Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors
International Atomic Energy Agency, 2006 - Business & Economics - 83 pages
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
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alloy americium Atomic Energy burnup candidate materials CANDU ceramic cercer cermet fuel cladding coolant core curium damage density dispersion fuels EFTTRA Email fast reactors fast spectrum fissile fission fragment fission gas release fission products fuel behaviour fuel compositions fuel concept fuel cycle fuel particle fuel pins Future Nuclear Systems heterogeneous high flux reactor homogeneous IAEA IMF rods IMF workshop in-pile inert matrix fuel Innovative Fuels irradiation experiments irradiation testing isotopes JAERI Japan metal MgAl2O4 minor actinides multi-recycling neutron nitride fuel Nucl nuclear fuel oxide Paul Scherrer Institute pellet Phenix plutonium and minor plutonium burning pressurized water reactors Proc programme proliferation resistance PuO2 reactivity recycling reduce repository reprocessing Research Reactor ROX fuel safety sintering solid solution spent fuel spinel stability studies swelling targets thermal conductivity transmutation UO2 fuel uranium waste water reactors Zircaloy zirconia zirconium ZrO2