Key Metrics
CiteScore 

0.7
SJR 

Q4Fuel Technology

SNIP 

0.43
Recommended pre-submission checks
Powered by 

Topics Covered on Journal of Nuclear Fuel Cycle and Waste Technology
Journal of Nuclear Fuel Cycle and Waste Technology Journal Specifications
Indexed in the following public directories
Web of Science
Scopus
DOAJ
SJR
| Overview | |
| Publisher | KOREAN RADIOACTIVE WASTE SOC (KRS) |
| Language | English,Korean |
| Frequency | Quarterly |
| Article Processing Charges | KRW 300000 |
| Publication Time | 20 |
| Editorial Review Process | Anonymous peer review |
| General Details | |
| Publication Details | |
| Other charges | Visit website |
| Publication Time | 20 |
| Editorial Review Detail | |
| Information for authors | |
| Author instructions | Visit website |
| Deposit Policy | Sherpa/Romeo |
| License type | CC BY-NC |
| OA statement | Visit website |
View less
Planning to publish in Journal of Nuclear Fuel Cycle and Waste Technology ?
Upload your Manuscript to get
- Degree of match
- Common matching concepts
- Additional journal recommendations

Recently Published Papers in Journal of Nuclear Fuel Cycle and Waste Technology
A Framework for Fuel Damage Ratio Calculation in Spent Nuclear Fuel Transportation
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Comparative Effects of Organic and Inorganic Ligands on Uranium Release From Uranophane Mineral
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
The Current Status of Liquid Fuel and Material Technology Development for Chloride-Based Molten Salt Reactors (MSRs) at KAERI Part I. Liquid Fuel Fabrication and Natural Convection Loop Operation for Corrosion Characteristics
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Representative Sampling-applied Nuclear Material Accountancy for the Headend Process of Pyro-Processing
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Effects of Thermal Treatment at 105°C and Conditions of Injected Water Pressure on Swelling and Hydraulic Conductivity of Ca-Bentonite Buffer Materials
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Evaluation of Uranium-Removal Characteristics From Soil-Washed Wastewater Using Precipitation Methods
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
A Framework for Fuel Damage Ratio Calculation in Spent Nuclear Fuel Transportation
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Comparative Effects of Organic and Inorganic Ligands on Uranium Release From Uranophane Mineral
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
The Current Status of Liquid Fuel and Material Technology Development for Chloride-Based Molten Salt Reactors (MSRs) at KAERI Part I. Liquid Fuel Fabrication and Natural Convection Loop Operation for Corrosion Characteristics
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Representative Sampling-applied Nuclear Material Accountancy for the Headend Process of Pyro-Processing
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Effects of Thermal Treatment at 105°C and Conditions of Injected Water Pressure on Swelling and Hydraulic Conductivity of Ca-Bentonite Buffer Materials
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Evaluation of Uranium-Removal Characteristics From Soil-Washed Wastewater Using Precipitation Methods
- 30 Mar 2025
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)