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Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel

Corrosion of aluminium alloy clad nuclear fuel, during reactor operation and under subsequent wet storage conditions, promotes the formation of aluminium hydroxide and oxyhydroxide layers. These hydrated mineral phases and the chemisorbed and physisorbed waters on their surfaces are susceptible to r...

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Autores principales: Conrad, Jacy K., Pu, Xiaofei, Khanolkar, Amey, Copeland-Johnson, Trishelle M., Pilgrim, Corey D., Wilbanks, Joseph R., Parker-Quaife, Elizabeth H., Horne, Gregory P.
Formato: Online Artículo Texto
Lenguaje:English
Publicado: MDPI 2022
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9607483/
https://www.ncbi.nlm.nih.gov/pubmed/36295382
http://dx.doi.org/10.3390/ma15207317
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author Conrad, Jacy K.
Pu, Xiaofei
Khanolkar, Amey
Copeland-Johnson, Trishelle M.
Pilgrim, Corey D.
Wilbanks, Joseph R.
Parker-Quaife, Elizabeth H.
Horne, Gregory P.
author_facet Conrad, Jacy K.
Pu, Xiaofei
Khanolkar, Amey
Copeland-Johnson, Trishelle M.
Pilgrim, Corey D.
Wilbanks, Joseph R.
Parker-Quaife, Elizabeth H.
Horne, Gregory P.
author_sort Conrad, Jacy K.
collection PubMed
description Corrosion of aluminium alloy clad nuclear fuel, during reactor operation and under subsequent wet storage conditions, promotes the formation of aluminium hydroxide and oxyhydroxide layers. These hydrated mineral phases and the chemisorbed and physisorbed waters on their surfaces are susceptible to radiation-induced processes that yield molecular hydrogen gas (H(2)), which has the potential to complicate the long-term storage and disposal of aluminium clad nuclear fuel through flammable and explosive gas mixture formation, alloy embrittlement, and pressurization. Here, we present a systematic study of the radiolytic formation of H(2) from aluminium alloy 1100 (AA1100) and 6061 (AA6061) coupons in “dry” (~0% relative humidity) and “wet” (50% relative humidity) helium environments. Cobalt-60 gamma irradiation of both aluminium alloy types promoted the formation of H(2), which increased linearly up to ~2 MGy, and afforded G-values of 1.1 ± 0.1 and 2.9 ± 0.1 for “dry” and “wet” AA1100, and 2.7 ± 0.1 and 1.7 ± 0.1 for “dry” and “wet” AA6061. The negative correlation of H(2) production with relative humidity for AA6061 is in stark contrast to AA1100 and is attributed to differences in the extent of corrosion and varying amounts of adsorbed water in the two alloys, as characterized using optical profilometry, scanning electron microscopy, Raman spectroscopy, and X-ray diffraction techniques.
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spelling pubmed-96074832022-10-28 Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel Conrad, Jacy K. Pu, Xiaofei Khanolkar, Amey Copeland-Johnson, Trishelle M. Pilgrim, Corey D. Wilbanks, Joseph R. Parker-Quaife, Elizabeth H. Horne, Gregory P. Materials (Basel) Article Corrosion of aluminium alloy clad nuclear fuel, during reactor operation and under subsequent wet storage conditions, promotes the formation of aluminium hydroxide and oxyhydroxide layers. These hydrated mineral phases and the chemisorbed and physisorbed waters on their surfaces are susceptible to radiation-induced processes that yield molecular hydrogen gas (H(2)), which has the potential to complicate the long-term storage and disposal of aluminium clad nuclear fuel through flammable and explosive gas mixture formation, alloy embrittlement, and pressurization. Here, we present a systematic study of the radiolytic formation of H(2) from aluminium alloy 1100 (AA1100) and 6061 (AA6061) coupons in “dry” (~0% relative humidity) and “wet” (50% relative humidity) helium environments. Cobalt-60 gamma irradiation of both aluminium alloy types promoted the formation of H(2), which increased linearly up to ~2 MGy, and afforded G-values of 1.1 ± 0.1 and 2.9 ± 0.1 for “dry” and “wet” AA1100, and 2.7 ± 0.1 and 1.7 ± 0.1 for “dry” and “wet” AA6061. The negative correlation of H(2) production with relative humidity for AA6061 is in stark contrast to AA1100 and is attributed to differences in the extent of corrosion and varying amounts of adsorbed water in the two alloys, as characterized using optical profilometry, scanning electron microscopy, Raman spectroscopy, and X-ray diffraction techniques. MDPI 2022-10-19 /pmc/articles/PMC9607483/ /pubmed/36295382 http://dx.doi.org/10.3390/ma15207317 Text en © 2022 by the authors. https://creativecommons.org/licenses/by/4.0/Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (https://creativecommons.org/licenses/by/4.0/).
spellingShingle Article
Conrad, Jacy K.
Pu, Xiaofei
Khanolkar, Amey
Copeland-Johnson, Trishelle M.
Pilgrim, Corey D.
Wilbanks, Joseph R.
Parker-Quaife, Elizabeth H.
Horne, Gregory P.
Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel
title Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel
title_full Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel
title_fullStr Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel
title_full_unstemmed Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel
title_short Radiolytic Gas Production from Aluminum Coupons (Alloy 1100 and 6061) in Helium Environments—Assessing the Extended Storage of Aluminum Clad Spent Nuclear Fuel
title_sort radiolytic gas production from aluminum coupons (alloy 1100 and 6061) in helium environments—assessing the extended storage of aluminum clad spent nuclear fuel
topic Article
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9607483/
https://www.ncbi.nlm.nih.gov/pubmed/36295382
http://dx.doi.org/10.3390/ma15207317
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