy Using Dynamic Reliability Methods

• Jae Moonsung

• Kim Jae-Hwan

• Nuclear Engineering and Technology   1997  Volume.29  No.1 1 ~ 6