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

被引:43
作者
Degueldre, Claude [1 ]
机构
[1] Paul Scherrer Inst, CH-5232 Villigen, Switzerland
关键词
inert matrix fuel; plutonium minor actinide; transmutation;
D O I
10.1016/j.jallcom.2006.11.203
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
The radiotoxicity of the UO2 spent fuel is dominated by plutonium and minor actinides (MA): Np, Am and Cm, after decay of the short life fission products. Zirconia ceramics containing Pu and MA in the form of an inert matrix fuel (IMF) could be used to burn these actinides in light water reactors or in high temperature reactors. Optimisation of the fuel designs dictated by properties such as thermal, mechanical, chemical and physical must be performed with attention for their behaviour under irradiation. Zirconia must be stabilised by yttria to form a solid solution such as MA(z)Y(y)Pu(x)Zr(1-y)O(2-zeta) where minor actinide oxides are also soluble. MA may act as a burnable poison reducing the reactivity at the beginning of life and yielding fertile nuclides improving the reactivity at the end of life. These zirconia cubic solid solutions are stable under heavy ion irradiation. The retention of fission products in zirconia, under similar thermodynamic conditions, is a priori stronger, compared to UO2, the lattice parameter being larger for UO2 than for (YZr)O2-x. (Er,YPu,Zr)O2-x in which Pu contains 5% Am was successfully irradiated in the Proteus reactor at PSI, in the HFR facility, Petten as well as in the Halden reactor. These tests support potential irradiations of such IMF in a commercial reactor. This would allow later a commercial deployment of such a zirconia fuel for Pu and MA utilisation in a last cycle. The fuel forms namely pellet-fuel, cercer, cermet or coated particle fuel are discussed considering the once through strategy. For this strategy, low solubility of the inert matrix is required for geological disposal. As spent fuels these IMFs must be excellent materials from the solubility point of view, this parameter was studied in detail for a range of solutions corresponding to groundwater under near field conditions. Under these conditions the IMF solubility is about 106 times smaller than glass, which makes the zirconia material very attractive for deep geological disposal. The desired objective would be to use IMF to produce energy in reactors, opting for an economical and ecological solution. (c) 2006 Elsevier B.V. All rights reserved.
引用
收藏
页码:36 / 41
页数:6
相关论文
共 30 条
[21]  
NITANI N, 1995, P PSI WORKSH ADV FUE, P118
[22]   ON THE PHYSICS FEASIBILITY OF LWR PLUTONIUM FUELS WITHOUT URANIUM [J].
PARATTE, JM ;
CHAWLA, R .
ANNALS OF NUCLEAR ENERGY, 1995, 22 (07) :471-481
[23]  
PORTA J, 1998, P ARWIF 98 OECD NEA
[24]   The influence of carbonate complexes on the solubility of zirconia: new experimental data [J].
Pouchon, MA ;
Curti, E ;
Degueldre, C ;
Tobler, L .
PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) :443-446
[25]   RELEASE OF FISSION-PRODUCTS (XE, I, TE, CS, MO AND TC) FROM POLYCRYSTALLINE UO2 [J].
PRUSSIN, SG ;
OLANDER, DR ;
LAU, WK ;
HANSSON, L .
JOURNAL OF NUCLEAR MATERIALS, 1988, 154 (01) :25-37
[26]   Advanced plutonium fuel assembly: An advanced concept for using plutonium in pressurized water reactors [J].
Puill, A ;
Bergeron, J .
NUCLEAR TECHNOLOGY, 1997, 119 (02) :123-140
[27]   Zirconia-based materials for transmutation of americium and curium: cubic stabilized zirconia and zirconium oxide pyrochlores [J].
Raison, PE ;
Haire, RG .
PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) :251-254
[28]   Radiation damage effects in zirconia [J].
Sickafus, KE ;
Matzke, H ;
Hartmann, T ;
Yasuda, K ;
Valdez, JA ;
Chodak, P ;
Nastasi, M ;
Verrall, RA .
JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) :66-77
[29]   Lattice parameter changes associated with the rim-structure formation in high burn-up UO2 fuels by micro X-ray diffraction [J].
Spino, J ;
Papaioannou, D .
JOURNAL OF NUCLEAR MATERIALS, 2000, 281 (2-3) :146-162
[30]   Thermal expansion of neptunium-plutonium mixed oxides [J].
Yamashita, T ;
Muto, H ;
Tsuji, T ;
Nakamura, Y .
JOURNAL OF ALLOYS AND COMPOUNDS, 1998, 271 :404-407