Journal of Nuclear Materials

Title Publication Date Language Citations
Formation mechanism of bubbles and holes on tungsten surface with low-energy and high-flux helium plasma irradiation in NAGDIS-II2004/08/01English227
Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating2015/10/01English226
Characterization of precipitates in MA/ODS ferritic alloys2006/06/01English224
Interatomic potentials for simulation of He bubble formation in W2013/01/01English222
Void-swelling in irons and ferritic steels1979/11/01English222
TEM observation of the growth process of helium nanobubbles on tungsten: Nanostructure formation mechanism2011/11/01English219
Properties of zirconium carbide for nuclear fuel applications2013/10/01English219
Progress in development of China Low Activation Martensitic steel for fusion application2007/08/01English211
Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors2019/04/01English209
Self-interstitial atoms in metals1978/02/01English206
Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment2014/12/01English205
Influence of particle dispersions on the high-temperature strength of ferritic alloys2007/08/01English205
Embrittlement of RPV steels: An atom probe tomography perspective2007/09/01English205
Comparison of empirical interatomic potentials for iron applied to radiation damage studies2010/11/01English203
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys2015/10/01English199
Silicon carbide composites as fusion power reactor structural materials2011/10/01English198
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions2014/05/01English197
Hydrogen in zirconium alloys: A review2019/05/01English197
A calculation of the surface recombination rate constant for hydrogen isotopes on metals1980/09/01English196
The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide1982/06/01English196
Transmission electron microscopy examination of oxide layers formed on Zr alloys2006/03/01English196
Sorption studies of uranium and thorium on activated carbon prepared from olive stones: Kinetic and thermodynamic aspects2010/01/01English195
The dilatational misfit of zirconium hydrides precipitated in zirconium1973/10/01English192
Status of reduced activation ferritic/martensitic steel development2007/08/01English192
Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate2004/01/01English191
Kinetics of diffusional motion of pores in solids1969/04/01English191
Fuels for sodium-cooled fast reactors: US perspective2007/09/01English190
Observation and analysis of defect cluster production and interactions with dislocations2004/08/01English189
A new fission-gas release model1983/08/01English189
Additive manufacturing of 316L stainless steel by electron beam melting for nuclear fusion applications2017/04/01English188