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Corrosion of 316L exposed to highly concentrated borated water used as shield in nuclear fusion experimental reactors cooling circuits

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Title: Corrosion of 316L exposed to highly concentrated borated water used as shield in nuclear fusion experimental reactors cooling circuits
Authors: Gasparrini, C
Douglas, JO
Yazdanpanah, A
Stroud, R
Divitini, G
Dabalà, M
Scatigno, GG
Pedrazzini, S
Wenman, MR
Badocco, D
Pastore, P
Terranova, N
Mariano, G
Dacquait, F
Palma, MD
Villari, R
Sonato, P
Item Type: Journal Article
Abstract: Borated water is used as a shield in nuclear fusion cooling circuits. General corrosion, activated corrosion products (ACPs) formation and stress corrosion cracking initiation of 316 L steels exposed to ultrapure water (UPW) or 8000 ppm B water at 80 °C were tested. A Ni enriched sub-oxide layer, a transition layer and oxide layer were observed using advanced characterisation (STEM-EELS, APT). The oxide formed in UPW was protective (Cr:O 40:45), the oxide formed in 8000 ppm B was non-passivating. 8000 ppm B led to higher release of Fe, Cr and Mo, 316 L was more prone to SCC initiation and enhanced ACPs formation.
Issue Date: 15-Apr-2024
Date of Acceptance: 4-Feb-2024
URI: http://hdl.handle.net/10044/1/110074
DOI: 10.1016/j.corsci.2024.111902
ISSN: 0010-938X
Publisher: Elsevier
Journal / Book Title: Corrosion Science
Volume: 230
Copyright Statement: © 2024 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY license (http://creativecommons.org/licenses/by/4.0/).
Publication Status: Published
Article Number: 111902
Online Publication Date: 2024-02-08
Appears in Collections:Materials



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