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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.
Fan, Fang-Li; Qin, Zhi; Cao, Shi-Wei; Tan, Cun-Min; Huang, Qing-Gang; Chen, De-Sheng; Wang, Jie-Ru; Yin, Xiao-Jie; Xu, Chao; Feng, Xiao-Gui.
Affiliation
  • Fan FL; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Qin Z; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Cao SW; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Tan CM; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Huang QG; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Chen DS; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Wang JR; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Yin XJ; Institute of Modern Physics , Chinese Academy of Sciences , Lanzhou 730000 , China.
  • Xu C; Nuclear Chemistry and Chemical Engineering Division, Institute of Nuclear and New Energy Technology , Tsinghua University , Beijing 100084 , China.
  • Feng XG; Nuclear Chemistry and Chemical Engineering Division, Institute of Nuclear and New Energy Technology , Tsinghua University , Beijing 100084 , China.
Inorg Chem ; 58(1): 603-609, 2019 Jan 07.
Article in En | MEDLINE | ID: mdl-30565939
ABSTRACT
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 metal compound M xO y is used to elaborate the solubility. This work represents the first case for efficient fission products removal by selective dissolution, avoiding the complete dissolution of spent nuclear fuel, the producing of the large high-level radioactive waste, and reducing environmental hazards.

Full text: 1 Collection: 01-internacional Database: MEDLINE Language: En Journal: Inorg Chem Year: 2019 Type: Article Affiliation country: China

Full text: 1 Collection: 01-internacional Database: MEDLINE Language: En Journal: Inorg Chem Year: 2019 Type: Article Affiliation country: China