Preliminary assessment of the safety factors in K-DEMO for fusion compatible regulatory framework. [PDF]
Kim BS, Hong SH, Kim K.
europepmc +1 more source
Direct Tungsten/Copper Bonding for Divertor Application
We carried out a fundamental investigation of a uniaxial direct W-to-Cu bonding at relatively low temperatures in ambient air, which would potentially allow for simple preparation and maintenance of divertor wall components. W/Cu bonds formed at 500◦C with a bonding pressure of 0.1 MPa, but the mechanical interfacial strength was about 1 MPa ...
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Exploring FAST Technique for Diffusion Bonding of Tungsten to EUROFERE97 in DEMO First Wall. [PDF]
Sánchez M +4 more
europepmc +1 more source
A high-density and high-confinement tokamak plasma regime for fusion energy. [PDF]
Ding S +20 more
europepmc +1 more source
Thermal Stability and Irradiation Resistance of (CrFeTiTa)<sub>70</sub>W<sub>30</sub> and VFeTiTaW High Entropy Alloys. [PDF]
Pereira A +7 more
europepmc +1 more source
Four-dimensional conditional averaging tomography of rotating plasma ejection from cylindrical detached plasma. [PDF]
Tanaka H, Kajita S, Natsume H, Ohno N.
europepmc +1 more source
Characterization of Tungsten Sputtering in the JET Divertor
van Rooij, G.J. +19 more
openaire +3 more sources
Modelling the Impact of Argon Atoms on a WO3 Surface by Molecular Dynamics Simulations. [PDF]
Shermukhamedov S, Maihom T, Probst M.
europepmc +1 more source
Computational design of ductility and phase stability in W-Ti-V-Cr refractory multiprincipal element alloys for fusion applications. [PDF]
Pitike KC +3 more
europepmc +1 more source
Development of tungsten divertor components for ITER in Japan
The refined design of full-W ITER divertor outer vertical targets (OVT) has the combination of plasma-facing units (PFUs) variants with bevelled W onoblocks to prevent leading edge overheating. Full-length PFU prototypes have withstood against the repetitive heat load of 20MW/m2 and they met the requirements for W technologies qualification programed ...
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