105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 2 Sludge

Pearce, Kenneth L.

doi:10.2172/803051

Cited by 18 publications

(12 citation statements)

References 4 publications

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“…In addition to the products of the fracture and subsequent corrosion of irradiated uranium metal fuel, the sludge contains sand (from sand filters); infiltrated soils; steel, aluminum, and concrete structural component corrosion products; organic and inorganic ion exchange materials; and miscellaneous debris. Characterization studies have shown that the K Basin sludge composition and quantity varies according to its source location (Makenas et al 1996(Makenas et al -1999aPearce 2001;Mellinger et al 2004). However, subsequent K Basin process activities (including the recently completed retrieval, washing, and packaging of the fuel) have further contributed to the sludge burden and altered the distribution reported in these prior characterizations.…”

Section: Introductionmentioning

confidence: 99%

Characterization of Compaction and Dryout Properties of KE Basin Sludge During Long-Term Storage

Delegard¹,

Poloski²,

Schmidt³

et al. 2005

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Section: Introductionmentioning

confidence: 99%

Characterization of Compaction and Dryout Properties of KE Basin Sludge During Long-Term Storage

Delegard¹,

Poloski²,

Schmidt³

et al. 2005

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“…Past sampling and analysis campaigns (Makenas et al 1996-99) characterized the bulk of the sludge, while a more recent study has focused on the ~6.3 m 3 of less radioactive, KE North Loadout Pit (NLOP) sludge (Mellinger et al 2004a). Pearce (2001) summarized the inventory and compositions of all K Basin sludge materials. The evolving plan for all but the KE NLOP sludge is disposition to the Waste Isolation Pilot Plant (WIPP) as remote handled transuranic waste (RH-TRU).…”

Section: Introductionmentioning

confidence: 99%

Final Report - Gas Generation Testing of Uranium Metal in Simulated K Basin Sludge and in Grouted Sludge Waste Forms

Delegard¹,

Schmidt²,

Sell³

et al. 2004

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metal in simulated sludge, in the present testing, are similar to, and thus confirm, those in prior tests of irradiated uranium metal fuel particles from K Basins. The following table summarizes the hydrogen generation rates from uranium metal corrosion at 60°C for the grout formulations and reference tests. The rates are for hypothetical RH-TRU 55-gallon drums loaded with 14.6 liters of KW canister sludge in the respective reference sludge or grouted sludge waste form. This amount of sludge is at the 200-gram 239 Pu fissile gram equivalent (FGE) limit mandated by WIPP. The hydrogen generation rates at the FGE-limited loadings are compared with the maximum 3.65×10-8 moles/second hydrogen generation rate tolerated in a WIPP RH-TRU drum. Case Drum Hydrogen Generation Rate (moles H 2 /sec) (a) Factor Improvement Needed for WIPP Reference Tests Uranium Metal 1.80×10-5 493 Uranium Metal in Simulated Sludge 5.71×10-6 156 Portland Cement BNFL 8.57×10-6 235 Bentonite 4.00×10-6 110 Weakley 9.43×10-6 258 Cast Stone 7.37×10-6 202 Magnesium Phosphate Cement Tectonite 1.71×10-5 470 Tectonite-Bentonite 7.57×10-6 207 Drum Hydrogen Generation Rate Limit 3.65×10-8 1 (a) Drum H 2 generation rate based on the uranium metal surface area in 14.6 liters of nominal KW canister sludge drum TRU RH

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“…This sludge consists of various proportions of fuel; structural corrosion products; windblown material; and miscellaneous constituents, such as ion exchange material (both organic and inorganic) and paint chips (Makenas et al 1996-99). Pearce (2001) describes the inventory and compositions of all K Basin sludge materials in detail.…”

Section: Introductionmentioning

confidence: 99%

Settling Test Using Simulants to Evaluate Uranium Metal Distribution in K Basin Sludge

Schmidt¹,

Elmore²

2002

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This document presents the results of a large-scale settling test conducted with a K Basin sludge simulant that included metallic tungsten/cobalt (W/Co) fragments (density ~14.5 g/cm 3) as a surrogate for uranium metal (density 19 g/cm 3). The objective of the testing was to gain insight into how uranium metal is likely to be distributed within the K Basin sludge loaded into the large-diameter containers (LDCs) that will be used for storage at T Plant. In the LDCs, uranium metal will react with water and generate heat and hydrogen gas. During loading, transportation, and storage operations, the uranium metal distribution in the LDCs will have an impact on the thermal stability. A settling model (a) has been developed to predict the uranium metal distribution during loading to generate input conditions for modeling the thermal stability of the sludge in the LCDs. (b) The results from the settling test discussed here will be compared against predictions developed from the settling model. This settling test was conducted by Pacific Northwest National Laboratory under contract to the Fluor Hanford Spent Nuclear Fuel (SNF) Project Sludge Handling Group. A five-component simulant was formulated for the settling test to approximate the average particle size distribution and particle density of a 40/60 volume basis mixture of K East Basin canister and floor sludge. For the test, 20 jars (batches) were prepared, containing 1 liter of sludge simulant each. A clear acrylic column, 1 ft in diameter (OD) and 5 ft tall, was used as the settling vessel. To simulate flow to the LDC, supernatant in the upper part of the settling column was recirculated using a peristaltic pump. Water was removed 6 in. from the top of column and discharged back into the column at about 1.2 gpm [discharge point: center of column, 9 in. below the top of the column]. Before the test was started, three closed-bottom glass cylinders (2.5 in. OD x 12 in. high] were placed on the bottom of the column to collect core samples of the settled sludge. For the test, a batch of sludge (1 L) was added to the top of the column (uniformly over the cross section of the column) once every 20 minutes. The sludge settled through 4 to 5 ft of water/slurry before accumulating on the bottom of the column. Twenty minutes after the last batch addition, the recirculation loop was turned off, and the suspended particulate was allowed to settle. The final settled sludge depth in the column was about 11.5 in. About 40 hours after the last sludge addition, clarified supernatant was removed and the lower portion of the column (containing the settled sludge) was transported (about 3 miles) via a pickup truck for X-ray nondestructive evaluation (NDE) analysis. Because X-rays could not penetrate the dense W/Co, the distribution of W/Co could be examined within the settled sludge matrix. However, the X-rays also could not penetrate the entire column thickness; consequently, images were captured by focusing the X-ray about 2 to 3 in. in from the edge of column. The column was rotated...

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105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 2 Sludge

Cited by 18 publications

References 4 publications

Characterization of Compaction and Dryout Properties of KE Basin Sludge During Long-Term Storage

Characterization of Compaction and Dryout Properties of KE Basin Sludge During Long-Term Storage

Final Report - Gas Generation Testing of Uranium Metal in Simulated K Basin Sludge and in Grouted Sludge Waste Forms

Settling Test Using Simulants to Evaluate Uranium Metal Distribution in K Basin Sludge

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