Application of R2S unstructured tetrahedral mesh method to radioactive concrete structure dismantling using AETIUS/FISPACT codes von Kim, Jong W., Cho, Jin Y., Lee, Young‐Ouk

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Semi-empirical model to determine pre- and post-neutron fission product yields and neutron multiplicity von Lee, Jounghwa, Lee, Young-Ouk, Park, Tae-Sun, Schillebeeckx, Peter, Hong, Seung-Woo

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Mass Distribution of the Fission Products of Plutonium Isotopes as Calculated by Using a Semi-empirical Model von Lee, Jounghwa, Lee, Young-Ouk, Park, Tae-Sun, Hong, Seung-Woo

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Calculation of fission product yields for uranium isotopes by using a semi-empirical model von Lee, Jounghwa, Gil, Choong-Sup, Lee, Young-Ouk, Park, Tae-Sun, Hong, Seung-Woo

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Possibilities of production of neutron-rich Md isotopes in multi-nucleon transfer reactions von Mun, Myeong-Hwan, Adamian, G. G., Antonenko, N. V., Lee, Young-Ouk

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A Deep Penetration Problem Calculation Using AETIUS:An Easy Modeling Discrete Ordinates Ṯransport Code UsIng Unstructured Tetrahedral Mesh, Shared Memory Parallel von KIM, Jong Woon, LEE, Young-Ouk

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Validation of Thermal Neutron Scattering Cross Sections for Heavy Water based on Molecular Dynamics Simulation von Hyun, Haelee, Kim, Do Heon, Lee, Young-Ouk

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AETIUS solutions for Kobayashi 3D benchmarks with the first collision source method on the volume source and unstructured tetrahedral mesh von Kim, Jong Woon, Lee, Young-Ouk

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Measurement of production cross sections in proton induced reactions on natural zirconium von Yang, Sung-Chul, Jung, Myung Hwan, Kim, Guinyun, Lee, Young-Ouk

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Shutdown dose rate analysis with unstructured tetrahedral element based R2S method using deterministic transport solver AETIUS von Kim, Jong Woon, Lee, Cheol Woo, Lee, Young-Ouk

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Study on collimator design for Neutron Science Facility of RAON accelerator complex von Lee, Eunjoong, Lee, Cheol-Woo, Yang, Sung-Chul, Lee, Young-Ouk, Cho, Gyuseong

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Production cross sections of proton-induced reactions on yttrium von Yang, Sung-Chul, Song, Tae-Yung, Lee, Young-Ouk, Kim, Guinyun

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Effect of graphite reflector on activation of fusion breeding blanket von Lee, Cheol Woo, Lee, Young-Ouk, Lee, Dong Won, Cho, Seungyon, Ahn, Mu-Young

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Development of discrete ordinates code supporting unstructured tetrahedral mesh and applied in neutronics analysis for the Korea Helium Cooled Ceramic Reflector Test Blanket Module von Kim, Jong Woon, Lee, Cheol Woo, Lee, Young-Ouk, Lee, Dong-Won, Cho, Seungyon

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Measurement of excitation functions of the natAg(α,x) reactions up to 45 MeV von Shahid, Muhammad, Kim, Kwangsoo, Kim, Guinyun, Naik, Haladhara, Zaman, Muhammad, Lee, Young-Ouk, Cho, Young-Sik

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Nuclear Data Evaluation for Proton-Induced Reactions of Aluminum based on the Talys Code von Kim, Hyeong Il, Lee, Young-Ouk

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Analysis of the Neutron Thermalization in an Accelerator Room von Lee, Cheol Woo, Lee, Young-Ouk, Cho, Young-Sik, Ahn, Sohyun

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Analysis of charged particle induced reactions for beam monitor applications von Surendra Babu, K., Lee, Young-Ouk, Mukherjee, S.

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The neutron transmission of natFe, 197Au and natW von Beyer, Roland, Junghans, Arnd R., Schillebeeckx, Peter, Sirakov, Ivan, Song, Tae-Yung, Bemmerer, Daniel, Capote, Roberto, Ferrari, Anna, Hartmann, Andreas, Hannaske, Ronald, Heyse, Jan, Il Kim, Hyeon, Woon Kim, Jong, Kögler, Toni, Woo Lee, Cheol, Lee, Young-Ouk, Massarczyk, Ralph, Müller, Stefan E., Reinhardt, Tobias P., Röder, Marko, Schmidt, Konrad, Schwengner, Ronald, Szücs, Tamás, Takács, Marcell P., Wagner, Andreas, Wagner, Louis, Yang, Sung-Chul

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Neutron science facility for neutron time-of-flight and fission cross-section measurements at RAON von Kim, Jae Cheon, Kim, Gi Dong, Son, Jae Bum, Lee, Cheol Woo, Lee, Young-Ouk

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