M. Rödig

Strategies for improving the sustainability of structural metals

Accident tolerant fuels for LWRs: A perspective

Materials for the plasma-facing components of fusion reactors

Material erosion and erosion products under plasma heat loads typical for ITER hard disruptions

Manufacturing and testing of a prototypical divertor vertical target for ITER

Performance of the different tungsten grades under fusion relevant power loads

Assessment and selection of materials for ITER in-vessel components

Structural materials for fission & fusion energy

Armour Materials for the ITER Plasma Facing Components

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Low-temperature low-dose neutron irradiation effects on beryllium

Handbook of SiC properties for fuel performance modeling

Critical heat flux analysis and R&D for the design of the ITER divertor

Radiation Effects in Refractory Alloys

Recent Developments in Irradiation-Resistant Steels

Materials challenges in nuclear energy

Testing of actively cooled high heat flux mock-ups

European development of the ITER divertor target

Material damage to beryllium, carbon, and tungsten under severe thermal shocks

Overview of EU CFCs development for plasma facing materials

Erosion of metals and carbon based materials during disruptions — simulation experiments in plasma accelerators

Carbon fiber composites application in ITER plasma facing components

Performance of beryllium, carbon, and tungsten under intense thermal fluxes

Neutron irradiation effects on plasma facing materials