Online ISSN : 1347-5320
Print ISSN : 1345-9678
ISSN-L : 1345-9678
Integrated Material System Modeling of Fusion Blanket
A. SagaraR. NygrenM. MiyamotoD. NishijimaR. DoernerS. FukadaY. OyaT. OdaY. WatanabeK. MorishitaF. GaoT. Norimatsu
Author information
JOURNALS FREE ACCESS Advance online publication

Article ID: MG201210

This article has a public article.

The blanket of fusion reactors is a multifunctional system that breeds tritium, harvests heat from the burning plasma, and protects the other components and the environment. The common task in the US-J TITAN (Tritium, Irradiation and Thermofluid for America and Nippon) project identifies cross-linked considerations in the blanket system modeling on the basis of the material research in each task. In this paper, we review the main outputs of this task: elucidation of the effect of helium on deuterium retention in the tungsten wall, analysis of tritium transfer in a Pb–Li liquid breeder, experimental and computational studies on the effects of radiation damage on hydrogen trapping, and modeling of the tritium barrier in a double-tube heat exchanger.

Information related to the author
© 2013 The Japan Institute of Metals and Materials