Self-passivating W-Cr-Y alloys as plasma-facing materials: Effect of Zr addition on fusion relevant properties; study of hydrogen retention, neutron irradiation and joining feasibility to steel.

Self-passivating W-Cr-Y alloys as plasma-facing materials: Effect of Zr addition on fusion relevant properties; study of hydrogen retention, neutron irradiation and joining feasibility to steel.

The selection of the material for the blanket first wall (FW) is one of the crucial aspects to overcome in the framework of the EUROfusion program towards DEMO. In this reactor, a loss-ofcoolant accident (LOCA) with simultaneous air ingress into the vacuum vessel would lead to temperatures of the...

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Bibliographic Details
Main Authors: Sal Broco, E. (Elisa), Garcia-Rosales, C. (Carmen)
Format: info:eu-repo/semantics/doctoralThesis
Language:eng
Published: Servicio de publicaciones. Universidad de Navarra 2022
Subjects:
Nuclear fusion energy
DEMO reactor
Self-passivating alloys
Tungsten
Oxidation
Joining feasibility
Hydrogen retention
Neutron irradiation
Online Access:https://hdl.handle.net/10171/64528

Internet

https://hdl.handle.net/10171/64528

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