In:
Advanced Materials Research, Trans Tech Publications, Ltd., Vol. 996 ( 2014-8), p. 22-26
Kurzfassung:
Oxide dispersive steel is a promising material for next nuclear reactors generation. Performance of this material in nuclear reactor can be modeled by means of irradiation by swift Bi ions, which are typical nuclear fusion products. Radiation damage results in microstructure alternation leading to formation of micro and macro stresses that influence the material performance. The residual stress state of ferrite matrix of the steel is investigated by XRD methodic and dependence on the irradiation dose is analyzed.
Materialart:
Online-Ressource
ISSN:
1662-8985
DOI:
10.4028/www.scientific.net/AMR.996
DOI:
10.4028/www.scientific.net/AMR.996.22
Sprache:
Unbekannt
Verlag:
Trans Tech Publications, Ltd.
Publikationsdatum:
2014
ZDB Id:
2265002-7
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