M. Rieth

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

P. F. Morris, B. Raj, S. Zinkle, 2014, 1408.3546.

Increasing Irradiation and Thermo-Hydraulic Performance of Breeding Blankets by ODS Steel Plating

S. Antusch, G. Pintsuk, Y. Carlan, 2022 .

Towards reduced activation structural materials data for fusion DEMO reactors

Reinhard Pippan, H.-C. Schneider, E. Diegele, 2005 .

Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation

M. Rieth, Y. Katoh, L. Snead, 2021, Fusion Engineering and Design.

Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications

Steven J. Zinkle, Michael Rieth, G. R. Odette, 2017 .