The MARINE experiment: Irradiation of sphere-pac fuel and pellets of UO 2−x for americium breading blanket concept

Synthesis and characterization of homogeneous (U,Am)O2 and (U,Pu,Am)O2 nanopowders

“…One of the sustainability goals for nuclear reactors of the fourth generation (Gen-IV), as defined by the Generation IV International Forum (GIF), is the minimisation of the nuclear waste and the reduction of the long-term stewardship burden. 1 Since plutonium and the minor actinides (MA) are largely responsible for the long-term radiotoxicity of the spent nuclear fuel, 2,3 their separation and transmutation into short-lived isotopes in fast reactor systems can significantly contribute to this goal. 4 The reuse of fissile isotopes from nuclear waste in the form of mixed oxide fuel is an integral part of the nuclear energy strategy in some EU member states and contributes to the sustainable usage of nuclear material resources.…”

Infiltration of porous uranium oxide microspheres prepared by internal gelation

“…Within the SPHERE irradiation experiment a mixed-oxide particle fuel (composition U0.76Pu0.20Am0.03O2-x) was developed by infiltration of porous beads prepared from external and internal gelation with americium solution [25]. In the later MARINE irradiation experiment the fabrication of mixed-oxide fuels with Am contents up to 14 % metal fraction similarly employed infiltration, but the precursors were made using external gelation only [26]. Recently, the application of infiltration on internally gelled UO3 microspheres was also reported for manganese and chromium doping (up to 2000 ppm, dopant to uranium weight concentration) [27].…”