Validation Testing of the Nitric Acid Dissolution Step Within the K Basin Sludge Pretreatment Process

Schmidt, Andrew J.; Delegard, Calvin H.; Silvers, K.L.; Bredt, Paul R.; Carlson, C.D.; Hoppe, E. W.; Hayes, James C.; Rinehart, Donald E; Gano, Susan R.; Thornton, Brenda M.

doi:10.2172/15010562

Cited by 3 publications

(8 citation statements)

References 1 publication

(2 reference statements)

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“…When combining the sub-samples KC-2/3 M250 (~40 ml), another KC-2/3 M250 (~70 ml), and KC-3 + KC-2 Rec 2 (40 ml) with KC-2/3 P250 (25 ml), a total of 175 ml of sludge were obtained, of which ~86 vol% is in the M250 fraction. This distribution is near that of the original KC-2/3 sludge in which about 78 wt% (wet) passed the 250-m sieve given that the M250 (2.129 g/cm 3 ) and P250 (2.109 g/cm 3 ) fractions had similar densities (Bredt et al 1999).…”

Section: Kc-2/3 Compmentioning

confidence: 66%

“…Other sludge sub-samples were sieved and the sieve fractions weighed and stored separately (e.g., Bredt et al 1999). Because these sludges were generally kept wetted (except as noted) and thus under conditions that they would otherwise have experienced as archive material, they were not physically or chemically altered by virtue of the characterization testing or by dry-out.…”

Section: Sludge Storage Conditions In the Rpl And Rationale For Gathementioning

confidence: 99%

“…The sub-sample KC-4 Rec contains only sludge passing a 250-m sieve. However, since 90 wt% of the sludge is in the M250 fraction (Bredt et al 1999), inclusion of this sub-sample has little impact on the composite composition. These five samples were combined to make the KC-4 composite, KC-4 Whole.…”

Section: Kc-4 Wholementioning

confidence: 99%

“…The first two were from stainless steel canisters and the others from aluminum canisters. The sludges, which were composited for bench-scale validation testing of nitric acid dissolution processing, were dry before their compositing and the noted weights are their dry weights (Schmidt et al 1999). The composite sludge is called "KE Canister Sludge Composite" in Schmidt et al (1999) and its previously analyzed composition is given in a footnote to Table 8.3 in the present report.…”

Section: -13 Ke Comp Amentioning

confidence: 99%

“…The sample KC-1 M500 is the portion of the KC-1 sample that was retained on 500-m and larger sieves during sieve analyses (Bredt et al 1999). The M500 fraction comprises 88.1 wt% of the total KC-1 wet (settled) solids.…”

Section: Kc-1 M500mentioning

confidence: 99%

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Characteristics of KE Basin Sludge Samples Archived in the RPL - 2007

Delegard¹,

Schmidt²,

Chenault³

2011

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Section: Kc-2/3 Compmentioning

confidence: 66%

Section: Sludge Storage Conditions In the Rpl And Rationale For Gathementioning

confidence: 99%

Section: Kc-4 Wholementioning

confidence: 99%

Section: -13 Ke Comp Amentioning

confidence: 99%

Section: Kc-1 M500mentioning

confidence: 99%

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Characteristics of KE Basin Sludge Samples Archived in the RPL - 2007

Delegard¹,

Schmidt²,

Chenault³

2011

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Determination of uranium metal concentration in irradiated fuel storage basin sludge using selective dissolution

Delegard

Sinkov

Chenault

et al. 2013

J Radioanal Nucl Chem

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Hydrothermal Testing of K Basin Sludge and N Reactor Fuel at Sludge Treatment Project Operating Conditions

Delegard¹,

Schmidt²,

Thornton³

2007

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Executive SummaryFive bench-scale tests (~50 ml each) were conducted in sealed, un-agitated reaction vessels using sludge samples collected from the K East Basin and particles/coupons of irradiated N Reactor fuel (also from the K Basins). These tests were designed to evaluate and understand the chemical changes that may be occurring under the hydrothermal conditions (e.g., 7 to 72 h at 185°C) of the Sludge Treatment Project (STP) corrosion process and the effects that any changes would have on sludge rheological properties. The two sludge formulations used in these tests were selected to represent nominal (vs. bounding) compositions of the two major sludge feed streams to the STP process. The scoping tests were not designed to evaluate engineering aspects of the process.The hydrothermal treatment affected the chemical and physical properties of the sludge. In each test, significant uranium compound phase changes were identified, resulting from dehydration and chemical oxidation and reduction reactions. Physical properties of the sludge were significantly altered from their initial, as-settled, sludge values including, shear strength, settled density, weight percent water, and gas retention.The high uranium content sludge (~70 wt% uranium) set up to form a very stiff solid that exhibited very high shear strength (120,000 to 170,000 Pa) after hydrothermal treatment at 185°C for 7 to 10 hours under static (unstirred) conditions. Shear strengths of untreated sludge range from about 270 to 8100 Pa. Also, the hydrothermal treatment reduced the water content in the settled sludge by about 20 wt%. The treated sludge was difficult to remove from the Teflon test vessels, with sludge firmly adhering to the Teflon vessel surfaces. The strength of the treated sludge was further evaluated by agitation in water. In a 600-ml beaker, with 400 ml water at ~30°C, the diameters of agglomerates were reduced by about 40 to 50% after 1 hour of agitation with a 5.08-cm (2-in.) diameter impeller rotated at a tip speed of 80 cm/s.Further static tests with lower uranium-content sludges (~16 wt% uranium) run 72 h at 185°C produced softer solids with 9,000 to 16,000 Pa shear strengths. While some sludge adhered to the Teflon liner, it was not tenaciously bound. The agglomerates from these tests were relatively weak and, in some cases, were disintegrated with a gentle stream of water. The water content in the settled sludge was not significantly affected by the hydrothermal treatment.Chemical phase alteration, observed by X-ray diffraction, scanning electron microscopy, and energy dispersive spectrometry, gave evidence that solids dissolution followed by precipitation was responsible for the increased strengths of the sludge products. The presence of organic ion exchange resin (OIER) and polymer flocculent (constituents known to be in K Basin sludge) in the lower uranium-content sludge did not appear to have a significant impact on the physical behavior of the post-treated sludge.Four irradiated uranium metal fuel coupons were included in on...

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Validation Testing of the Nitric Acid Dissolution Step Within the K Basin Sludge Pretreatment Process

Cited by 3 publications

References 1 publication

Characteristics of KE Basin Sludge Samples Archived in the RPL - 2007

Characteristics of KE Basin Sludge Samples Archived in the RPL - 2007

Determination of uranium metal concentration in irradiated fuel storage basin sludge using selective dissolution

Hydrothermal Testing of K Basin Sludge and N Reactor Fuel at Sludge Treatment Project Operating Conditions

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