Jaewoon Yoo

发表

Thermo-mechanical analysis of supercritical pressure light water-cooled fast reactor fuel rod by FEMAXI-6 code

Y. Oka, Y. Ishiwatari, Jie Liu, 2006 .

A Conformal mapped nodal SP3 method for hexagonal core analysis

Y. Kim, D. Hahn, C. Kim, 2009 .

Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling

Yoshiaki Oka, Yuki Ishiwatari, Jaewoon Yoo, 2006 .

Assessment of tritium effluent from Prototype Generation IV Sodium-cooled Fast Reactor

Jae-Yong Lim, T. Kim, C. Grandy, 2021 .

Numerical investigation of heat transfer in upward flows of supercritical water in circular tubes and tight fuel rod bundles

Yoshiaki Oka, Yuki Ishiwatari, Jaewoon Yoo, 2007 .

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Jin-Sik Cheon, Sung-Kyun Kim, Tae-Ho Lee, 2016 .

Alternative Applications of Homogeneous Thoria-Urania Fuel in Light Water Reactors to Enhance the Economics of the Thorium Fuel Cycle

J. Noh, J. Cho, H. Joo, 2004 .