Advanced lithium-rich ceramic materials are under consideration for the helium cooled pebble-bed breeder unit prototype in ITER. Although chemical compatibility issues with reduced activation steels have in general been associated with liquid breeders, corrosion has also been observed to be produced by some solid compositions under specific conditions. In this work, the mechanisms including the corrosion process considering different lithium ceramics (lithium orthosilicate and lithium metatitanate) are examined, together with the influence of temperature and exposure time. The effect of the composition of the purge gas, intended for tritium extraction, is also evaluated. Corrosion in Eurofer was found to severely occur for metatitanate comp...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....
In order to investigate the chemical compatibility between tritium breeder Li2TiO3 pebbles and triti...
The pebbles of Li2TiO3 with excess Li, which is in a developmental stage in JAEA (Japan Atomic Energ...
In a solid breeding blanket, ceramic breeder pebbles are in contact with reduced activation ferritic...
In a solid breeding blanket, ceramic breeder pebbles are in contact with reduced activation ferritic...
6 pags., 7 figs., 2 tabs.This paper is concerned with the identification of the corrosive phase form...
A possible concept for the blanket for next generation fusion devices is the lithium salt blanket, w...
The aim of this work was to study resistance to helium accumulation processes in the structure of th...
The interest in lithium-containing ceramics is due to their huge potential as blanket materials for ...
The interest in lithium-containing ceramics is due to their huge potential as blanket materials for ...
The breeding blanket is a key component of the fusion reactor since it involves tritium breeding and...
The chemical compatibility between Li4SiO4 pebbles and ODS steel is important for the safe operation...
Strict control of tritium migration is an essential requirement for every blanket concept in a fusio...
The use of ferritic/martensitic RAFM steels in PbLi blanket applications requires a better understan...
AbstractLithium orthosilicate (Li4SiO4) ceramics in from of pebble bed is the European candidate for...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....
In order to investigate the chemical compatibility between tritium breeder Li2TiO3 pebbles and triti...
The pebbles of Li2TiO3 with excess Li, which is in a developmental stage in JAEA (Japan Atomic Energ...
In a solid breeding blanket, ceramic breeder pebbles are in contact with reduced activation ferritic...
In a solid breeding blanket, ceramic breeder pebbles are in contact with reduced activation ferritic...
6 pags., 7 figs., 2 tabs.This paper is concerned with the identification of the corrosive phase form...
A possible concept for the blanket for next generation fusion devices is the lithium salt blanket, w...
The aim of this work was to study resistance to helium accumulation processes in the structure of th...
The interest in lithium-containing ceramics is due to their huge potential as blanket materials for ...
The interest in lithium-containing ceramics is due to their huge potential as blanket materials for ...
The breeding blanket is a key component of the fusion reactor since it involves tritium breeding and...
The chemical compatibility between Li4SiO4 pebbles and ODS steel is important for the safe operation...
Strict control of tritium migration is an essential requirement for every blanket concept in a fusio...
The use of ferritic/martensitic RAFM steels in PbLi blanket applications requires a better understan...
AbstractLithium orthosilicate (Li4SiO4) ceramics in from of pebble bed is the European candidate for...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....
In order to investigate the chemical compatibility between tritium breeder Li2TiO3 pebbles and triti...
The pebbles of Li2TiO3 with excess Li, which is in a developmental stage in JAEA (Japan Atomic Energ...