| Nuclear fuels – Present and future | 2009/05/01 | English | 163 |
| Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems | 2011/12/01 | English | 162 |
| Thermophysical properties of U3Si2 to 1773 K | 2015/09/01 | English | 162 |
| Impact of low energy helium irradiation on plasma facing metals | 2005/03/01 | English | 162 |
| Microencapsulated fuel technology for commercial light water and advanced reactor application | 2012/08/01 | English | 161 |
| The passivity of Type 316L stainless steel in borate buffer solution | 2008/09/01 | English | 161 |
| Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding | 2016/09/01 | English | 160 |
| Nanometer scale precipitation in ferritic MA/ODS alloy MA957 | 2004/08/01 | English | 160 |
| The role of implanted gas and lateral stress in blister formation mechanisms | 1978/09/01 | English | 160 |
| Development of potential low activation ferritic and austenitic steels | 1986/11/01 | English | 159 |
| T91 cladding tubes with and without modified FeCrAlY coatings exposed in LBE at different flow, stress and temperature conditions | 2008/06/01 | English | 158 |
| Modelling deuterium release during thermal desorption of D+-irradiated tungsten | 2008/03/01 | English | 158 |
| An object Kinetic Monte Carlo Simulation of the dynamics of helium and point defects in tungsten | 2009/03/01 | English | 157 |
| Issues and advances in SiCf/SiC composites development for fusion reactors | 2004/08/01 | English | 157 |
| High performance of phosphate-functionalized graphene oxide for the selective adsorption of U(VI) from acidic solution | 2015/11/01 | English | 156 |
| A review of irradiation assisted stress corrosion cracking | 1994/08/01 | English | 156 |
| Hydride precipitates in zirconium alloys (A review) | 1968/11/01 | English | 156 |
| Characterization of SiC–SiC composites for accident tolerant fuel cladding | 2015/11/01 | English | 156 |
| Thermochemical properties of lanthanides (Ln=La,Nd) and actinides (An=U,Np,Pu,Am) in the molten LiCl–KCl eutectic | 2005/09/01 | English | 155 |
| On the relation between lattice parameter and O/M ratio for uranium dioxide-trivalent rare earth oxide solid solution | 1981/11/01 | English | 155 |
| Lead–lithium eutectic material database for nuclear fusion technology | 2008/06/01 | English | 155 |
| Microstructure of neutron-irradiated iron before and after tensile deformation | 2006/06/01 | English | 154 |
| Interstitial mobility and interactions | 1978/02/01 | English | 153 |
| Post-irradiation examination of uranium–7wt% molybdenum atomized dispersion fuel | 2004/10/01 | English | 153 |
| Fracture toughness investigations of tungsten alloys and SPD tungsten alloys | 2007/08/01 | English | 152 |
| Uniform corrosion of FeCrAl alloys in LWR coolant environments | 2016/10/01 | English | 152 |
| Molecular dynamic calculations of energetic displacement cascades | 1981/01/01 | English | 152 |
| Molecular dynamics simulation of displacement cascades in α-Fe: A critical review | 2006/06/01 | English | 152 |
| Trapping of deuterium implanted in carbon and silicon: A calibration for particle-energy measurements in the plasma boundary of tokamaks | 1979/10/01 | English | 151 |
| MD and KMC modeling of the growth and shrinkage mechanisms of helium–vacancy clusters in Fe | 2003/12/01 | English | 151 |