Wet storage integrity update

Bailey, W.J.; Johnson, A.B.

doi:10.2172/7079263

Cited by 5 publications

(6 citation statements)

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“…ASTM A887-89 (ASTM International, 2009) defines eight types (304B and 304B1-304B7) of borated stainless steels with boron concentrations from 0.2 to 2.25 wt%. Requirements for the chemical composition of borated stainless steel for nuclear application are provided in ASTM International (2009).…”

Section: Corrosion Of Borated Stainless Steelmentioning

confidence: 99%

“…Conventional cast-and-wrought metallurgical practice can reach Grade B properties; however, ASTM International does not preclude using powder metallurgy techniques in the supply of Grade B materials. EPRI (2009) lists products conforming to ASTM A887-89 (ASTM International, 2009) specifications from two suppliers: NeutroSorb®, NeutroSorb Plus®, or Micro-Melt® NeutroSorb (Carpenter Powder Products, USA) and Neutronit® (Bohler Bleche GmbH, Austria).…”

Section: Effects Of Residual Water On Storage Canister Internal Compomentioning

confidence: 99%

“…In borated stainless steel, the formation of chromium-rich secondary phase (Fe, Cr)2B particles could lead to intergranular corrosion. EPRI (2009,1992) reported that borated stainless steel is susceptible to intergranular corrosion in acidic environments with pH <2; therefore, this degradation mechanism is not likely during storage. Furthermore, stainless steels are typically manufactured with carbon content less than 0.03 percent to minimize the potential for intergranular corrosion.…”

Section: Effects Of Residual Water On Storage Canister Internal Compomentioning

confidence: 99%

“…The studies showed that the general corrosion rates of 304B4 were hundreds of nm/yr with no clear dependence on temperature. Bailey and Johnson (1983) examined the corrosion rate of Type 304 stainless steel in high-purity water. They reported a corrosion rate of Type 304 stainless steel less than 0.25 µm/yr.…”

Section: Effects Of Residual Water On Storage Canister Internal Compomentioning

confidence: 99%

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Effects of Residual Water on Storage Canister Internal Components

Shukla¹,

Sindelar²

2020

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This report describes an evaluation of the spent nuclear fuel cladding and canister internal materials' corrosion/oxidation due to (inadvertent) residual free water inside a dry storage canister post-dryout. Drying of spent nuclear fuel (SNF) and the impact of (inadvertent) residual water in a SNF canister is being addressed under the DOE-NE Spent Fuel and Waste Science and Technology (SFWST) program to ensure the safe extended dry storage and transportation of commercial SNF. A long-standing understanding has been that the amount of residual water in a storage canister after vacuum drying is not expected to be much more than trace amounts of 0.43 gram mole (NRC, 2010). However, recent findings from the High Burnup Demonstration project (Bryan et al., 2019a-c), and an Integrated Research Project (Knight, 2018) show that residual free water well above the amount of approximately 0.43 gm-moles that had been assumed for a 3 torr rebound pressure, may remain within an SNF canister following prototypic drying. In fact, an NRC-NMSS sponsored study considered residual water amount as high as 55 moles (CNWRA, 2013). Considering the recent findings and the NRC-sponsored work, this present work was conducted to study the effects of unspecified amount of residual water on oxidation and corrosion of canister internals, i.e., it was assumed that the residual water amount is not limiting. It was assumed that the spent nuclear fuel content in the canister is not exposed to the internal environment, i.e., the packaged canister does not contain any damaged (breached) fuel. The overall approach consisted of explicit accounting of both spatial and temporal variations of thermal conditions in a generic storage canister in the corrosion/oxidation of the materials. Radiolysis of the residual water is expected to result in the formation of hydrogen peroxide, both in liquid and vapor phase of the residual water. Literature information suggests that vapor phase hydrogen peroxide would decompose into oxygen and water; this reaction will be catalyzed by the cladding surface. On other hand, hydrogen peroxide in liquid water would persist. It was assumed that radiolysis would yield approximately 0.1 mole of hydrogen peroxide for each liter of residual water or 0.1 M concentration. Considering this, it was considered for the corrosion evaluation that hydrogen peroxide concentration in liquid phase residual water ranges between 0 to 2 M. Corrosion rates of various internal component materials were obtained as a function of temperature and hydrogen peroxide. Cladding materials' oxidation rates, reported in the previous study (Shukla, et al, 2019), were used. Additional analysis also indicated that cladding oxidation could only occur when temperatures are high enough for the residual water to be in vapor phase. Cladding oxidation rates and corrosion rates of the internal components were integrated with the spatial and temporal thermal conditions inside the canister for the storage period of 300 years. The specific components were those for the f...

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Section: Corrosion Of Borated Stainless Steelmentioning

confidence: 99%

Section: Effects Of Residual Water On Storage Canister Internal Compomentioning

confidence: 99%

Section: Effects Of Residual Water On Storage Canister Internal Compomentioning

confidence: 99%

Section: Effects Of Residual Water On Storage Canister Internal Compomentioning

confidence: 99%

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Effects of Residual Water on Storage Canister Internal Components

Shukla¹,

Sindelar²

2020

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“…Crud may be released from If Bailey and Johnson (1983) (Rasmussen 1986;Bailey 1985a). Spent fuel used in the program was discharged from Oconee-2 PWR in 1977.…”

Section: Inmentioning

confidence: 99%

Characteristics of fuel crud and its impact on storage, handling, and shipment of spent fuel. [Fuel crud]

Hazelton¹

1987

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This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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General and Specific Perspectives on Biological Impacts in Wet Storage Facilities for Irradiated Nuclear Fuel

Johnson¹,

Burke²

1997

Microbial Degradation Processes in Radioactive Waste Repository and in Nuclear Fuel Storage Areas

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Wet storage integrity update

Cited by 5 publications

References 5 publications

Effects of Residual Water on Storage Canister Internal Components

Effects of Residual Water on Storage Canister Internal Components

Characteristics of fuel crud and its impact on storage, handling, and shipment of spent fuel. [Fuel crud]

General and Specific Perspectives on Biological Impacts in Wet Storage Facilities for Irradiated Nuclear Fuel

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