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Scaling Up Fabrication of UO2 Porous Pellet With a Simulated Spent Fuel Composition
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.343-353
DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.343 Download PDF Export Citation
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.2 pp.113-122
DOI:https://doi.org/10.7733/jnfcwt.2015.13.2.113 Download PDF Export Citation
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Evaluation of 14C Behavior Charateristic in Reactor Coolant from Korean PWR NPP’s
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.1-7
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Preliminary Study on the Development of Alternative Methods for the Treatment of TRISO Fuels
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.201-211
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Sample pre-treatment for measurement of 129I in radwastes
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.49-56
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Solidification of Molten Salt Waste by Gel-Route Pre-treatment
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.57-65
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Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.4 pp.231-238
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