Advanced thermal denitration conversion processes for aqueous-based reprocessing and recycling of spent nuclear fuels

Research output: Chapter in Book/Report/Conference proceedingChapterpeer-review

12 Scopus citations

Abstract

This chapter focuses on advanced thermal denitration methods for conversion of nitrate solutions of uranium and plutonium to oxide particles with good ceramic properties for fabrication of recycle fuel. Specifically, the Japanese microwave heating process and the U.S. modified direct denitration process are described and compared, with emphasis on co-conversion of mixed uranium-plutonium nitrate solutions to produce mixed oxide. Process chemistry, processing equipment, oxide product characteristics, and co-conversion process comparisons are described.

Original languageEnglish
Title of host publicationReprocessing and Recycling of Spent Nuclear Fuel
PublisherElsevier Inc.
Pages313-323
Number of pages11
ISBN (Electronic)9781782422174
ISBN (Print)9781782422129
DOIs
StatePublished - Apr 23 2015

Keywords

  • Advanced thermal denitration
  • Co-conversion
  • Oxide product characteristics
  • Process chemistry
  • Process equipment

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