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A Probabilistic Safety Assessment of a Pyro-processed Waste Repository

Youn-Myoung Lee^*, Jongtae Jeong

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.263-272

DOI:https://doi.org/10.7733/jkrws.2012.10.4.263 Download PDF Export Citation
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Studies on the Electrochemical Dissolution for the Treatment of 10 g-Scale Zircaloy-4 Cladding Hull Wastes in LiCl-KCl Molten Salts

Chang Hwa Lee^*, You Lee Lee, Min Ku Jeon, Kweon Ho Kang

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.273-280

DOI:https://doi.org/10.7733/jkrws.2012.10.4.273 Download PDF Export Citation
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Current Status of the Numerical Models for the Analysis of Coupled Thermal-Hydrological-Mechanical Behavior of the Engineered Barrier System in a High-level Waste Repository

Won-Jin Cho^*, Jin Seop Kim, Changsoo Lee and Heui-Joo Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.4 pp.281-294

DOI:https://doi.org/10.7733/jkrws.2012.10.4.281 Download PDF Export Citation
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A Deterministic Safety Assessment of a Pyro-processed Waste Repository

Youn-Myoung LEE¹⁾, Jongtae JEONG , Jongwon CHOI

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.171-188

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Design, Manufacturing, and Performance estimation of a Disposal Canister for the Ceramic Waste from Pyroprocessing

Minsoo Lee¹⁾, Heui-Joo choi, Jong-Youl Lee ,Jong-Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.209-218

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A Study on the Conceptual Development for a Deep Geological Disposal of the Radioactive Waste from Pyro-processing

Jong-Youl LEE¹⁾, Min-Soo LEE, Heui-Joo CHOI, Dae-Seok BAE, Kyeong-Soo Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.219-228

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An Evaluation on the Radiation Shielding of the Radwaste Drum Assay Facility

Young-Yong Ji, Kyung-Kil Kwak, Dae-Seok Hong and Jong-Sik Shon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.117-123

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Safety Evaluation of Radioactive Material Transport Package under Stacking Test Condition

Ju-Chan Lee, Ki-Seog Seo, Seong-Yeon Yoo

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.37-43

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The State-of-the Art of the Borehole Disposal Concept for High Level Radioactive Waste

Sung-Hoon Ji, Yong-Kwon Koh, Jong-Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.55-62

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Patent Analysis for Pyroprocessing of Spent Nuclear Fuels

Jae-Hyung Yoo, Jung-Kuk Kim, Han-Soo Lee, In-Seok Seo, Eun-ka Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.247-258

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Detennination of ¹²⁹I in simulated radioactive wastes using distiIlation technique

Ke Chon Choi,Byung Cheol Song,Sun Ho Han,Yong Joon Park,Kyuseok Song

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.141-148

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Multiple-Silo Performance Assessment Model for the Wolsong LILW Disposal Facility in Korea PHASE I: Model Development

Doo-Hyun Lim, Jee-Yeon Kim, Joo-Wan Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.99-105

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Synthetic Study on the Geological and Hydrogeological Model around KURT

Kyung Woo Park, Kyung Su Kim, Yong Kwon Koh, Jong Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.13-21

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Analysis on the International Trends in Safe Management of Very Low Level Waste Based upon Graded Approach and Their Implications

Jae Hak Cheong

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.49-62

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Study on the Geological Structure around KURT Using a Deep Borehole Investigation

Kyung Woo Park, Kyung Su Kim, Yong Kwon Koh, Jong Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.279-291

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Source Term Characterization for Structural Components in 17 x 17 KOFA Spent Fuel Assembly

Dong-Keun Cho, DongHak Kook, Heui-Joo Choi, Jongwon Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.347-353

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Decontamination Characteristics of 304 Stainless Steel Surfaces by a Q-switched Nd:YAG Laser at 532 nm

Jei-Kwon Moon, Byambatseren Baigalmaa, Hui-Jun Won, Kune-Woo Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.181-188

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A Study on the Determination of the Seasonal Heat Transfer Coefficient in KURT Under Forced Convection

윤찬훈, 권상기, 황인필, 김진

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.189-199

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Temperature Effect on the Swelling Pressure of a Domestic Compacted Bentonite Buffer

이지현, 이민수, 최희주, 최종원

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.207-213

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Study on Pre-treatment Method for Vitrification of Concentrated Wastes

조현제, 김득만, 박종길

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.221-227

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