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Irradiation-induced hardening and loss of ductility of ferritic/martensitic materials envisaged for future fusion reactor is still difficult to understand. In particular, helium (He), produced by transmutation by the fusion neutrons of 14 MeV, is known to ...
A methodology is presented for the accurate assessment of the fast neutron fluence at the reactor pressure vessel (RPV) of a pressurised water reactor (PWR). The basis is the transfer of results from deterministic CASMO-4/SIMULATE-3 core-follow calculation ...
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, ...
Nanostructured materials should present a good resistance to irradiation because the large volume fraction of grain boundaries can be an important sink for radiation-induced defects. The objective of the present study is to experimentally investigate the i ...
A high-fluence proton irradiation of neptunium was the last experiment in PSIs programme ATHENA related to accelerator-based transmutation. The principal aim of the programme has been to provide experimental data for the validation of theoretical models in ...
We propose a spectral prediction model for predicting the reflectance and transmittance of recto-verso halftone prints. A recto-verso halftone print is modeled as a diffusing substrate surrounded by two inked interfaces in contact with air (or with another ...
Molecular dynamics (MD) simulation of displacement cascades in Fe-0.1%He are used to investigate the synergistic effects of primary knock-on atoms (PKA) and He on the irradiation damage production at temperatures between 10 K and 523 K. The results indicat ...
Radiation tests of 32 μm thick hydrogenated amorphous silicon n-i-p diodes have been performed using a high- energy 24 GeV proton beam up to fluences of 2x1016 protons/cm2. The results are compared to irradiation of similar 1 μm and 32 μm thick n-i-p diode ...
Charpy impact tests were performed on martensitic/ferritic (MF) steels T91, F82H, Optifer-V and Optimax-A/-C irradiated in SINQ Target-3 up to 7.5 dpa and 500 appm He in a temperature range of 120-195 degrees C. Results demonstrate that for all the four ki ...
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 ...