The Experts below are selected from a list of 20523 Experts worldwide ranked by ideXlab platform
Xiaogui Feng - One of the best experts on this subject based on the ideXlab platform.
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highly efficient and selective dissolution separation of fission products by an ionic liquid hbet tf2n a new approach to Spent Nuclear Fuel recycling
Inorganic Chemistry, 2019Co-Authors: Qinggang Huang, Jieru Wang, Desheng Chen, Chao Xu, Xiaogui FengAbstract:Here, we propose the use of carboxyl-functionalized ionic liquid, [Hbet][Tf2N], to separate the fission products from Spent Nuclear Fuels. This innovative method allows the selective dissolution of neutron poisons, lanthanides oxide, as well as some fission products with high yield, leaving most of the UO2 matrix and minor actinides behind in the Spent Nuclear Fuel and accomplishing the actinides recovery as a group. Water-saturated [Hbet][Tf2N] can dissolve lanthanides oxide from simulated Spent Nuclear Fuel with a dissolution ratio of 100% at 40 °C. However, the dissolution of uranium is almost negligible (<1%) under the same conditions. This big difference in dissolution provides a novel separation approach to Spent Nuclear Fuel recycling and may open new perspectives for Spent Nuclear Fuel reprocessing. The recovery of Nd and U from metal-loaded ionic liquids and the recyclability of the ionic liquid [Hbet][Tf2N] have also been investigated. Furthermore, a U/x value related to the lattice energy U of ...
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Highly Efficient and Selective Dissolution Separation of Fission Products by an Ionic Liquid [Hbet][Tf2N]: A New Approach to Spent Nuclear Fuel Recycling
2018Co-Authors: Fang-li Fan, Qinggang Huang, Jieru Wang, Desheng Chen, Zhi Qin, Shi-wei Cao, Cun-min Tan, Xiao-jie Yin, Xiaogui FengAbstract:Here, we propose the use of carboxyl-functionalized ionic liquid, [Hbet][Tf2N], to separate the fission products from Spent Nuclear Fuels. This innovative method allows the selective dissolution of neutron poisons, lanthanides oxide, as well as some fission products with high yield, leaving most of the UO2 matrix and minor actinides behind in the Spent Nuclear Fuel and accomplishing the actinides recovery as a group. Water-saturated [Hbet][Tf2N] can dissolve lanthanides oxide from simulated Spent Nuclear Fuel with a dissolution ratio of 100% at 40 °C. However, the dissolution of uranium is almost negligible (
Qinggang Huang - One of the best experts on this subject based on the ideXlab platform.
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highly efficient and selective dissolution separation of fission products by an ionic liquid hbet tf2n a new approach to Spent Nuclear Fuel recycling
Inorganic Chemistry, 2019Co-Authors: Qinggang Huang, Jieru Wang, Desheng Chen, Chao Xu, Xiaogui FengAbstract:Here, we propose the use of carboxyl-functionalized ionic liquid, [Hbet][Tf2N], to separate the fission products from Spent Nuclear Fuels. This innovative method allows the selective dissolution of neutron poisons, lanthanides oxide, as well as some fission products with high yield, leaving most of the UO2 matrix and minor actinides behind in the Spent Nuclear Fuel and accomplishing the actinides recovery as a group. Water-saturated [Hbet][Tf2N] can dissolve lanthanides oxide from simulated Spent Nuclear Fuel with a dissolution ratio of 100% at 40 °C. However, the dissolution of uranium is almost negligible (<1%) under the same conditions. This big difference in dissolution provides a novel separation approach to Spent Nuclear Fuel recycling and may open new perspectives for Spent Nuclear Fuel reprocessing. The recovery of Nd and U from metal-loaded ionic liquids and the recyclability of the ionic liquid [Hbet][Tf2N] have also been investigated. Furthermore, a U/x value related to the lattice energy U of ...
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Highly Efficient and Selective Dissolution Separation of Fission Products by an Ionic Liquid [Hbet][Tf2N]: A New Approach to Spent Nuclear Fuel Recycling
2018Co-Authors: Fang-li Fan, Qinggang Huang, Jieru Wang, Desheng Chen, Zhi Qin, Shi-wei Cao, Cun-min Tan, Xiao-jie Yin, Xiaogui FengAbstract:Here, we propose the use of carboxyl-functionalized ionic liquid, [Hbet][Tf2N], to separate the fission products from Spent Nuclear Fuels. This innovative method allows the selective dissolution of neutron poisons, lanthanides oxide, as well as some fission products with high yield, leaving most of the UO2 matrix and minor actinides behind in the Spent Nuclear Fuel and accomplishing the actinides recovery as a group. Water-saturated [Hbet][Tf2N] can dissolve lanthanides oxide from simulated Spent Nuclear Fuel with a dissolution ratio of 100% at 40 °C. However, the dissolution of uranium is almost negligible (
Rodney C. Ewing - One of the best experts on this subject based on the ideXlab platform.
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Long-term storage of Spent Nuclear Fuel
Nature Materials, 2015Co-Authors: Rodney C. EwingAbstract:To design reliable and safe geological repositories it is critical to understand how the characteristics of Spent Nuclear Fuel evolve with time, and how this affects the storage environment.
