Volume.16 No.2 July 2018

• Validation of Performance of Engineered Barriers in a Geological Repository: Review of In-Situ Experimental Approach

  Won-Jin Cho, Geon Young Kim

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.137-164

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.137

  Open abstract

• A Study on the Droplet Formation of Liquid Metal in Water-Mercury System as a Surrogate of Molten Salt-Liquid Metal System at Room Temperature

  Yong-il Kim, Byung Gi Park

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.165-172

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.165

  Open abstract

• Effect of Cetyltrimethyl Ammonium Bromide on Foam Stability and SiO₂ Separation for Decontamination Foam Application

  Mansoo Choi, Seung-Eun Kim, In-Ho Yoon, Chong-Hun Jung, Wang-Kyu Choi, Jei-Kwon Moon, Seon-Byeong Kim

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.173-182

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.173

  Open abstract

• 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

  Open abstract

• Effect of Target Material and the Neutron Spectrum on Nuclear Transmutation of ⁹⁹Tc and ¹²⁹I in Nuclear Reactors

  Seung-gu Kang, Hyun-chul Lee

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.195-202

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.195

  Open abstract

• A Study on Diffusion Approximations to Neutron Transport Boundary Conditions

  Taewan Noh

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.203-209

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.203

  Open abstract

• Nodal Transport Methods Using the Simplified Even-Parity Neutron Transport Equation

  Taewan Noh

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.211-221

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.211

  Open abstract

• Porous Media Modelling and Verification of Thermal Analysis for Inlet and Outlet Ducts of Spent Fuel Storage Cask

  Ju-Chan Lee, Kyung-Sik Bang, Woo-Seok Choi, Ki-Seog Seo, Sungho Ko

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.223-232

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.223

  Open abstract

• Evaluation of Silicon Carbide (SiC) for Deep Borehole Disposal Canister

  Minsoo LEE, Jongyoul LEE, Heuijoo CHOI, MalGoBalGaeBitNaLa YOO, Sunghoon JI

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.233-242

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.233

  Open abstract

• State-of-Arts of Primary Concrete Degradation Behaviors due to High Temperature and Radiation in Spent Fuel Dry Storage

  Jin-Seop Kim, Donghak Kook, Jong-Won Choi, Geon-Young Kim

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.243-260

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.243

  Open abstract

• Development of Novel Joint Device for a Disposal Canister in Deep Borehole Disposal

  Minsoo LEE, Jongyoul LEE, Sung-Hoon JI

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.261-270

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.261

  Open abstract

• Development Status for Commercialization of Spent Nuclear Fuel Transportation and Dry Storage System Technology

  Chang-Yeal Baeg, Chun-Hyung Cho

  Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.271-279

  DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.271

  Open abstract