A5008237555- Fusion materials and technologies
- Nuclear Materials and Properties
- Ion-surface interactions and analysis
- Magnetic confinement fusion research
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- High Temperature Alloys and Creep
- Nuclear Physics and Applications
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Superconducting Materials and Applications
- Nuclear materials and radiation effects
CEA Cadarache
2024
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
Forschungszentrum Jülich
2016-2021
Abstract The paper reports the first demonstration of in situ laser-induced desorption — quadrupole mass spectrometry (LID-QMS) application on a large scale fusion device performed summer 2023. LID-QMS allows direct measurements fuel inventory plasma facing components without retrieving them from device. diagnostic desorbs retained gases by heating 3 mm diameter spot wall using 1 ms long laser pulse and detects QMS. Thus, it can measure gas content at any position accessible to laser....
This study combines both transmutational changes and accelerated damage by simulation of irradiating tungsten with 16, 30 45 MeV protons. Comparative results indicate to be most optimal amongst the three, for uniformity combined damage. Finally, were compared against fission reactor calculations DEMO relevant compositional changes. Using protons, damages 1 dpa equivalent, rhenium content is calculated as 401 appm. compares well appm induced within a better than estimated 50,000 reactor....
Materials are the most urgent issue in nuclear fusion research. Besides tungsten, steels considered for unifying functional and structural materials due to their cost mechanical advantages over tungsten. However, neutrons impose a strong constraint on ingredients of steel order avoid long lasting activation, while material has pertain sputtering resistance, low hydrogen retention, long-term stability. In this proof-of-principle, we demonstrate interesting properties new HiperFer (High...
Nuclear fusion plasma-facing materials (PFM) will suffer from irradiation, leading to significant changes in the material properties. This study investigates impact of displacement damage on deuterium retention near room temperature. ITER grade tungsten, Eurofer-97, and HiperFer 17Cr5 steel samples are irradiated with a tandem accelerator ~3 MeV protons at currents 100–600 nA 250–550 µm spots 320±10 K. In total 33 0 0.9 displacements per atom (DPA) 0–4 depth 5 samples. After exposed D2...
Tungsten samples have been irradiated with 3 MeV protons dose rates of 1×10-04 to 5×10-05 dpa/s doses 0.01–0.67 dpa at 360 K in a pilot experiment. Micro- and macro-indentation were used measure irradiation hardening the samples. An initial 1.23 ± 0.09 GPa 1.88 0.83 was measured by micro macro indentation. The observed saturate 0.03 damage. Dislocation loops identified using TEM suggesting an increasing loop size dose.
Abstract 16 MeV protons have been used to irradiate 300 μ m thick macroscopic W samples in a pilot experiment 0.006 dpa damage dose under low and high temperature scenarios of ∼373 K ∼1223 K, respectively. The linear pre-Bragg region has for where the electronic loss (heat) sample amounts 1.5 MW · −2 . Post high-temperature irradiation, recrystallized as seen scanning electron microscope. Indentation measurements on surface show softening 0.6 GPa post-recrystallization against an irradiation...