D. Staicu

Mechanochemistry: opportunities for new and cleaner synthesis

Accident tolerant fuels for LWRs: A perspective

Computer Simulation of Liquids

Molecular dynamics scheme for precise estimation of electrostatic interaction via zero-dipole summation principle

The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel

The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents

Some recent trends in research and technology of advanced thermal barrier coatings

The Serpent Monte Carlo code: Status, development and applications in 2013

An Optimum Approach to Monte Carlo Burnup

Transmutation of americium in a medium size sodium cooled fast reactor design

Magnetic pyrochlore oxides

Synthesis and formation mechanism of cubic ZrN nanopowders by mechanochemical reaction of ZrCl4 and Li3N

The high burn-up structure in nuclear fuel

Nuclear waste disposal—pyrochlore (A2B2O7): Nuclear waste form for the immobilization of plutonium and “minor” actinides

The impact of americium on the ULOF and UTOP transients of the European Lead-cooled SYstem (ELSY)

First-principles DFT+Umodeling of actinide-based alloys: Application to paramagnetic phases of UO2and (U,Pu) mixed oxides

The Open Quantum Materials Database (OQMD): assessing the accuracy of DFT formation energies

An improved and extended internally consistent thermodynamic dataset for phases of petrological interest, involving a new equation of state for solids

The Tetragonal‐Monoclinic Transformation in Zirconia: Lessons Learned and Future Trends

Bulk-nanocrystalline oxide nuclear fuels – An innovative material option for increasing fission gas retention, plasticity and radiation-tolerance

Phase equilibria of the system

Thermal-barrier coatings for more efficient gas-turbine engines

Materials challenges in nuclear energy

Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels

On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM

Effect of burn-up on the thermal conductivity of uranium dioxide up to 100.000 MWdt−1

Effective thermal conductivity of heterogeneous materials: calculation methods and application to different microstructures

Zirconate pyrochlore as a transmutation target: thermal behaviour and radiation resistance against fission fragment impact

Thermophysical characterization of nitrides inert matrices: Preliminary results on zirconium nitride

Molecular dynamics simulation of premelting and melting phase transitions in stoichiometric uranium dioxide

CERMET fuel behavior and properties in ADS reactors