Results 11 to 20 of about 4,677 (183)
Swelling of Highly Neutron Irradiated Beryllium and Titanium Beryllide
Journal of Nuclear Engineering, 2022 The swelling of beryllium and titanium beryllide after irradiation at 70–750 °C to neutron fluences of (0.25–8) · 1022 cm−2 (E > 1 MeV) was measured using methods of immersion, dimension, and helium pycnometry.
Vladimir Chakin +3 more
doaj +1 more source
Ab initio investigation of properties and mobility of helium defects in La2Sn2O7 pyrochlore
Nuclear Materials and Energy, 2022 The accumulated helium atoms mitigate the physical properties of nuclear waste forms through long-time radionuclide decay and thus cause the safety concern. In this work, first-principles calculations were carried out to investigate the effects of helium
Xiaolong Li +8 more
doaj +1 more source
Crystals, 2022 The paper is devoted to the study of radiation-induced damage kinetics in beryllium oxide ceramics under irradiation with low-energy helium ions with fluences of 1015–1018 ion/cm2.
Maxim V. Zdorovets +3 more
doaj +1 more source
Crystals, 2021 The aim of this work was to study resistance to helium accumulation processes in the structure of the surface layer of lithium-containing ceramics and the subsequent destruction and embrittlement processes, depending on radiation fluence.
Dmitriy I. Shlimas +4 more
doaj +1 more source
Nuclear Materials and Energy, 2018 Oxide dispersion strengthened (ODS) ferritic–martensitic steels are considered as promising structural materials for fusion reactors, as well as for active zone of new generations fast reactors.
I.I. Chernov +4 more
doaj +1 more source
Swelling and Helium Damage in Reactor Materials
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1969 The production of inert gases by irradiation gives rise to various consequential effects on reactor materials such as swelling, fission product release and high temperature embrittlement. A review is presented on the production and the behavior of inert gases in reactor materials.
Yoshitsugu MISHIMA, Shiori ISHINO
openaire +2 more sources
Fabrication of nanometre sized gratings via ion irradiation [PDF]
EPJ Web of Conferences, 2023 The damage caused by irradiation of crystalline material with ions results in localized volume changes. Here, swelling is utilized to fabricate nanostructured gratings with heights below 10 nm for extreme ultraviolet radiation.
Kaufmann Johannes +2 more
doaj +1 more source
Effect of High helium Content on Stainless-Steel Swelling
Nuclear Technology, 1975 Type 316 stainless-steel specimens have been irradiated in the High Flux Isotope Reactor at temperatures between 380 and 680°C to displacement damage levels up to 120 displacements per atom and tra...
F. W. Wiffen, E. E. Bloom
openaire +3 more sources
Materials & Design, 2022 The level of chromium plays an essential role in irradiation tolerance of Fe-Cr ferritic alloys. However, conflicting results have been reported regarding the dependence of cavity swelling under irradiation on Cr level and temperature.
Yan-Ru Lin +6 more
doaj +1 more source
Predicting structural material degradation in advanced nuclear reactors with ion irradiation
Scientific Reports, 2021 Swelling associated with the formation and growth of cavities is among the most damaging of radiation-induced degradation modes for structural materials in advanced nuclear reactor concepts.
Stephen Taller +3 more
doaj +1 more source