Dry pretreatment of used nuclear fuel to simplify storage or recycle - Shearing or chemical decladding and voloxidation

G. D. DelCul, J. A. Johnson, B. B. Spencer, E. D. Collins, R. T. Jubin, J. C. Bresee

Research output: Contribution to journalConference articlepeer-review

2 Scopus citations

Abstract

The application of NO2 voloxidation could result in cost reduction and simplification of treating nuclear fuel. The resulting oxide product devoided of volatile fission products that could be released from stored fuel during an accident scenario is a very stable form for long-term storage. However, because the oxidation produces a fine powder with 99% of the particles reduced to <20 urn and with a bulk density of ∼2.2 g/mL, this option may require a densification step prior to packaging for long-term stable storage. A remotely operated compaction process may be required. The oxides or nitrated powders are also an excellent initial product for aqueous and nonaqueous processing methods such as electrochemical separation in molten salts, halide volatility, crystallization, DUPIC-like processes, supercritical C02 dissolution, aqueous alkaline separations, etc.

Original languageEnglish
Pages (from-to)241-242
Number of pages2
JournalTransactions of the American Nuclear Society
Volume107
StatePublished - 2012
Event2012 ANS Annual Winter Meeting - San Diego, CA, United States
Duration: Nov 11 2012Nov 15 2012

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