J.-F. Salavy

Breeding Blanket Modules testing in ITER: An international program on the way to DEMO

Binder jet 3D printing—Process parameters, materials, properties, modeling, and challenges

Supercritical carbon dioxide cycles for power generation: A review

Current status and critical issues for development of SiC composites for fusion applications

Limits on irradiation-induced thermal conductivity and electrical resistivity in silicon carbide materials

Structural materials for fission & fusion energy

Supercritical CO2 Brayton power cycles for DEMO fusion reactor based on Helium Cooled Lithium Lead blanket

Design, preparation and properties of non-oxide CMCs for application in engines and nuclear reactors: an overview

Handbook of SiC properties for fuel performance modeling

Molecular dynamics simulation of alloying during sintering of Li and Pb metallic nanoparticles

Friction stir welding/processing of metals and alloys: A comprehensive review on microstructural evolution

Critical issues and current status of SiC/SiC composites for fusion

Supercritical CO2 Brayton power cycles for DEMO (demonstration power plant) fusion reactor based on dual coolant lithium lead blanket

The metallurgical bonding and high temperature tensile behaviors of 9Cr-1W steel and 316L steel dissimilar joint by friction stir welding

Ferritic–Martensitic steel Test Blanket Modules: Status and future needs for design criteria requirements and fabrication validation

Overview of liquid metal TBM concepts and programs

R&D issues for SiCf/SiC composites structural material in fusion power reactor blankets

Tauro: a ceramic composite structural material self-cooled Pb—17Li breeder blanket concept

Design requirements for SiC/SiC composites structural material in fusion power reactor blankets

The EU advanced lead lithium blanket concept using SiCf/SiC flow channel inserts as electrical and thermal insulators

The European test blanket module systems: Design and integration in ITER

Present status of the conceptual design of the EU test blanket systems

Objectives feasibility assessment of the water-cooled lithium–lead mock-up testing in ITER