Controlled Conversion of Sodium Metal From Nuclear Systems to Sodium Chloride

Steven Herrmann, Haiyan Zhao, Meng Shi, Michael Patterson

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.2 pp.233-241

DOI:https://doi.org/10.7733/jnfcwt.2021.19.2.233 Download PDF Export Citation

Trends in Technology Development for the Treatment of Radioactive Concrete Waste

Keun-Young Lee, Maengkyo Oh, Jimin Kim, Eil-Hee Lee, Ik-Soo Kim, Kwang-Wook Kim, Dong-Yong Chung, Bum-Kyoung Seo

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.1 pp.93-105

DOI:https://doi.org/10.7733/jnfcwt.2018.16.1.93 Download PDF Export Citation

The Effects of Impurity Composition and Concentration in Reactor Structure Material on Neutron Activation Inventory in Pressurized Water Reactor

Gil Yong Cha, Soon Young Kim, Jae Min Lee, Yong Soo Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.2 pp.91-100

DOI:https://doi.org/10.7733/jnfcwt.2016.14.2.91 Download PDF Export Citation

Removal of Cs by Adsorption with IE911 (Crystalline Silicotitanate) from High-Radioactive Seawater Waste

Eil-Hee Lee, Keun-Young Lee, Kwang-Wook Kim, Ik-Soo Kim, Dong-Yong Chung, Jei-Kwon Moon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.3 pp.171-180

DOI:https://doi.org/10.7733/jnfcwt.2015.13.3.171 Download PDF Export Citation

A Study on Radioactive Source-term Assessment Method for Decommissioning PWR Primary System

Jong Soon Song, Hyun-Min Kim, Sang-Heon Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.2 pp.153-164

DOI:https://doi.org/10.7733/jnfcwt.2014.12.2.153 Download PDF Export Citation

Spatial Distributions of 3H and 14C in the Shielding Concrete of KRR-2

Sang Bum Hong, Hee Reyoung Kim, Kun Ho Chung, Mun Ja Kang, Gyeong Hwan Jeong, Un Soo Chung, Jin Ho Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.329-334

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Estimation of Radioactive Inventory for a major component of Reactor in Decommissioning

Hak-soo Kim, Ki-doo Kang, Kyoung-doek Kim, Chan-Woo Jeong

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.69-75

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