Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor by W. F. G. van Rooijen, J. L. Kloosterman

“…The paper ends with some recommendations for future research in this promising area of the nuclear fuel cycle.…”
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First principle investigation of Cr doping effect on the stability of NiFe2O4 by Tianhao Rui, Yulin Lan, Congyi Li, Haibin Zhang, Xiaojing Liu

“…Recent experimental studies showed that Cr impurity may affect the formation and growth of NiFe2O4-rich deposit on Cr-coated nuclear fuel, demonstrating a promising solution to inhibit the growth of CRUD. …”
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Study of an ADS Loaded with Thorium and Reprocessed Fuel by Graiciany de Paula Barros, Claubia Pereira, Maria A. F. Veloso, Antonella L. Costa

“…The aim of this paper is to investigate the nuclear fuel evolution and the neutronic parameters of a lead-cooled accelerator-driven system used for fuel breeding. …”
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Evaluation of anion exchange resin for sorption of selenium (IV) from aqueous solutions by A. El-Tantawy, E. M. Abu Elgoud, S. E. A. Sharaf El-Deen

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Conceptual safeguards method proposal for milling facilities based on nuclear isotopic ratios in uranium mill tailings by Danwoo Ko, Seunguk Cheon, Jiyoung Kim, Seungmin Lee, Seung Min Woo

“…There is an argument that the Comprehensive Safeguards Agreement (CSA) should be applied to the milling process, which is the first stage of nuclear fuel cycle, to reduce the possibility of nuclear proliferation. …”
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Advanced Measuring (Instrumentation) Methods for Nuclear Installations: A Review by Wang Qiu-kuan, Lin Chang-hua, Yang Yan

“…The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. …”
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Effect of Weld Properties on the Crush Strength of the PWR Spacer Grid by Kee-nam Song, Sang-hoon Lee

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Projected Salt Waste Production from a Commercial Pyroprocessing Facility by Michael F. Simpson

“…Pyroprocessing of used nuclear fuel inevitably produces salt waste from electrorefining and/or oxide reduction unit operations. …”
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Electrochemical Behaviour of Actinides and Fission Products in Room-Temperature Ionic Liquids by K. A. Venkatesan, Ch. Jagadeeswara Rao, K. Nagarajan, P. R. Vasudeva Rao

“…In the recent past, room-temperature ionic liquids (RTILs) are being explored for possible applications in nuclear fuel cycle. RTILs are being studied as an alternative to the diluent, n-dodecane (n-DD), in aqueous reprocessing and as possible substitute to high-temperature molten salts in nonaqueous reprocessing applications. …”
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International cooperation in the sphere of peaceful uses of nuclear energy as a resolution of energy supply and nuclear proliferation problems by M. V. Zharkih

“…The comparative analysis of the two large-scale initiatives in the field ofmultilateral approaches to the nuclear fuel cycle – these are the Russian initiative on the development of the Global infrastructure of nuclear energy and the American Global nuclear energy partnership –made in the article discloses the main principles of work of the abovementioned mechanisms of interaction as well as their advantages and disadvantages. …”
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Simulation of the Thermal Conditions of Cask with Fuel Assemblies of BN-350 Reactor for Dry Storage by Ye. T. Koyanbayev, M. K. Skakov, D. A. Ganovichev, Ye. A. Martynenko, A. A. Sitnikov

“…As a result of the calculated studies, the parameters of SNF (spent nuclear fuel) storage are determined, under which the fuel temperatures will have minimum and maximum values.…”
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Electrochemical Behavior of CsI in LiCl Molten Salt by Sung-Wook Kim, Sang-Kwon Lee, Min Ku Jeon, Eun-Young Choi

“…The electrochemical behavior of CsI in LiCl molten salt was investigated to identify its impact on the electrolytic oxide reduction of oxide-phase spent nuclear fuels by combined electrolysis and cyclic voltammetry experiments of LiCl-CsI in comparison with LiCl, LiCl-CsCl, and LiCl-LiI. …”
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Effect of Deposit on the Evaporation Rate of Adhered Salt in Uranium Dendrite by Sang Woon Kwon, Si Woo Park, Sung Jai Lee

“…Moreover, it is very important to increase the throughput of the salt separation system due to the high uranium content of the spent nuclear fuel and high salt fraction of uranium dendrites. …”
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The Effect of Regional Industrial Restructuring on the Resource Environmental Carrying Capacity in Jingjiang City, Jiangsu Province, China by Yunlong Bi, Yi Hu, Xiaoli Xu, Fangqu Niu

“…The results also show that the RECC with the development of the petroleum, coking, and nuclear fuel processing products industry can maximize the RECC of Jingjiang. …”
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Boiling Heat Transfer and Critical Heat Flux Enhancement Using Electrophoretic Deposition of SiO2 Nanofluid by Aref Rahimian, Hosein Kazeminejad, Hosein Khalafi, Azam Akhavan, Seyed Mohammad Mirvakili

“…However, because of the setup simplicity, the shape independency, the particle-coating uniformity, and thickness controllability, the EPD technique can be an appropriate option for modification of the surface and coating on the nuclear fuel cladding.…”
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Transmutation Strategy Using Thorium-Reprocessed Fuel ADS for Future Reactors in Vietnam by Thanh Mai Vu, Takanori Kitada

“…Nevertheless, spent nuclear fuel from nuclear power plants is the source of radiotoxic and proliferation risk. …”
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CFD Turbulence Study of PWR Spacer-Grids in a Rod Bundle by C. Peña-Monferrer, J. L. Muñoz-Cobo, S. Chiva

“…Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow dynamics and heat transfer phenomena along the fuel rods. …”
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Thermodynamic study on the separation of strontium and barium from LWR spent fuel by Jin-Mok Hur, Jungho Hur, Yung-Zun Cho, Chang Hwa Lee

“…Process flows were developed for treating spent nuclear fuel by heating it at high temperatures to remove volatile nuclides, followed by chlorination with a chlorinating agent. …”
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Flowsheets for the Validation of the Reference AmSEL System by Vanel Vincent, Wilden Andreas, Modolo Giuseppe, Geist Andreas, Montuir Marc

“…Recycling americium (Am) from spent nuclear fuels is an important option considered for the future nuclear fuel cycle as americium is the main contributor to the long-term radiotoxicity and heat power of the ultimate waste. …”
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Modified Steam-Turbine Rankine Cycle without Rejection of the Cycle Condensation Heat, Driven by a Wet-Vapor-Region Thermocompressor by Branko Stanković

“…The concept can be applied to steam-turbine-cycle power-plants fueled by: coal or solid/liquid/gaseous fuel, waste heat, nuclear fuel (used by boiling water reactors, pressurized water reactors, pressurized heavy-water reactors, gas-cooled reactors, molten salt reactors or liquid-metal-cooled fast reactors) or renewable energy sources (Solar energy, biomass, geothermal). …”
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