Sensitivity study of coupled chemical-CFD simulations for analyzing aluminum-clad spent nuclear fuel storage in sealed canisters

Abboud, Alexander W.

doi:10.1016/j.nucengdes.2022.111691

Cited by 10 publications

(13 citation statements)

References 19 publications

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“…This includes sealed and vented dry storage configurations of ATR and other ASNF types within canisters with different backfill gases, such as He. 23,24,25,26,27,28,29 All work completed to close this knowledge gap supports the conclusion that extended ASNF dry storage is both safe and viable.…”

Section: Resolution Of Radiolytic Gas Generation Data For Asnfmentioning

confidence: 80%

Technical basis for extended dry storage of aluminum-clad spent nuclear fuel

Eidelpes

Jarrell

Lister

et al. 2023

Journal of Nuclear Materials

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Section: Resolution Of Radiolytic Gas Generation Data For Asnfmentioning

confidence: 80%

Technical basis for extended dry storage of aluminum-clad spent nuclear fuel

Eidelpes

Jarrell

Lister

et al. 2023

Journal of Nuclear Materials

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“…Overall, the presented G (H 2 ) He values are important for the development of predictive computer models for evaluating the feasibility of extended storage of ASNF in He backfilled canisters [ 53 ].…”

Section: Discussionmentioning

confidence: 99%

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

Conrad

Khanolkar

et al. 2022

Materials

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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 (H2), 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 H2 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 H2, 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 H2 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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“…A summary of previously constructed model is provided. More in depth details are provided in other reports (Abboud and Huang 2019a;Abboud and Huang 2019b). There are only three main changes to the model made here.…”

Section: Theory and Model Descriptionmentioning

confidence: 99%

“…Many of these CFD models have not coupled the thermal and convective fields with the harmful chemical species which occur due to the radiolytic breakdown of water vapor, nitrogen, oxygen and carbon dioxide that can be within canisters (Wittman and Hanson 2015;Arkhipov et al 2007;Atkinson et al 2004). The developed transient model that is used here allows for one-way coupling of the transient thermal environment of the DOE sealed canisters with the full set of radiolytic chemical reactions for both gas phase and surface phase chemistry (Abboud and Huang 2019a;Abboud and Huang 2019b).…”

Section: Introductionmentioning

confidence: 99%

Modeling of ATR fuel in DOE Standard Canisters with Helium Backfilled Condition

Abboud

2021

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Road-ready and final disposition packaging configurations for the advanced test reactor (ATR) fuel dictates storage within helium backfilled sealed DOE standard canisters. These sealed canisters are intended for extended (>50 year) dry storage). The typical packaging configuration for the 15-foot DOE canisters places 10 ATR elements within a Type 1a basket, and three baskets are loaded within each DOE canister. During in-reactor operations and cooling pond storage conditions, oxyhydroxide layers form on the surface of the aluminum clad fuel. These layers produce hydrogen gas over time due to the fuel's radiation field. As part of the packing procedure, the ATR fuel should be dried to remove any residual physio-/chemi-sorbed water bound to the surface. As testing to the effectiveness of the drying procedure is still underway, this modeling will include results at fully saturated and fully dried conditions. In previous modeling efforts, the G-value for the production of hydrogen from the oxyhydroxide layers was assumed to be in argon environments as measured by Task 2 -Oxyhydroxide Layer Radiolytic Gas Generation Resolution. Previous experimental testing showed differences in the hydrogen generated based on the gaseous environment. vi

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Sensitivity study of coupled chemical-CFD simulations for analyzing aluminum-clad spent nuclear fuel storage in sealed canisters

Cited by 10 publications

References 19 publications

Technical basis for extended dry storage of aluminum-clad spent nuclear fuel

Technical basis for extended dry storage of aluminum-clad spent nuclear fuel

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

Modeling of ATR fuel in DOE Standard Canisters with Helium Backfilled Condition

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