Composite fuels. Defining a strategy for better Pu utilization in PWRs
- 1. DRN/DER/SIS CE Cadarache Bat. 211, 13108 St. Paul lez Durance CEDEX (France)
Description
After a description of the French context dominated by the accumulation of plutonium, and the international context in which the tendency is towards the disappearance of plutonium reserves and the destruction of minor actinides, a few solutions selected in the framework of the Innovating Fuels programme are presented. The aim is to burn the surplus Pu by means of fuel in inert matrices since, in addition to the increased burnup, the absence of plutonium generating conversion must be considered. The experiments intended to qualify selected CERCERs and CERMETs are presented and discussed, the feasibility of CERMET UO2 and MOX cores is established. Things are more complicated for PuO2 CERMET and we show that, in order to optimize loading, a dedicated heterogeneous assembly has to be defined. The Advanced Plutonium Assembly (APA) is presented. The last part of this article is devoted to the first fabrication tests on these very particular fuels and to the definition of reference accidents liable to affect 'cold' fuels such as CERMETs. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-7: Proceedings of the 7th international conference on nuclear engineering
- Imprint Pagination
- 4252 p.
- Journal Page Range
- [9 p.]
Conference
- Title
- 7. international conference on nuclear engineering
- Acronym
- ICONE-7
- Dates
- 19-23 Apr 1999
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31010901
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CERMETS; DEMONSTRATION PROGRAMS; FISSION PRODUCT RELEASE; MIXED OXIDE FUELS; NUCLEAR FUELS; PLUTONIUM; PLUTONIUM OXIDES; PWR TYPE REACTORS; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; COMPOSITE MATERIALS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 95/98/NT, MACINTOSH and UNIX; Acrobat Reader 3.0.1 is included; Data in PDF format, Track No. 09, ICONE-7109