Published December 1, 2006 | Version v1
Journal article

Electrochemical reduction of (U-40Pu-5Np)O2 in molten LiCl electrolyte

  • 1. Central Research Institute of Electric Power Industry, Nuclear Technology Research Laboratory, Iwato-kita 2-11-1, Komae, Tokyo 201-8511 (Japan)

Description

The electrochemical reduction of neptunium-containing MOX ((U-40Pu-5Np)O2) was performed in molten lithium chloride melt at 923 K to investigate fundamental behavior of the transuranium elements and applicability of the method to reduction process for these materials. The Np-MOX was electrochemically reduced at the potential lower than -0.6 V vs. Bi-35 mol% Li reference electrode. The reduced metal grains in the surface region of the sample cohered with each other and made the layer of relatively high density, although it did not prevent the reduction of the sample toward the center. Complete reduction of the Np-MOX was shown by the weight change measurement through the electrochemical reduction and also by SEM-EDX observation. The chemical composition of the reduction products was homogeneous and agreed to that of the initial Np-MOX, which indicates that the reduction was completed and not selective among the actinides. The concentrations of the actinide elements, especially plutonium and americium in the electrolyte, increased with the progress of the tests, although their absolute values were very small. It is quite likely that plutonium and americium dissolve into the melt in the same manner as the lanthanide elements in the lithium reduction process

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2006.08.003;
PII
S0022-3115(06)00443-0;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
359
Journal Issue
1-2
Journal Page Range
p. 102-113
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2006 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.