Radioactivity release from the Fukushima accident and its consequences: A review von Koo, Yang-Hyun, Yang, Yong-Sik, Song, Kun-Woo

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Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage von Hong, Jong-Dae, Yang, Yong-Sik, Kook, Donghak

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Rod internal pressure of spent nuclear fuel and its effects on cladding degradation during dry storage von Kim, Ju-Seong, Hong, Jong-Dae, Yang, Yong-Sik, Kook, Dong-Hak

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Synthesis of PA12/functionalized GNP nanocomposite powders for the selective laser sintering process von Kim, Hyo Chan, Hahn, H Thomas, Yang, Yong Sik

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Delayed hydride cracking assessment of PWR spent fuel during dry storage von Hong, Jong-Dae, Kim, Hyo-Chan, Kim, Ju-Seong, Yang, Yong-Sik, Kook, Dong-Hak

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3D finite element analysis of a nuclear fuel rod with gap elements between the pellet and the cladding von Kang, Chang-Hak, Lee, Sung-Uk, Yang, Dong-Yol, Kim, Hyo-Chan, Yang, Yong-Sik

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Evaluation of a Dual-Cooled Annular Fuel Heat Split and Temperature Distribution von YANG, Yong Sik, SHIN, Chang Hwan, CHUN, Tae Hyun, SONG, Kun Woo

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Implementation of effective-stress-function algorithm for nuclear fuel performance code von Kim, Hyo-Chan, Yang, Yong-Sik, Koo, Yang-Hyun

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Areas of improvement in FRAPCON and FRAPTRAN codes for applications to fuels with cladding material change von Park, Ju Yeop, Kang, Sarah, Baek, Kyunglok, Kim, Seulbeen, Yang, Yong Sik

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Hoop strength and ductility evaluation of irradiated fuel cladding von Kim, Sun-Ki, Bang, Je-Geon, Kim, Dae-Ho, Lim, Ik-Sung, Yang, Yong-Sik, Song, Kun-Woo, Kim, Do-Sik

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Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating von Jeong, Eun, Jo, Yunki, Shin, ChangHwan, Yang, Yong-Sik, Kim, Jae-Yong, Lee, Deokjung

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Mechanical property evaluation of high burn-up nuclear fuel cladding using the ring tensile test von Kim, Sun-Ki, Bang, Je-Geon, Kim, Dae-Ho, Yang, Yong-Sik, Song, Kun-Woo, Kim, Do-Sik

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Development of NUFORM3D module with FRAPCON3.4 for simulation of pellet-cladding mechanical interaction von Kim, Hyo Chan, Seo, Sang Kyu, Lee, Sung Uk, Yang, Yong Sik

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Multidimensional gap conductance model for thermo-mechanical simulation of LWR fuel behavior using a virtual link element von Kim, Hyo Chan, Yang, Yong Sik, Koo, Yang Hyun

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A New Mechanistic and Engineering Fission Gas Release Model for a Uranium Dioxide Fuel von LEE, Chan Bock, YANG, Yong Sik, KIM, Dae Ho, KIM, Sun Ki, BANG, Je Geun

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Gas releases and rod internal pressure of BN-added UO 2 fuel von Jeong, Gwan Yoon, Yang, Yong Sik, Sohn, Dong-Seong

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Springback adjustment for multi-point forming of thick plates in shipbuilding von Hwang, Se Yun, Lee, Jang Hyun, Yang, Yong Sik, Yoo, Mi Ji

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Gas releases and rod internal pressure of BN-added UO2 fuel von Jeong, Gwan Yoon, Yang, Yong Sik, Sohn, Dong-Seong

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Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage von Hong, Jong-Dae, Yang, Yong-Sik, Kook, Donghak

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Evaluation of a Dual-Cooled Annular Fuel Heat Split and Temperature Distribution von YANG, Yong Sik, SHIN, Chang Hwan, CHUN, Tae Hyun, SONG, Kun Woo

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