The oxidative pulverisation of mixed oxide fuels
Creators
- 1. Nexia Solutions, Seascale, Cumbria (United Kingdom)
- 2. V.G. Khlopin Radium Institute, St. Petersburg (Russian Federation)
Description
An investigation of the oxidation of mixed uranium-plutonium oxide (MOx) fuels containing from 5-30% plutonium (heavy metal basis) in air and oxygen atmospheres has been undertaken. MOx pellets prepared by a co-precipitation process were oxidised at temperatures from 600 to 1200degC, samples were reduced back to the MO2 state and then re-oxidised. Weight changes were monitored during each procedure and the phases present in the products from each treatment were analysed using X-ray diffraction (XRD). Samples containing up to 10% Pu were oxidised sufficiently to cause pulverisation of the fuel matrix by a single oxidation treatment at 600degC whereas samples containing higher plutonium contents required a cycle of oxidation-reduction-oxidation cause them to become fragmented. XRD data suggests the formation of plutonium-rich and plutonium-lean grains during the reduction cycle and it is suggested that the oxidation of plutonium-lean grains during re-oxidation step is responsible for the break up of the pellets during this step. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability
- Imprint Pagination
- [2562 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International conference on nuclear energy systems for future generation and global sustainability
- Acronym
- GLOBAL 2005
- Dates
- 9-13 Oct 2005
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37052029
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMMINUTION; COPRECIPITATION; FUEL PELLETS; LATTICE PARAMETERS; MEETINGS; MIXED OXIDE FUELS; OXIDATION; PLUTONIUM; REDUCTION; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; THERMAL GRAVIMETRIC ANALYSIS; URANIUM OXIDES; X-RAY DIFFRACTION
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; CHEMICAL ANALYSIS; CHEMICAL REACTIONS; COHERENT SCATTERING; DIFFRACTION; ELEMENTS; ENERGY SOURCES; FUELS; GRAVIMETRIC ANALYSIS; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PELLETS; PRECIPITATION; QUANTITATIVE CHEMICAL ANALYSIS; REACTOR MATERIALS; SCATTERING; SEPARATION PROCESSES; SOLID FUELS; TEMPERATURE RANGE; THERMAL ANALYSIS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name GL3XX, Paper ID GL372DF.pdf; 6 refs., 13 figs., 4 tabs.