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A Study on Diffusion Approximations to Neutron Transport Boundary Conditions
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 Download PDF Export Citation
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Nodal Transport Methods Using the Simplified Even-Parity Neutron Transport Equation
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 Download PDF Export Citation
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External Cost Assessment for Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.4 pp.243-251
DOI:https://doi.org/10.7733/jnfcwt.2015.13.4.243 Download PDF Export Citation
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Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.219-230
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Multilateral Approaches to the Back-end of the Nuclear Fuel Cycle: Challenges and Possibilities
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.269-277
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Assessment of Potential Impacts of the Proposals for Multilateralization of Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.339-346
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A Conceptual Design Study for a Spent Fuel Pyroprocessing Facility of a Demonstration Scale
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.233-244
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Uncertainty Cases in Economic Evaluation of Back-End Nuclear Fuel Cycle
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.141-145
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.283-295
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.339-350
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