Evaluation of Li{sub 3}N accumulation in a fused LiCl/Li salt matrix.

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Pyrochemical conditioning of spent nuclear fuel for the purpose of final disposal is currently being demonstrated at Argonne National Laboratory (ANL), and ongoing research in this area includes the demonstration of this process on spent oxide fuel. In conjunction with this research a pilot scale of the preprocessing stage is being designed by ANL-W to demonstrate the in situ hot cell capability of the chemical reduction stage. An impurity evaluation was completed for a Li/LiCl salt matrix in the presence of spent LWR uranium oxide fuel. A simple analysis was performed in which the sources of impurities in the salt ... continued below

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9 p.

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Eberle, C. S. February 3, 1998.

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Description

Pyrochemical conditioning of spent nuclear fuel for the purpose of final disposal is currently being demonstrated at Argonne National Laboratory (ANL), and ongoing research in this area includes the demonstration of this process on spent oxide fuel. In conjunction with this research a pilot scale of the preprocessing stage is being designed by ANL-W to demonstrate the in situ hot cell capability of the chemical reduction stage. An impurity evaluation was completed for a Li/LiCl salt matrix in the presence of spent LWR uranium oxide fuel. A simple analysis was performed in which the sources of impurities in the salt matrix were only from the cell atmosphere. Only reactions with the lithium were considered. The levels of impurities were shown to be highly sensitive system conditions. A predominance diagram for the Li-O-N system was constructed for the device, and the general oxidation, nitridation and combined reactions were calculated as a function of oxygen and nitrogen partial pressure. These calculations and hotcell atmosphere data were used to determine the total number and type of impurities expected in the salt matrix and the mass rate for the device was determined.

Physical Description

9 p.

Notes

INIS; OSTI as DE00011023

Medium: P; Size: 9 pages

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  • Annual Meeting of the American Nuclear Society, Nashville, TN (US), 06/07/1998--06/11/1998

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  • Report No.: ANL/ED/CP-95580
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11023
  • Archival Resource Key: ark:/67531/metadc626717

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • February 3, 1998

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  • June 16, 2015, 7:43 a.m.

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  • April 11, 2017, 8:13 p.m.

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Eberle, C. S. Evaluation of Li{sub 3}N accumulation in a fused LiCl/Li salt matrix., article, February 3, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc626717/: accessed November 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.