Electrochemical reprocessing,
also referred to as pyroprocessing,
is a technique for recycling actinides from used nuclear fuel (UNF)
to produce fuel for future reactors. Here, UNF is dissolved in a molten
salt (e.g., LiCl-KCl eutectic) within an electrorefiner. After UNF
dissolution, fission products are released into the electrolyte salt
and converted to chlorides. This paper discusses wasteform options
for processing the base electrolyte salt with the fission product
salts as well as only the rare-earth (RE) fission products (as RECl3, REOCl, or REO
x
) with the intent
of finding optimal methods for reducing total waste salt volumes by
partitioning the salt for alternate wasteform options. Two of the
more detailed partitioning options discussed herein include halide
removal from the salt (dehalogenation), which accounts for more than
half of the salt on a molar basis, and RE fission product removal
for wasteforms with high-RE loadings. Wasteform properties are compared
with emphasis on wasteform volume starting from a given amount of
(1) total salt cations or (2) RE cations. Comparisons are also made
of wasteform chemical durabilities, with the data available from like
testing methods. A main conclusion from this work is the justification
of subsequent salt processing after electrorefiner operations for
achieving significant wasteform volume reduction.