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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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1-s2.0-S0010938X24000866-main.pdf | Published version | 11.66 MB | Adobe PDF | View/Open |
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 |
This item is licensed under a Creative Commons License