Journal of Nuclear Materials

Title Publication Date Language Citations
Recommendation of miniaturized techniques for mechanical testing of fusion materials in an intense neutron source1996/09/01English
Microstructure assessment of the low activation ferritic/martensitic steel F82H1998/10/01English
Irradiation embrittlement of 2Cr–1Mo steel at 400°C and its electrochemical evaluation1998/10/01English
Developments of high-Tc superconducting current feeders for a large-scale superconducting coil system1998/10/01English
Manufacturing porous U-10Zr metallic fuels with controllable microstructure by volume control spark plasma sintering2024/05/01English
Influence of Nd doping on the structural and electrochemical properties of uranium dioxide2024/05/01English
Development and characterisation of Be/Glidcop® joints obtained by hot isostatic pressing for high temperature working conditions1998/10/01English
XAS and XRD study of annealed 238Pu- and 239Pu-substituted zircons (Zr0.92Pu0.08SiO4)2000/04/01English
Effect of carbon and nitrogen on grain boundary segregation in irradiated stainless steels1998/10/01English
Long-lived activity of elements: Effect of new activation cross- sections and their uncertainties on the selection of materials for IFE reactors1998/10/01English
Glass-ceramic joining and coating of SiC/SiC for fusion applications1998/10/01English
Dynamic strain ageing evidences during low cycle fatigue deformation in ferritic–martensitic stainless steels1998/10/01English
Analysis and measurement of residual stress distribution of vanadium/ceramics joints for fusion reactor applications1998/10/01English
Fabrication and thermal conductivity of UN-UB2 composites fabricated by spark plasma sintering2023/12/01English
Dynamic heterogeneity of atomic transport in a body-centered cubic WTaVCr non-equiatomic high-entropy alloy2023/12/01English
MD simulation of primary radiation damage in fcc multi-principal element alloys: Effect of compositional undulation2023/12/01English
Porosity evolution in proton irradiated microfine-grained POCO graphite2023/12/01English
Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln2023/12/01English
Effects of irradiation on the insolubility of sodium fast reactor (U,Pu)O2 mixed oxide with a very high amount of plutonium2023/12/01English
Editorial Board2023/12/01English
Nuclear forensic signatures of UO2 fuel pellets for differentiation and provenance determination illustrated using synthetic database2023/12/01English
Precipitation characteristics and growth mechanism of Fe and Cr from liquid lead-bismuth eutectic by quenching in liquid nitrogen2023/12/01English
Mechanical behavior analysis using small-size graphite disc compression testing with digital image correlation methods2023/12/01English
On the creep mechanisms and macroscopic creep rate modeling of high-uranium-density composite fuels2023/12/01English
Development of an oxidation model for the prediction of the corrosion risk induced by deposits on cladding surface in PWRs2023/12/01English
Simulations of self- and Xe diffusivity in uranium mononitride including chemistry and irradiation effects2023/12/01English
Predicting the particle-agglomeration effect on the equivalent mechanical properties of dispersion nuclear fuel by machine learning2023/12/01English
The channeling effect of symmetrical tilt grain boundaries on helium bubbles in tungsten2023/12/01English
Editorial Board2023/11/01English
Thermal conductivity degradation due to radiation-induced amorphization in U3Si2: A pilot study2023/12/01English