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 language | English |
|---|---|
| Title of host publication | Reprocessing and Recycling of Spent Nuclear Fuel |
| Publisher | Elsevier Inc. |
| Pages | 313-323 |
| Number of pages | 11 |
| ISBN (Electronic) | 9781782422174 |
| ISBN (Print) | 9781782422129 |
| DOIs | |
| State | Published - Apr 23 2015 |
Keywords
- Advanced thermal denitration
- Co-conversion
- Oxide product characteristics
- Process chemistry
- Process equipment
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