| Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses | 2010/11/01 | English | 151 |
| Brittle fracture and the brittle-to-ductile transition of tungsten | 2003/12/01 | English | 151 |
| Chemical thermodynamic representation of | 1985/02/01 | English | 150 |
| The ITER divertor concept | 1995/04/01 | English | 150 |
| In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes | 2008/01/01 | English | 150 |
| Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT | 2009/07/01 | English | 150 |
| Neutron irradiation effects on the microstructural development of tungsten and tungsten alloys | 2016/04/01 | English | 149 |
| Review on the EFDA programme on tungsten materials technology and science | 2011/10/01 | English | 149 |
| Detailed characterisation of the rim microstructure in PWR fuels in the burn-up range 40–67 GWd/tM | 1996/08/01 | English | 149 |
| Neutron irradiation of superconducting compounds | 1978/03/01 | English | 148 |
| Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600 | 2006/01/01 | English | 148 |
| Metallic fuels for advanced reactors | 2009/07/01 | English | 147 |
| Radiation damage in helium ion irradiated nanocrystalline Fe | 2012/06/01 | English | 147 |
| Materials challenges for ITER – Current status and future activities | 2007/08/01 | English | 146 |
| Materials for future nuclear energy systems | 2019/12/01 | English | 145 |
| Sputtering properties of tungsten ‘fuzzy’ surfaces | 2011/08/01 | English | 144 |
| Void swelling and defect cluster formation in reactor-irradiated copper | 1989/12/01 | English | 144 |
| Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding | 2015/11/01 | English | 144 |
| Diffusion bonding of titanium to 304 stainless steel | 2003/11/01 | English | 144 |
| Neutron irradiation-induced voids in β-silicon carbide | 1973/08/01 | English | 144 |
| Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors | 2009/07/01 | English | 144 |
| High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments | 2019/12/01 | English | 143 |
| Cation disorder in high dose, neutron-irradiated spinel | 1995/03/01 | English | 143 |
| Radiation hardening of copper single crystals | 1960/12/01 | English | 142 |
| Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuel | 2008/04/01 | English | 142 |
| Development of a helium-cooled divertor: Material choice and technological studies | 2007/08/01 | English | 141 |
| Deuterium trapping in irradiated 316 stainless steel | 1978/09/01 | English | 141 |
| TEM characterization of structure and composition of nanosized ODS particles in reduced activation ferritic–martensitic steels | 2004/08/01 | English | 141 |
| A theory of swelling and gas release for reactor materials | 1964/02/01 | English | 140 |
| Chemically produced nanostructured ODS–lanthanum oxide–tungsten composites sintered by spark plasma | 2011/01/01 | English | 140 |