Zirconia inert matrix for plutonium utilisation and minor actinides disposition in reactors

作者: Claude Degueldre

DOI: 10.1016/J.JALLCOM.2006.11.203

关键词: Chemical engineeringFission productsRadiochemistryPlutoniumNuclear fuelSpent nuclear fuelMinor actinideMaterials scienceLight-water reactorNuclear fission productYttria-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.

参考文章(17)
C. Lombardi, A. Mazzola, Plutonium burning in pressurized water reactors via nonfertile matrices Nuclear Science and Engineering. ,vol. 122, pp. 229- 239 ,(1996) , 10.13182/NSE96-A24157
Hiroshi Akie, Tadasumi Muromura, Hideki Takano, Shojiro Matsuura, A new fuel material for once-through weapons plutonium burning Nuclear Technology. ,vol. 107, pp. 182- 192 ,(1994) , 10.13182/NT107-182
G. Busker, R.W. Grimes, M.R. Bradford, The diffusion of iodine and caesium in the UO2±x lattice Journal of Nuclear Materials. ,vol. 279, pp. 46- 50 ,(2000) , 10.1016/S0022-3115(99)00274-3
M. Burghartz, G. Ledergerber, F. Ingold, P. Heimgartner, C. Degueldre, X-ray diffraction analysis and data interpretation of stabilized zirconia inert matrix fuel doped with plutonium Progress in Nuclear Energy. ,vol. 38, pp. 247- 250 ,(2001) , 10.1016/S0149-1970(00)00109-8
Christian Ekberg, Göran Källvenius, Yngve Albinsson, Paul L. Brown, Studies on the Hydrolytic Behavior of Zirconium(IV) Journal of Solution Chemistry. ,vol. 33, pp. 47- 79 ,(2004) , 10.1023/B:JOSL.0000026645.41309.D3
J.M. Paratte, R. Chawla, On the physics feasibility of LWR plutonium fuels without uranium Annals of Nuclear Energy. ,vol. 22, pp. 471- 481 ,(1995) , 10.1016/0306-4549(94)00061-I
S.G. Prussin, D.R. Olander, W.K. Lau, L. Hansson, Release of fission products (Xe, I, Te, Cs, Mo and Tc) from polycrystalline UO2 Journal of Nuclear Materials. ,vol. 154, pp. 25- 37 ,(1988) , 10.1016/0022-3115(88)90115-8
K.E. Sickafus, Hj. Matzke, Th. Hartmann, K. Yasuda, J.A. Valdez, P. Chodak III, M. Nastasi, R.A. Verrall, Radiation Damage Effects in Zirconia. Journal of Nuclear Materials. ,vol. 274, pp. 66- 77 ,(1999) , 10.1016/S0022-3115(99)00041-0