Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor

Grain boundary (GB) oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor was investigated. The investigation was conducted by studying microstructure of the oxide and oxide precursor formed at GB on an "atom-by-atom" basis by a comb...

Descripción completa

Detalles Bibliográficos
Autores principales: Deng, Ping, Peng, Qunjia, Han, En-Hou
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Nature Publishing Group UK 2021
Materias:
Article
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC7809272/
https://www.ncbi.nlm.nih.gov/pubmed/33446760
http://dx.doi.org/10.1038/s41598-020-80600-x
_version_ 1783637086492950528
author Deng, Ping
Peng, Qunjia
Han, En-Hou
author_facet Deng, Ping
Peng, Qunjia
Han, En-Hou
author_sort Deng, Ping
collection PubMed
description Grain boundary (GB) oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor was investigated. The investigation was conducted by studying microstructure of the oxide and oxide precursor formed at GB on an "atom-by-atom" basis by a combination of atom-probe tomography and transmission electron microscope. The results revealed that increasing irradiation dose promoted the GB oxidation, in correspondence with a different oxide and oxide precursor formed at the GB. Correlation of the oxide and oxide precursor with the GB oxidation behavior has been discussed in detail.
format Online
Article
Text
id pubmed-7809272
institution National Center for Biotechnology Information
language English
publishDate 2021
publisher Nature Publishing Group UK
record_format MEDLINE/PubMed
spelling pubmed-78092722021-01-15 Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor Deng, Ping Peng, Qunjia Han, En-Hou Sci Rep Article Grain boundary (GB) oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor was investigated. The investigation was conducted by studying microstructure of the oxide and oxide precursor formed at GB on an "atom-by-atom" basis by a combination of atom-probe tomography and transmission electron microscope. The results revealed that increasing irradiation dose promoted the GB oxidation, in correspondence with a different oxide and oxide precursor formed at the GB. Correlation of the oxide and oxide precursor with the GB oxidation behavior has been discussed in detail. Nature Publishing Group UK 2021-01-14 /pmc/articles/PMC7809272/ /pubmed/33446760 http://dx.doi.org/10.1038/s41598-020-80600-x Text en © The Author(s) 2021, corrected publication 2021 https://creativecommons.org/licenses/by/4.0/Open Access This article is licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons licence, and indicate if changes were made. The images or other third party material in this article are included in the article's Creative Commons licence, unless indicated otherwise in a credit line to the material. If material is not included in the article's Creative Commons licence and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this licence, visit http://creativecommons.org/licenses/by/4.0/ (https://creativecommons.org/licenses/by/4.0/) .
spellingShingle Article
Deng, Ping
Peng, Qunjia
Han, En-Hou
Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_full Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_fullStr Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_full_unstemmed Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_short Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_sort grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
topic Article
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC7809272/
https://www.ncbi.nlm.nih.gov/pubmed/33446760
http://dx.doi.org/10.1038/s41598-020-80600-x
work_keys_str_mv AT dengping grainboundaryoxidationofprotonirradiatednucleargradestainlesssteelinsimulatedprimarywaterofpressurizedwaterreactor
AT pengqunjia grainboundaryoxidationofprotonirradiatednucleargradestainlesssteelinsimulatedprimarywaterofpressurizedwaterreactor
AT hanenhou grainboundaryoxidationofprotonirradiatednucleargradestainlesssteelinsimulatedprimarywaterofpressurizedwaterreactor

Ejemplares similares