Helium effects on irradiation assisted stress corrosion cracking susceptibility of 316L austenitic stainless steel
Graph Chatbot
Chat with Graph Search
Ask any question about EPFL courses, lectures, exercises, research, news, etc. or try the example questions below.
DISCLAIMER: The Graph Chatbot is not programmed to provide explicit or categorical answers to your questions. Rather, it transforms your questions into API requests that are distributed across the various IT services officially administered by EPFL. Its purpose is solely to collect and recommend relevant references to content that you can explore to help you answer your questions.
The effects of neutron irradiation on austenitic stainless steels, usually used for the manufacturing of internal elements of nuclear reactors (e.g. the core shrouds), are the alteration of the microchemistry and the microstructure, and, as a consequence, ...
Nuclear materials have been successfully employed in commercial fission reactors for many decades. Research and material development for advanced fission system and future thermo-nuclear fusion reactors have acquired maturity while great challenges remain ...
Molecular dynamics is used to examine the deformation and failure of Al-Si interfaces and of nanocomposites consisting of Al and Si nanograins loaded in tension. The modified embedded atom method, is used to describe the forces and energies in the system a ...
A continuum model of nanocrystalline copper was developed based on results from independent atomistic calculations on 11 bicrystals containing high angle grain boundaries. The relationship between grain boundary structure and its mechanical response was in ...
Mechanisms responsible for the embrittlement of leaded "free-machining" copper alloys at intermediate temperatures (i.e. around 400 °C) are examined using a combination of microstructural and mechanical characterization. Tensile tests are conducted on pure ...
Irradiation is known to lead to a degradation of the mechanical properties of materials. This is particularly crucial in the case of materials that will be used in the future thermonuclear fusion reactor, where extremely high irradiation doses are expected ...
The fracture strength of silicon nanowires grown on a [111] silicon substrate by the vapor-liquid-solid process was measured. The nanowires, with diameters between 100 and 200 nm and a typical length of 2 μm, were subjected to bending tests using an atomic ...
Oxide dispersion strengthened (ODS) ferritic steels are investigated as possible structural material for the future generation of high temperature gas cooled nuclear reactors. ODS-steels are considered to replace other high temperature materials for tubing ...
We present an atomistic study of the plastic deformation mechanisms occurring in columnar structures of nanocrystalline Ni, with particular emphasis on the process of dislocation emission form the grain boundaries. The samples are constructed with grain bo ...
Tensile properties and microstructure of Danocrystalline electrodeposited Ni at temperatures between room temperature and 330° C are presented. Above 300° C low flow stress and high tensile elongation are observed along with grain growth and segreg ...
