A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1 von Seo, Hyung-Woo, Ryu, Gang-Woo, Na, Young-Il, Park, Chan-Geun, Son, Jin-Won, Kim, Cheon-Woo

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Proposal of weighting options for influencing factors and method of giving preference to alternatives for selecting the preliminary decommissioning strategy of Kori-1 von Jung, Hye-Jin, Seo, Hyung-Woo, Son, Jin-Won, Kim, Cheon-Woo

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Leaching behaviors and mechanisms of vitrified forms for the low-level radioactive solid wastes von Kim, Miae, Kim, Hyun Gyu, Kim, Shin, Yoon, Jang-Hee, Sung, Ji Yeong, Jin, Jong Sung, Lee, Mi-Hyun, Kim, Cheon-Woo, Heo, Jong, Hong, Kyong-Soo

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Radiation and Decommissioning Laboratory, an R&D Center for the Back-end Cycle of Nuclear Power Plants von Kim, Cheon-Woo

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The study for activation evaluation on activated structures in nuclear power plant with 40 years operation history von Dong Sohn, Hee, Soo Park, Kwang, Woong Kim, Hae, Woo Kim, Cheon, Hwan Hwang, Young, Young Yoon, Ju

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Analysis of Leaching Behavior of Simulated LILW Glasses by Using the MCC-1 Test Method von KIM, Cheon-Woo, PARK, Jong-Kil, HWANG, Tae-Won

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Physicochemical Property of Borosilicate Glass for Rare Earth Waste From the PyroGreen Process von Hwang, Young Hwan, Lee, Mi-Hyun, Kim, Cheon-Woo

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A Study on the Long-Term Integrity of Polymer Concrete for High Integrity Containers von Hwang, Young Hwan, Lee, Mi-Hyun, Hwang, Seok-Ju, Son, Jung-Kwon, Kim, Cheon-Woo, Lim, Suknam

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Development of equivalent dose assessment methodology for the lens of the eye at nuclear power plant workers von Kim, Siyoung, Son, Jungkwon, Kim, Cheon-Woo

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Enthalpies of Chromium Oxide Solution in Soda Lime Borosilicate Glass Systems von Kim, Cheon-Woo, Choi, Kwansik, Park, Jong-Kil, Shin, Sang-Woon, Song, Myung-Jae

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Analysis of Leaching Behavior of Simulated LILW Glasses by Using the MCC-1 Test Method von KIM, Cheon-Woo, PARK, Jong-Kil, HWANG, Tae-Won

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A Study on Segmentation Process of the K1 Reactor Vessel and Internals von Hwang, Young Hwan, Hwang, Seokju, Hong, Sunghoon, Park, Kwang Soo, Kim, Nam-Kyun, Jung, Deok Woon, Kim, Cheon-Woo

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Determination of a representative composition of dry active waste from Korean nuclear power plants von Park, Jin Beak, Kim, Cheon-Woo, Kim, Suk-Hoon, Kim, Ju Youl

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Fabrication and Characterization of Zr and Hf Containing Vitrified Forms of Radioactive Waste von Hwang, Young Hwan, Shin, Seong-Sik, Hong, Sunghoon, Son, Jung-Kwon, Kim, Cheon-Woo

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Level Gauge by Using the Acoustic Resonance Frequency von Jung, Sung Soo, Cho, Seung Il, Kim, Yong Tae, Kim, Cheon-Woo

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Vitrification of Combustible Dry Active Waste Generated from Korean Nuclear Power Plants von SONG, Myung-Jae, KIM, Cheon-Woo

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Conceptual Designs and Evaluation of the Treatment Process of Square and Cylindrical Concrete Re-Package Drums von Hwang, Young Hwan, Hong, Sunghoon, Shin, Seong-Sik, Hwang, Seokju, Son, Jung-Kwon, Kim, Cheon-Woo, Kim, Changgyu, Park, Kwang Soo, Lim, Taeseob, Park, Donghun

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Safety Analysis of Concrete Treatment Workers in Decommissioning of Nuclear Power Plant von Hwang, Young Hwan, Kim, Si Young, Lee, Mi-Hyun, Hong, Sang Beom, Kim, Cheon-Woo

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A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1 von Hyung-Woo Seo, Gang-Woo Ryu, Young-Il Na, Chan-Geun Park, Jin-Won Son, Cheon-Woo Kim

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Characterization of simulated Al2O3-containing nuclear waste glass von BONG KI RYU, BYUNG CHUL LEE, CHOE, Youngson, JONG RAK CHOI, PYUNG KOOK JI, CHEON WOO KIM, JONG HYUN HA, JONG KIL PARK, MYUNG JAE SONG

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