Title of article :
Nitrides as a nuclear fuel option
Author/Authors :
Streit، نويسنده , , Marco and Ingold، نويسنده , , Franz، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2005
Abstract :
Nitrides have been proposed to be a suitable material for fast neutronic systems from beginning of the development of nuclear fuel. Starting with the production of uranium nitride and sesquinitrides up to mixed plutonium uranium nitrides, todayʹs developments are inert nitride matrix materials to burn plutonium or to transmute long-lived actinides in accelerator-driven sub-critical systems (ADS) or fast reactors (FR). Several authors proposed zirconium nitride as possible inert matrix material for this reason. Mixed zirconium nitrides can be fabricated by carbothermal nitridation of the oxides in a narrow temperature window. Obtaining high quality material with low carbon and oxygen content is still the major challenge. Producing mixed nitride fuels by special shaping methods, as for example direct coagulation casting or freeze drying, in comparison to conventional powder compaction enables to use this material in special shapes to optimize burn up.The history of nitride fuels at PSI will be shown up to todayʹs CONFIRM project, dealing with plutonium zirconium nitride fuels.
Keywords :
nitrides , Nuclear applications , Powders-chemical preparation , Shaping , Sol–gel processes
Journal title :
Journal of the European Ceramic Society
Journal title :
Journal of the European Ceramic Society