Browsing by Author "Park, Sung-Ho"
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- An Evaluation of Korean Next Generation Reactor Pressure Vessel Neutron Fluence by Monte Carlo Simulations(IASMiRT, 2001-08-12T00:00:00+00:00) Kim, Jong Kyung; Shin, Chang Ho; Park, Sung-Ho; Park, Goon-Cherl; Lee, Jae-Hun
- Prediction of Burst Pressure of Steam Generator Tube with an Axial Through Wall Crack: Finite Element Method Approach(IASMiRT, 2001-08-12T00:00:00+00:00) Yoo, One; Kang, Seon-Ye; Choi, Seog Nam; Park, Sung-Ho