Browsing by Author "Lee, Jae-Hun"
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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
