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Title: Analysis and modeling of the equilibrium behaviors of U and Pu in molten LiCl-KCl/Cd system at 500 °C

Journal Article · · Journal of Nuclear Materials
ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States). Pyroprocessing Department
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In the field of pyroprocessing of used nuclear fuels, liquid cadmium is applied in different ways to recover transuranics from molten salt, while effecting some degree of separations between transuranics and lanthanides. In this work, a model of the separation performance between uranium and plutonium across the phase boundary between molten salt and liquid cadmium is presented. The salt is the LiCl-KCl eutectic with solute concentrations of UCl3 and PuCl3. The cadmium is the liquid cadmium phase field from the Cd-U-Pu ternary alloy system. Lastly, the model used to describe the behavior of uranium and plutonium in the salt/cadmium system is applied to describe the behavior of plutonium and lanthanide in the salt/cadmium system.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1478469
Alternate ID(s):
OSTI ID: 1775993
Report Number(s):
INL/JOU-18-44719-Rev000
Journal Information:
Journal of Nuclear Materials, Vol. 508, Issue C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 4 works
Citation information provided by
Web of Science

Figures / Tables (24)

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
pyroprocessing
uranium
plutonium
cadmium
liquid cadmium cathode
electrorefining
electrometallurgical
nuclear fuel reprocessing
liquid metal extraction