What shall we do with the separated Pu?
Creators
Description
A summary is given of a report ''Management of Separated Plutonium: the technical options'' by an expert group of the OECD's Nuclear Energy Agency. The group has reviewed experience with Pu handling and use in the civil nuclear industry. They conclude that in the next 15 to 20 years Pu can be effectively recycled in thermal reactors in the form of mixed oxide (MOX) fuel and details are provided of MOX fuel fabrication status in OECD countries. Future reactor options are being researched in many countries. These include: Pu burning fast reactors using oxide fuels; alternatives to oxides such as plutonium-uranium nitride and carbide; Pu annihilation in CANDU reactors; high temperature gas-cooled reactor options which would burn Pu to the point of almost not needing reprocessing. Final disposal options must be considered if separated Pu is not used as a fissile energy source. The group reviewed vitrification and burial in deep boreholes. They noted that both physical security and nuclear criticality are significant issues to be addressed if Pu borosilicate glass is to be placed in a repository. The greatest unknown for the alternative of placing Pu directly into a custom deep borehole facility in small criticality safe containers, is the uncertain regulatory status. Regulations applicable to a dedicated Pu disposal facility do not currently exist. (UK)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering International
- Journal Volume
- 42
- Journal Issue
- 516
- Journal Page Range
- p. 28-29.
- ISSN
- 0029-5507
- CODEN
- NEINBF
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 28064635
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BWR TYPE REACTORS; CANDU TYPE REACTORS; FAST REACTORS; HTGR TYPE REACTORS; MIXED CARBIDE FUELS; MIXED NITRIDE FUELS; MIXED OXIDE FUELS; PLUTONIUM; PLUTONIUM CARBIDES; PLUTONIUM DIOXIDE; PLUTONIUM NITRIDES; PLUTONIUM RECYCLE; PWR TYPE REACTORS; RADIOACTIVE WASTE DISPOSAL; UNDERGROUND DISPOSAL; VITRIFICATION
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FUEL CYCLE; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAVY WATER MODERATED REACTORS; MANAGEMENT; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; PNICTIDES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS; WASTE DISPOSAL; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS