Sludge Batch 10 Flowsheet Testing with Non-radioactive Simulants

Woodham, Wesley; Howe, A.; Siegfried, Matthew

doi:10.2172/1821142

Cited by 5 publications

(19 citation statements)

References 7 publications

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“…Based on the nitrate, glycolate, and sulfate analysis, the SME Product slurry appears approximately 13 to 20 percent more concentrated on a mass basis than the SRAT Product slurry. Based on the nitrate, glycolate, formate, oxalate, and TS results in the SME Product slurry and using the predictive REDOX equation reported elsewhere, 48 the predicted iron REDOX for the SB10 SME Product is 0.10. This matches the targeted iron REDOX of 0.1.…”

Section: Product Analytical Resultsmentioning

confidence: 99%

“…Glycolate concentrations in SRAT and SME condensates were similar to the concentrations in the comparable condensates from the SB10 simulant flowsheet tests (>10 mg/L to 90.5 mg/L in SRAT and SME condensates, averaging 44 mg/L in SRAT condensate) and the SC-18 SB9 NGA qualification test (>10 mg/L to 17.7 mg/L in the SRAT and SME dewater condensates). 48,53 Even though formate concentration is lower in the SRAT and SME slurries for the NGA flowsheet compared with the NFA flowsheet, formate is often noted in the NGA condensates (<10 mg/L to 37 mg/L in the SB10 simulant flowsheet test condensates, 266 mg/L in the SC-18 SRAT dewater condensate, and <10 mg/L in the SC-18 SME dewater condensates). 48,53 Elemental mercury and methylmercury were detected in both the SRAT and SME condensates.…”

Section: Condensate Analytical Resultsmentioning

confidence: 99%

“…48,53 Even though formate concentration is lower in the SRAT and SME slurries for the NGA flowsheet compared with the NFA flowsheet, formate is often noted in the NGA condensates (<10 mg/L to 37 mg/L in the SB10 simulant flowsheet test condensates, 266 mg/L in the SC-18 SRAT dewater condensate, and <10 mg/L in the SC-18 SME dewater condensates). 48,53 Elemental mercury and methylmercury were detected in both the SRAT and SME condensates. The SME condensate also contained ionic (inorganic) mercury.…”

Section: Condensate Analytical Resultsmentioning

confidence: 99%

“…Mercury data from the radioactive SB10 demonstration can be compared to similar testing with simulants. 48,54 The simulant studies included total mercury and methylmercury analyses. General conclusions from the simulant studies include 1) observation of methylmercury during the SRAT and SME cycles, 2) likely generation of methylmercury in the SRAT and SME kettles (i.e., not exclusively formed in condensate or off-gas), 3) either consumption of methylmercury in the SRAT or SME, or volatilization of methylmercury allowing it to vaporize and enter condensate/off-gas streams during CPC processing, 4) methylmercury is likely predominately formed at the beginning of the SRAT cycle when mercury is present at the highest concentration.…”

Section: Mercury Speciation Resultsmentioning

confidence: 99%

“…See the SB10 simulant report, particularly run TK51-4. 48 The time of carbonate destruction and the relatively small peak are likely due to the slow acid addition. Similarly, nitrous oxide peak was lower and broader due to the slower acid addition.…”

Section: Srat and Sme Off-gas Generationmentioning

confidence: 99%

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Radioactive Waste Sludge Washing and Demonstration of the Nitric-Glycolic Acid Flowsheet for Sludge Batch 10 Qualification

