SNL Contribution: Consequence Analysis for Moisture Remaining in Dry Storage Canisters After Drying

Bryan, Charles R.; Durbin, Samuel; Lindgren, Eric R.; Ilgen, Anastasia Gennadyevna; Montoya, Timothy; Dewers, Thomas; Fascitelli, Dominic

doi:10.2172/1762933

Cited by 4 publications

(14 citation statements)

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“…SNL work involved analyzing gas samples collected from an in-service canister loaded with SNF. Both works' (Knight, 2018;Bryan et al, 2019) results warrant an explanation for the presence of the residual water in the canister cavity. To this end, following qualitative analysis is presented.…”

Section: Residual Water Inventorymentioning

confidence: 74%

“…Knight (2018) observed subzero temperatures in a mockup fuel assembly subjected to an industry practiced drying process. In addition, recent work (Bryan et al, 2019) by Sandia National Laboratory (SNL) under the high burnup cask demonstration project indicate presence of 100 g of residual water in a canister cavity. SNL work involved analyzing gas samples collected from an in-service canister loaded with SNF.…”

Section: Residual Water Inventorymentioning

confidence: 99%

“…This work assumes the presence of 5.5 and 10 moles of residual water in the canister cavity. The value of 5.5 moles is based on work by Bryan et al (2019) in which residual free water at ~100 ml was reported in the HBU demonstration that used a typical vacuum drying process. The value of 10 moles is used considering uncertainties associated with logged water in failed rods and bound water with other assembly hardware (CNWRA, 2013;Bryan et al, 2019).…”

Section: Residual Water Inventorymentioning

confidence: 99%

“…Results of the gas sampling analysis under the high burnup cask demonstration project have shown residual water amount to be approximately 100 mL, i.e., 5.5 moles (Bryan et al, 2019). Considering uncertainty is determining the residual water amount, an analysis was conducted using 5.5 and 10 moles of residual water.…”

Section: Summary Conclusion and Future Refinementsmentioning

confidence: 99%

“…Dryness of spent nuclear fuel (SNF) and the surrounding environment in a canister is an essential aspect in evaluation of materials aging during extended dry storage. Recent work (Bryan et al, 2019) suggests that inadvertent free water may remain following drying even with a dryness criterion of 3 torr pressure limit following a 30-minute hold after active drying is completed. Regulations in 10 CFR Part 72 require that for a period of at least 20 years the dry storage casks function to ensure (i) fuel assemblies can be retrieved if necessary, 1 (ii) subcritical conditions can be maintained under credible scenarios, (iii) radioactive releases do not exceed specified limits, and (iv) there is sufficient shielding to keep direct radiation dose rates below specified limits.…”

Section: Introductionmentioning

confidence: 99%

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Consequence Analysis of Residual Water in a Storage Canister (Preliminary Report)

Shukla

Sindelar

Lam

2019

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This report describes an investigation of materials' interactions due to residual water remaining inside a dry storage canister, and the impacts on the spent nuclear fuel and canister internals.Recent findings from the High Burnup Demonstration project, and an Integrated Research Project, sponsored under the DOE-Nuclear Energy, Spent Fuel and Waste Disposition campaign, show that residual free water, well above the amount of approximately 0.4 gm-moles that had been assumed for a 3 torr rebound pressure, may remain within an SNF canister following prototypic drying.

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Section: Residual Water Inventorymentioning

confidence: 74%

Section: Residual Water Inventorymentioning

confidence: 99%

Section: Residual Water Inventorymentioning

confidence: 99%

Section: Summary Conclusion and Future Refinementsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Consequence Analysis of Residual Water in a Storage Canister (Preliminary Report)

Shukla

Sindelar

Lam

2019

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Drying of Spent Nuclear Fuel: Considerations and Examples

et al. 2023

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Evaluation of Hydrogen Generation in High Burnup Demonstration Dry Storage Cask

d’Entremont

Kesterson

Sindelar

2020

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This report provides a best-estimate evaluation of residual water content (post-dry out) in the High Burnup (HBU) LWR Spent Fuel Demonstration project TN-32 cask, and evaluates the radiolysis of the residual free water, and the physisorbed and chemisorbed waters on the surfaces of the fuel and cask internal contents. 1 The evaluation of radiolytic breakdown of those waters with gamma radiation causing the generation of hydrogen gas (H2) is made using available literature data and models. This evaluation is part of the overall materials performance evaluation of the SNF-in-canister system, and is part of the technical bases for their continued safe dry storage.The TN-32 cask contents included 32 HBU LWR spent fuel assemblies each with 264 fuel rods clad in zirconium alloys, aluminum neutron absorber components, and aluminum and stainless steel structural components. The residual free and surface (physisorbed/chemisorbed) waters are ascribed to water vapor in the free volume and to components' surfaces, respectively. The total potential radiolytic hydrogen inventory from the water vapor and from waters ascribed to surfaces has been calculated assuming all the water produced molecular H2. The residual water that is chemically incorporated into the bulk of a hydrated oxide, i.e., chemisorbed water, and its total potential hydrogen inventory has been calculated. These calculations are at the physical limit of material available and are used for a bounding assessment purpose only.An estimate was made of amount of hydrogen (H2) generated in the HBU cask free volume after 12 days and after 40 years with radiolysis of the residual waters. The oxygen from radiolytic breakdown of free and surface water (effective net reaction H2O = H2 + 1/2O2) is not built up in the canister, and rather is assumed to be consumed by oxidation reactions with the materials. The oxidation of materials in the canister, addressed in a previous report [Shukla et al, 2019] in the NE-SFWST campaign, is not discussed in this report. No oxygen (O2) generation is expected from radiolytic breakdown of chemisorbed water in hydrated oxides based on results of previous studies. Gettering of hydrogen and back reactions to reduce hydrogen concentration were not considered in this present work.

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SNL Contribution: Consequence Analysis for Moisture Remaining in Dry Storage Canisters After Drying

Cited by 4 publications

References 0 publications

Consequence Analysis of Residual Water in a Storage Canister (Preliminary Report)

Consequence Analysis of Residual Water in a Storage Canister (Preliminary Report)

Drying of Spent Nuclear Fuel: Considerations and Examples

Evaluation of Hydrogen Generation in High Burnup Demonstration Dry Storage Cask

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