The thermal conductivities of near-stoichiometric (U, Pu, Am) O 2 doped with Nd and/or Sm,
which are major fission products (FPs) generated during irradiation of uranium–plutonium …

Oxygen potentials of U 0.817 Pu 0.180 Am 0.003 O 2±x incorporating 10 and 20 mol% of
neodymium (Nd/Metal) were investigated by thermogravimetry at 1573, 1773, and 1873 K …

This paper presents the results of studies developed at the Department of Nuclear
Engineering of the Universidade Federal de Minas Gerais–Brazil (DEN-UFMG) on the use of …

Additive MOX pellets are fabricated by mechanically blending the additive material powder
and MOX powder. Nd2O3 and Sm2O3 are chosen as the additive materials to simulate the …

Alternative nuclear fuel cycles could contribute to the future of nuclear fission technology
reducing the use of natural resources, waste management and lessening greenhouse gas …

Spent fuel reprocessed by UREX+ technique and spiked with thorium was submitted to a
neutron irradiation in two different fusion–fission systems. One based on magnetic …

The aim of this work is to preliminarily evaluate the behaviour of a PWR core based on
Brazilian Angra 2 when reprocessed fuel spiked with thorium (TRU) is inserted. The TRU …

This study proposes an optimized small-sized subcritical fast reactor with an external
neutron source for actinide transmutation. The reactor integrates features of Accelerator …

The aim of this study is to investigate the nuclear fuel evolution and the neutronic
parameters of a lead-cooled ADS used for fuel breeding and transmutation of reprocessed …

Accelerator‐driven systems (ADSs) are investigated for long‐lived fission product
transmutation and fuel regeneration. The aim of this paper is to investigate the nuclear fuel …