Internal Dose Assessment of Worker by Radioactive Aerosol Generated During Mechanical Cutting of Radioactive Concrete

Jihye Park, Wonseok Yang, Nakkyu Chae, Minho Lee, Sungyeol Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.2 pp.157-167

DOI:https://doi.org/10.7733/jnfcwt.2020.18.2.157 Download PDF Export Citation

Comparison of Compton Image Reconstruction Algorithms for Estimation of Internal Radioactivity Distribution in Concrete Waste During Decommissioning of Nuclear Power Plant

Tae-Woong Lee, Seong-Min Jo, Chang-Yeon Yoon, Nak-Jeom Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.2 pp.217-225

DOI:https://doi.org/10.7733/jnfcwt.2020.18.2.217 Download PDF Export Citation

Inventory Estimation of ³⁶Cl and ⁴¹Ca in Concrete of Kori Unit 1

Mee Jang, Jong Myoung Lim, Hyun Chul Kim, Chang-Jong Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.1 pp.121-126

DOI:https://doi.org/10.7733/jnfcwt.2019.17.1.121 Download PDF Export Citation

Screening Assessment of Radiological Effect From Clearance of Decommissioning Concrete Waste Based Upon Recycling Framework of Construction Waste in Korea

Kun-Su Lim, Jae Hak Cheong, Joo Ho Whang

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.4 pp.441-454

DOI:https://doi.org/10.7733/jnfcwt.2018.16.4.441 Download PDF Export Citation

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 Download PDF Export Citation

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 Download PDF Export Citation

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 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 Dismantling and Disposal Strategy of a Biological Shield for Minimization of Radioactive Concrete Waste During Decommissioning of a Nuclear Power Plant

Cheol-Seung Cheon, Chang-Lak Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.355-367

DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.355 Download PDF Export Citation

Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions

Tae-Man Kim, Ho-Seog Dho, Chun-Hyung Cho, Jae-Hun Ko

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.391-402

DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.391 Download PDF Export Citation

Evaluation of Canister Weld Flaw Depth for Concrete Storage Cask

Tae-Chul Moon, Chun-Hyung Cho, Sung-Hun Jung, Young-Oh Lee, In-su Jung

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.1 pp.91-99

DOI:https://doi.org/10.7733/jnfcwt.2017.15.1.91 Download PDF Export Citation

Aggregate Effects on γ-ray Shielding Characteristic and Compressive Strength of Concrete

Jeong-Hwan Oh, Young-Bum Mun, Jae-Hyung Lee, Hyun-Kook Choi, Sooseok Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.4 pp.357-365

DOI:https://doi.org/10.7733/jnfcwt.2016.14.4.357 Download PDF Export Citation

Service-life Prediction of Reinforced Concrete Structures in Subsurface Environment

Ki-jung Kwon, Haeryong Jung, Joo-Wan Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.1 pp.11-19

DOI:https://doi.org/10.7733/jnfcwt.2016.14.1.11 Download PDF Export Citation

Gas Migration in Low- and Intermediate-Level Waste (LILW) Disposal Facility in Korea

Jaechul Ha, Jeong-Hwan Lee, Haeryong Jung, Juyub Kim, Juyoul Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.4 pp.267-274

DOI:https://doi.org/10.7733/jnfcwt.2014.12.4.267 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

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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Separation of Radionuclide from Dismantled Concrete Waste

민병연, 박정우, 최왕규, 이근우

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.2 pp.79-86

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Residual Radioactivity Investigation & Radiological Assessments for Self-disposal of Concrete Waste in Nuclear Fuel Processing Facility

설중군, 류재봉, 조석주, 유성현, 송정호, 백훈, 김성환, 신진성, 박현균

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.91-101

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Radioactivity Analysis of 55Fe and 63Ni in Dismantled Concrete

Mun Ja Kang, Kun Ho Chung, Sang Bum Hong, Geun Sik Choi, Chang Woo Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.19-27

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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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