Kinev E.A.1,2, Tsygvintsev V.A. 1
1 Institute of Nuclear Materials, Zarechny, Russia
2 National Research Nuclear University "MIFI", Moscow, Russia
For decrease of fuel multiplier in electrical power cost and competitiveness with thermal nuclear reactors the essential increase of new generation fast reactors fuel burnup is required. The analysis of materials science investigations of structure, porosity, lattice parameter, pressure of gaseous fission products for uranium dioxide, mixed uranium-plutonium oxide and dense uranium pellet fuel after irradiation in fast neutron spectra have been made. The comparison between investigated characteristics for short-term (less than 1% FIMA) and maximum (~14% FIMA) burnup have been executed. It is shown that to exception undesirable thermomechanical interaction of dense fuel with the cladding at high burning out the increased technological porosity or central hole in fuel pellets may be demanded. The same type interaction of uranium dioxide fuel at 14% FIMA is essentially weakened under formation of highly-porous unstable periphery Rim-area and pellet creep. The internal pressure of gaseous fission products in fuel elements at working temperatures and maximum investigated burnup exceeds 6 MPa (circumferential stress of the cladding is nearby 55 MPa). It may require increase of free volume of fuel element compensation space which provides 16-20% FIMA burnup.
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