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Spent Nuclear Fuel
Elements, 2006Co-Authors: Jordi Bruno, Rodney C. EwingAbstract:The primary waste form resulting from Nuclear energy production is Spent Nuclear Fuel (SNF). There are a number of different types of Fuel, but they are predominantly uranium based, mainly UO 2 or, in some cases, metallic U. The UO 2 in SNF is a redox-sensitive semiconductor consisting of a fine-grained (5-10 μm), polycrystalline aggregate containing fission-product and transuranium elements in concentrations of 4 to 6 atomic percent. The challenge is to predict the long-term behavior of UO 2 under a range of redox conditions. Experimental results and observations from natural systems, such as the Oklo natural reactors, have been used to assess the long-term performance of SNF.
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uraninite and uo2 in Spent Nuclear Fuel a comparison
Journal of Nuclear Materials, 1996Co-Authors: Janusz Janeczek, Virginia M Oversby, Rodney C. Ewing, Lars WermeAbstract:Abstract Similarities and differences between uraninite and uranium dioxide in Spent Nuclear Fuel are discussed in detail. Uraninite and its morphological variety, pitchblende, display structural and chemical properties and features that can be considered analogous to UO 2 in Spent Nuclear Fuel, despite the different thermal histories and irradiation conditions. The similarities include topologically identical structures, high resistance to radiation damage, solid solutions with ThO 2 , CaO, and RE 2 O 3 , similar behavior during oxidation, and presence of fission products in uraninite from natural fission reactors in Gabon. The behavior of fission product residues during alteration of uraninite to coffinite in natural fission reactors may aid in estimation of the long-term behavior of fission products from Spent Fuels under repository disposal conditions.
Svitlana Alyokhina - One of the best experts on this subject based on the ideXlab platform.
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thermal analysis of certain accident conditions of dry Spent Nuclear Fuel storage
Nuclear Engineering and Technology, 2018Co-Authors: Svitlana AlyokhinaAbstract:Abstract Thermal analysis of accident conditions is an important problem during safety assessment of the dry Spent Nuclear Fuel storage facilities. Thermal aspects of accident conditions with channel blockage of ventilated storage containers are considered in this article. Analysis of flow structure inside ventilated containers is carried out by numerical simulation. The main mechanisms of heat and mass transfer, which take part in Spent Nuclear Fuel cooling, were detected. Classification of accidents on the basis of their influence on the maximum temperatures inside storage casks is proposed.
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simulation of thermal state of containers with Spent Nuclear Fuel multistage approach
International Journal of Energy Research, 2015Co-Authors: Svitlana Alyokhina, A Kostikov, Volodymyr Goloshchapov, Yu MatsevityAbstract:Summary The safe thermal conditions of Spent Nuclear Fuel storage are the important component of complex safety of the dry Spent Nuclear Fuel storage facility. The multistage approach for numerical definition of thermal fields in storage containers with Spent Fuel assemblies is proposed. The approach is based on solving of the series of the conjugate heat transfer problems with different geometrical detailing. The developed approach is used for estimation of thermal state of ventilated containers with Spent Nuclear Fuel of WWER-1000 reactors of Zaporizhska Nuclear power plant. The results of the thermal calculations for single-placed container on open-site storage platform were presented. The safety of containers usage in normal and extreme ambient temperatures was proven. Copyright © 2015 John Wiley & Sons, Ltd.
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equivalent thermal conductivity of the storage basket with Spent Nuclear Fuel of vver 1000 reactors
Kerntechnik, 2014Co-Authors: Svitlana Alyokhina, A KostikovAbstract:Abstract Due to limitation of computation resources and/or computation time many thermal problems require to use simplified geometrical models with equivalent thermal properties. A new method for definition of equivalent thermal conductivity of Spent Nuclear Fuel storage casks is proposed. It is based on solving the inverse heat conduction problem. For the proposed method two approaches for equivalent thermal conductivity definition were considered. In the first approach a simplified model in conjugate formulation is used, in the second approach a simplified model of solid body which allows an analytical solution is used. For safety ensuring during all time of Spent Nuclear Fuel storage the equivalent thermal conductivity was calculated for different storage years. The calculated equivalent thermal conductivities can be used in thermal researches for dry Spent Nuclear Fuel storage safety.
Yu Matsevity - One of the best experts on this subject based on the ideXlab platform.
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simulation of thermal state of containers with Spent Nuclear Fuel multistage approach
International Journal of Energy Research, 2015Co-Authors: Svitlana Alyokhina, A Kostikov, Volodymyr Goloshchapov, Yu MatsevityAbstract:Summary The safe thermal conditions of Spent Nuclear Fuel storage are the important component of complex safety of the dry Spent Nuclear Fuel storage facility. The multistage approach for numerical definition of thermal fields in storage containers with Spent Fuel assemblies is proposed. The approach is based on solving of the series of the conjugate heat transfer problems with different geometrical detailing. The developed approach is used for estimation of thermal state of ventilated containers with Spent Nuclear Fuel of WWER-1000 reactors of Zaporizhska Nuclear power plant. The results of the thermal calculations for single-placed container on open-site storage platform were presented. The safety of containers usage in normal and extreme ambient temperatures was proven. Copyright © 2015 John Wiley & Sons, Ltd.
