According to the most recently revised European design strategy for DEMO breeding
blankets, mature concepts have been identified that require a reduced technological …

Abstract Ni-Mo-Cr alloys (Hastelloy N and Hastelloy X) having different Mo/Cr ratio were
exposed to FLiNaK salt at 973 K for 72 h in an in-house developed static corrosion test …

Dissimilar materials interactions are a major concern when liquid metals are used as a
working fluid. To simulate a dual-coolant PbLi blanket, chemical vapor deposited (CVD) SiC …

The long-term corrosion behavior of IN-RAFM steel in molten Pb-Li upto 10, 000 h of
exposure was studied in a rotating disc corrosion test facility at 823 K. As-received IN …

This paper represents a part of the research of structural materials for fusion systems. The
performance of a conventionally formed Eurofer-97 steel and its Sc-Y-ODS variant …

Abstract Information as concerning the compatibility of EUROFER97, or other martensitic
steels, and liquid lead–lithium eutectic is collected and evaluated. The best part addresses …

Abstract Liquid Pb-16Li eutectic alloy is the tritium breeding material in several breeding
blanket concepts for European DEMO reactor, which are the Helium-Cooled Lithium-Lead …

The liquid lead-lithium (Pb–17Li) blanket has many applications in fusion reactors due to its
good tritium breeding performance, high heat transfer efficiency and safety. The compatibility …

Liquid PbLi blanket is one of the promising designs for fusion reactor, which requires tritium
permeation barriers (TPBs) with higher corrosion resistance. The corrosion behavior under …

The liquid lead lithium blanket is considered to be one of the most promising blanket
concepts. Oxide Dispersion Strengthened (ODS) steel probably emerge as an important …