作者: U. Engman , B. Holmqvist
DOI: 10.1080/00337577508239480
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摘要: Abstract Since a few years ago it has been well known1 that reactor construction materials which are exposed to high neutron fluences, i.e. about 1022 neutrons/cm2, will undergo density changes caused by creation and growth of voids. The void formation is accompanied swelling the material, an effect can be as large several per cent. However, takes more than year irradiation time in flux reach necessary dose for such effects making systematic studies very consuming. It therefore convenient simulate radiation damage, instance ion implantation, using fact cross section ion-nucleus interaction orders magnitude larger neutron-nucleus interaction. Thus damage comparable with obtained produced after only hours or days accelerator irradiation.