Publication Date:
2016
abstract:
Corrosion behaviour of ferritic and ferritic-martensitic oxide dispersed strengthened (ODS) steels woth different chromium content (9, 12 and 14 % Cr) have been tested in stagnant liquid lead with an oxygen concentration cO2 = 10-6 wt%. The study has been carried out with the aim to identify the most appropriate structural materials for advanced nuclear energy system and waste transmutation system.
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Iris type:
04.06 Keynote o lezione magistrale
Keywords:
ODS; steel; nuclear materials
List of contributors: