Design and Structural Safety Evaluation of the High Burn-up PWR Spent Nuclear Fuel for Storage Cask

2024-6-30

Fabrication and Characterization of Zr and Hf Containing Vitrified Forms of Radioactive Waste

2024-6-30

Dynamic Material Testing of Aged Concrete Cores From the Outer Wall of the High-Flux Advanced Neutron Application Reactor

2024-6-30

A Comparative Study on Gamma-ray Measurement and MCNP Simulation for Precise Measurement of Spent Nuclear Fuel Burnup

2024-6-30

Conceptual Designs and Evaluation of the Treatment Process of Square and Cylindrical Concrete Re-Package Drums

2024-6-30

Numerical Simulation of Rainfall Infiltration Into Disposal Cover of Performance Test Facility

2024-6-30

Corrosion Behavior of Cu−Ni Alloy Film Fabricated by Wire-fed Additive Manufacturing in Oxic Groundwater

2024-6-30

An Efficient Sulfuric Acid- and Hydrazine-based Process for Recycling Wastewater Generated From U(VI)-Contaminated Soil-Washing

2024-6-30

Irradiation Effect on Silo Dry Storage Systems for CANDU Spent Nuclear Fuel

2024-6-30

Optimal Cycle Length of MAGNOX Reactor for Weapons-Grade Plutonium Production

2024-6-30

Feasibility Study of Environmental and Geographical Data Transfer (EGDT) Device for Wide-Area Environmental Sampling in Undeclared Areas

2024-6-30

Demonstration of Heat Dissipation Performance of Copper Plate in Engineered Barrier System

2024-6-30

Assessing the Feasibility of Diver Access During Dismantling of Reactor Vessel Internals

2024-3-30

Comparative Study of Dose Evaluation of Liquid Effluent in Nuclear Power Plants for Radiological Impact on the Environment Review

2024-3-30

A Study of Immobilization Performance Requirements for Heterogeneous Radioactive Waste

2024-3-30

Evaluation of Thermal Properties for the Bentonil-WRK Bentonite

2024-3-30

Feasibility Study on Aluminum Under Laser Ablation for Corrosion Resistance in Molten Salt

2024-3-30

Galvanic Corrosion Behavior of Copper Canister

2024-3-30

Isotopic Analysis of Decay Heat Contributors From Actinides and Fission Fragments of Spent Nuclear Fuel for Intermediate- and Long-Term Storage Times

2024-3-30

Separation and Determination of Citric Acid by Ion Chromatography in Radioactive Concrete Waste

2024-3-30

Thermal Influence on Hydraulic Conductivity in Compacted Bentonite: Predictive Modeling Based on the Dry Density-Hydraulic Conductivity Relationship

2024-3-30

A Study on the Radiological Emergency Plan for Decommissioning Nuclear Power Plant

2024-3-30

Thermal Analyses of Deep Geological Disposal Cell With Heterogeneous Modeling of PLUS7 Spent Nuclear Fuel

2023-12-30

Characterization of the Purified Ca-type Bentonil-WRK Montmorillonite and Its Sorption Thermodynamics With Cs(I) and Sr(II)

2023-12-30

Design and Structural Safety Evaluation of Canister for Dry Storage System of PWR Spent Nuclear Fuels

2023-12-30

Development of a Methodology for Estimating Radioactivity Concentration of NORM Scale in Scrap Pipes Based on MCNP Simulation

2023-12-30

Design and Structural Safety Evaluation of Transfer Cask for Dry Storage System of PWR Spent Nuclear Fuel

2023-12-30

The French Underground Research Laboratory in Bure: An Essential Tool for the Development and Preparation of the French Deep Geological Disposal Facility Cigéo

2023-12-30

Comparison of Environmental Radiation Survey Analysis Results in a High Dose Rate Environment Using CZT, NaI(Tl), and LaBr<sub>3</sub>(Ce) Detectors

2023-12-30

Review of Aging Management for Concrete Silo Dry Storage Systems

2023-12-30

Assessing the Potential of Small Modular Reactors (SMRs) in Spent Nuclear Fuel Management: A Review of the Generation IV Reactor Progress

2023-12-30

Preliminary Selection of Safety-Relevant Radionuclides for Long-Term Safety Assessment of Deep Geological Disposal of Spent Nuclear Fuel in South Korea

2023-12-30

Rolling Test Simulation of Sea Transport of Spent Nuclear Fuel Under Normal Transport Conditions

2023-12-30

Numerical Modelling of Radionuclide Migration for the Underground Silo at Near-Field

2023-12-30

A Method to Estimate the Burnup Using Initial Enrichment, Cooling Time, Total Neutron Source Intensity and Gamma Source Activities in Spent Fuels

2023-9-30

Parametric Study for Structural Reinforcement Methods of Disposal Container for NPP Decommissioning Radioactive Waste

2023-9-30

Sensitivity Analysis of Thermal Parameters Affecting the Peak Cladding Temperature of Fuel Assembly

2023-9-30

Evaluation of Occupational, Facility and Environmental Radiological Data From the Centralized Radioactive Waste Management Facility in Accra, Ghana

2023-9-30

Radiation and Decommissioning Laboratory, an R&D Center for the Back-end Cycle of Nuclear Power Plants

2023-9-30

Development of Nuclear Industry Information Gathering and Analysis System and Denied Persons Information Gathering System for Preventing Illegitimate Export of Trigger List Items in Korea

2023-9-30

Thermodynamic Study of Sequential Chlorination for Spent Fuel Partitioning

2023-9-30

A Study on the Long-Term Integrity of Polymer Concrete for High Integrity Containers

2023-9-30

An Analysis of Constraints on Pyroprocessing Technology Development in ROK Under the US Nonproliferation Policy

2023-9-30

Proposal of Application Method for Concentration Averaging of Radioactive Waste in Korea by Using CA BTP of US NRC

2023-9-30

Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)

2023-9-22

Physicochemical Property of Borosilicate Glass for Rare Earth Waste From the PyroGreen Process

2023-6-30