作者: Claude Degueldre
DOI: 10.1016/J.JALLCOM.2006.11.203
关键词: Chemical engineering 、 Fission products 、 Radiochemistry 、 Plutonium 、 Nuclear fuel 、 Spent nuclear fuel 、 Minor actinide 、 Materials science 、 Light-water reactor 、 Nuclear fission product 、 Yttria-stabilized zirconia
摘要: Abstract The radiotoxicity of the UO 2 spent fuel is dominated by plutonium and minor actinides (MA): Np, Am Cm, after decay short life fission products. Zirconia ceramics containing Pu MA in form an inert matrix (IMF) could be used to burn these light water reactors or high temperature reactors. Optimisation designs dictated properties such as thermal, mechanical, chemical physical must performed with attention for their behaviour under irradiation. stabilised yttria a solid solution z Y y x Zr 1− O 2− ζ where actinide oxides are also soluble. may act burnable poison reducing reactivity at beginning yielding fertile nuclides improving end life. These zirconia cubic solutions stable heavy ion retention products zirconia, similar thermodynamic conditions, priori stronger, compared , lattice parameter being larger than (Y,Zr)O . (Er,Y,Pu,Zr)O which contains 5% was successfully irradiated Proteus reactor PSI, HFR facility, Petten well Halden reactor. tests support potential irradiations IMF commercial This would allow later deployment utilisation last cycle. forms namely pellet-fuel, cercer, cermet coated particle discussed considering once through strategy. For this strategy, low solubility required geological disposal. As fuels IMFs excellent materials from point view, studied detail range corresponding groundwater near field conditions. Under conditions about 10 6 times smaller glass, makes material very attractive deep desired objective use produce energy reactors, opting economical ecological solution.