[go: up one dir, main page]

Wu et al., 1990 - Google Patents

Erosion of beryllium by oxygen

Wu et al., 1990

Document ID
17737970366708468050
Author
Wu C
Hechtl E
Yang H
Eckstein W
Publication year
Publication venue
Journal of nuclear materials

External Links

Snippet

Beryllium has been seriously considered as a plasma-facing material because of its low Z, favourable thermomechanical properties and expected low tritium retention. However, erosion by plasma and impurities is another important issue in assessing its suitability for …
Continue reading at www.sciencedirect.com (other versions)

Similar Documents

Publication Publication Date Title
Roth et al. Erosion of carbon due to bombardment with energetic ions at temperatures up to 2000 K
Roth et al. Mechanism of enhanced sputtering of carbon at temperatures above 1200 C
Rohde Reduction of the thermal conductivity of SiC by radiation damage
Wu et al. Erosion of beryllium by oxygen
Behrisch Plasma-facing materials for fusion devices
Hino et al. Evaluation for boron mixed graphite and high Z metal as plasma facing material
Hechtl et al. An experimental study of tungsten self sputtering
Wolfer et al. An assessment of radiation effects in beryllium
Snead Fusion energy applications
Roth et al. Search for low-erosion carbon materials
Hassanein et al. Beryllium and graphite performance in ITER during a disruption
MacFarlane et al. Analysis of Physical Processes in ICF Target Chambers: Application to the Laboratory Microfusion Facility
Wu et al. Erosion of tungsten by self-sputtering and light ion irradiation at oblique angles of incidence
Moses et al. First-wall protection in particle-beam fusion reactors by inert cavity gases
MacFarlane et al. Non-LTE effects in inertial confinement fusion target chambers
Conn Relation of surface interactions to first-wall and in-vessel-component (IVC) design and materials performance in fusion devices
Goel et al. Proton stopping in thin aluminum slabs
Mattas et al. Materials selection for the US INTOR divertor collector plate
Wu The angular dependence of physical sputtering of graphite by light ions in the low-energy regime
Vietzke Isotope dependence of the chemical erosion of graphite by hydrogen/deuterium implantation
Wilson et al. Deuterium trapping measurements in aluminum and plasma-sprayed aluminum coatings
Hopkins et al. Carbon and silicon carbide as first wall materials in inertial confinement fusion reactors
Peterson Analysis of cavity gas conditions in heavy-ion beam fusion reactors
Bourham et al. Erosion of plasma-facing components under simulated disruption-like conditions using an electrothermal plasma gun
Yanagihara et al. Helium retention properties of plasma facing materials