Characterization of Cement Solidification for Enhancement of Cesium Leaching Resistance

Gi Yong Kim, Won-Hyuk Jang, Sung-Chan Jang, Junhyuck Im, Dae Seok Hong, Chel Gyo Seo, Jong Sik Shon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.183-193

DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.183 Download PDF Export Citation

Characteristics of Solidified Cement of Electrokinetically Decontaminated Soil and Concrete Waste

Daeseo Koo, Hyun-Hee Sung, Sang Bum Hong, Bum Kyoung Seo

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.1 pp.83-91

DOI:https://doi.org/10.7733/jnfcwt.2018.16.1.83 Download PDF Export Citation

The Corrosion Properties of Zr-Cr-NM Alloy Metallic Waste Form for Long-term Disposal

Seungyoub Han, Seon Ah Jang, Hee-Chul Eun, Jung-Hoon Choi, Ki Rak Lee, Hwan Seo Park, Do-Hee Ahn

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.2 pp.125-133

DOI:https://doi.org/10.7733/jnfcwt.2017.15.2.125 Download PDF Export Citation

Dechlorination/Solidification of LiCl Waste by Using a Synthetic Inorganic Composite with Different Compositions

Na-Young Kim, In Hak Cho, Hwan-Seo Park, Do-Hee Ahn

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.3 pp.211-221

DOI:https://doi.org/10.7733/jnfcwt.2016.14.3.211 Download PDF Export Citation

Characterization of Cement Waste Form for Final Disposal of Decommissioned Concrete Waste

Doo Seong Hwang^*, Yoon Ji Lee, Ki Won Lee, Gyeong Hwan Jeong, Jei Kwon Moon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.11 No.4 pp.271-280

DOI:https://doi.org/10.7733/jnfcwt-k.2013.11.4.271 Download PDF Export Citation

A Study on Wasteform Properties of Spent Salt Treated with Zeolite and SAP

Hwan-young Kim, Hwan-Seo Park, Kweon-Ho Kang, Byung-gil Ahn, In-Tae Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.2 pp.99-105

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Measurement of the Radiolysis Gases Generated in Several Waste Forms by External Irradiation

Kyung-Kil Kwak, Young-Gerl Ryue, Ki-Hong Kim, Whan-Gyeong Je, Dong-Ho Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.345-352

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Evaluation of Chemical Durability of Vitrified Forms for Simulated Radioactive Waste Using Product Consistency Test(PCT) and Vapor Hydration Test(VHT)

Cheon-Woo Kim, Ji-Yean Kim, Sung-Jun Maeng, Jong-Kil Park, Tae-Won Hwang

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.227-234

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Determination of Forward Dissolution Rate of Glass by a Single-Pass Flow-Through Test

Seung Soo Kim, Kwan Sik Chun, Jong-won Choi, Sung Ki Kim, Pil-Soo Hahn

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.335-340

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Identification of Uranium Species Released from the Waste Glass in Contact with Bentonite

Seung Soo Kim, Kwan-Sik Chun, Chul-Hyung Kang, Phil-Su Han, Jong-won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.177-181

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Solidification of Molten Salt Waste by Gel-Route Pre-treatment

Hwan-Seo Park, In-Tae Kim, Hwan-Young Kim, Seung-Kon Ryu, Joon-Hyung Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.57-65

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Comparative Evaluation of Various Standard Methods in Leaching Test of Radioactive Waste Form

Ki-Hong Kim, Young-Gerl Ryu, Kyung-Ki Chung, Kwon-Pyo Hong, Nak-Hee Lee, Heon Kim, Yi-Yeong Jeong, Duck-Joon Koh

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.1 No.1 pp.93-103

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