MOX fuel quality and reprocessing requirements
- 1. Belgonucleaire SA, Dessel (Belgium)
Description
The BN MIMAS fuel manufacturing process relies on the dilution in free flowing UO2 of a micronized master blend containing up to 30% of PuO2. This allows to produce industrial amounts of MOX fuel with a good quality level, as illustrated by resintering results as well as weld contamination measurements. While this fuel is completely soluble in 10M HNO3, kinetics limitations appear when testing entire pellets at 5.5M molarity. These kinetic effects can be virtually eliminated by testing mid-cleaved pellets in non boiling acid, thereby confirming that the dissolution characteristics of MOX fuel are identical to those of UO2. During the reprocessing of modern MOX fuels, one should therefore not expect a more difficult dissolution than with UO2 fuel. (author). 4 refs, 5 figs, 2 tabs
Additional details
Publishing Information
- Imprint Title
- Recycling of plutonium and uranium in water reactor fuels
- Imprint Pagination
- 340 p.
- Journal Page Range
- p. 166-170.
- Report number
- IWGFPT--35
Conference
- Title
- Technical committee meeting on recycling of plutonium and uranium in water reactor fuels.
- Dates
- 13-16 Nov 1989.
- Place
- Cadarache (France).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22051805
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DISSOLUTION; FUEL PELLETS; MIXED OXIDE FUELS; NITRIC ACID; REPROCESSING; SOLUBILITY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; FUELS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; MATERIALS; NITROGEN COMPOUNDS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; SEPARATION PROCESSES; SOLID FUELS; URANIUM COMPOUNDS; URANIUM OXIDES