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. [...]

Corrosion behaviour of ODS Cr-based steels in liquid lead

S Amore;D Giuranno;G Canu;R Novakovic;E Ricci
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. [...]
2016
Istituto di Chimica della Materia Condensata e di Tecnologie per l'Energia - ICMATE
Istituto di Chimica della Materia Condensata e di Tecnologie per l'Energia - ICMATE
ODS
steel
nuclear materials
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/318560
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