MARTINO¹,

Siegfried²,

Pareizs³

et al. 2022

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For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs qualification testing to demonstrate that the sludge batch (SB) is processible. During processing of SB9, DWPF will be transitioning from the Nitric-Formic Acid (NFA) flowsheet to the Nitric-Glycolic Acid (NGA) flowsheet. Thus, the qualification of SB10 was requested to only be performed using the NGA flowsheet.In order to qualify the batch for the NGA flowsheet, Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) cycles, designated SC-19, were performed using SB10 Tank 51 sample material. SRNL received Tank 51 material in the midst of Tank Farm washing. SRNL continued the washing in the SRNL Shielded Cells. The SRNL process included the addition of Sodium Reactor Experiment (SRE) material from H Canyon, simulating the transfer of SRE from H Canyon to Tank 51 during Tank Farm washing. The washed SB10 Tank 51 material, with SRE, was characterized prior to flowsheet qualification testing.The Chemical Process Cell demonstration with the NGA flowsheet utilized an acid stoichiometry of 107% Koopman Minimum Acid basis (102% Hsu basis). The qualification was performed on the "batch", which is representative of the Tank 51 material that will be transferred to Tank 40, rather than the "blend", which is representative of the Tank 40 material that will be fed to DWPF. Thus, specifics for the DWPF processing of the Tank 40 blend may differ in varying degrees from this qualification test. Additionally, the qualification did not include Salt Waste Processing Facility (SWPF) feeds (Monosodium Titanate (MST)/Sludge Solids and Strip Effluent), which would contribute soluble salts and the MST solids, which could influence the acid addition and the product rheology, respectively. For these reasons, the results of this qualification testing demonstration are used in conjunction with simulant testing to inform the processing of the Tank 40 blend with inclusion of SWPF feeds.Highlights of the testing results are summarized in the paragraphs below.Prior to the addition of antifoam, foaming was encountered in the SRAT cycle during the addition of nitric acid to the extent that sludge foamed over into the off-gas system. Based on observations from simulant testing, during which foaming was not noted during nitric acid addition, the plan involved addition of Momentive TM Y-17112 antifoam after the completion of nitric acid addition and prior to glycolic acid addition. The foaming during nitric acid addition was likely due to the release of carbon dioxide from the acid reacting with carbonate. After a time out (3 weeks), the SRAT cycle was resumed with an antifoam addition prior to resumption of nitric acid addition. Foaming was successfully mitigated during the remainder of the SRAT and SME cycles.Total dried solids measurements of the SRAT and SME Products were 20.1 and 48.1 weight percent (wt%), respectively. Calcined solids measured 11.3 wt% in the SRAT Receipt and SRAT Pr...

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Section: Product Analytical Resultsmentioning

confidence: 99%

Section: Condensate Analytical Resultsmentioning

confidence: 99%

Section: Condensate Analytical Resultsmentioning

confidence: 99%

Section: Mercury Speciation Resultsmentioning

confidence: 99%

Section: Srat and Sme Off-gas Generationmentioning

confidence: 99%

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Radioactive Waste Sludge Washing and Demonstration of the Nitric-Glycolic Acid Flowsheet for Sludge Batch 10 Qualification

MARTINO¹,

Siegfried²,

Pareizs³

et al. 2022

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Modeling of Chemical Slurry Rheology in DWPF Sludge Batch (SB) 10 Simulants

Cintas

Lambert

Gudavalli

et al. 2023

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The Defense Waste Processing Facility (DWPF) treats high-activity radionuclides from sludge through a process called vitrification. This process converts radioactive liquid waste currently stored in tank farms into a solid glass form that is suitable for long-term storage and disposal. Due to the complexities involved in vitrifying this waste within each operation of the Chemical Processing Cell (CPC), waste rheology is studied to characterize the fluid-mechanical properties as it passes through the CPC and into the Melter. To better understand the waste and validate flow behavior, slurry rheology of simulants that represents the waste was studied at various acid stoichiometry percentages and solids concentrations to determine the simulant's yield stress and viscosity.

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Technical Evaluation of Accelerated Basin De-Inventory Material Addition to Sludge Batch 11

MARTINO¹,

Johnson²,

Lambert³

et al. 2023

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The Accelerated Basin De-inventory (ABD) program involves discarding spent nuclear fuel that is currently stored in L-Basin to the Defense Waste Processing Facility (DWPF) for vitrification. The first ABD discards will occur during the preparation of Sludge Batch (SB) 11. Savannah River Mission Completion has requested that the Savannah River National Laboratory assess the technical gaps related to the increased gadolinium poisoning requirement and the impacts of performing the Low Temperature Aluminum Dissolution (LTAD) process in Tank 51 with H-Canyon discards present.The following summarizes the evaluation of the impacts of increasing the quantity of gadolinium (and related topics) from what was previously evaluated in the SRNL studies of gadolinium-poisoned ABD material solubility, the overall ABD flowsheet review, and increasing the fissile mass loading in glass: Based on literature surveys, there is no indication that organic interactions with gadolinium will be significant at the high pH (typically >13) conditions of the Concentration, Storage, and Transfer Facilities. Any interactions of gadolinium with organics in DWPF are not expected to adversely impact DWPF or downstream facilities. Thus, there is little-to-no residual risk from organic interactions with gadolinium. [Gap closed]  Increasing the gadolinium mass ratio to 3.0:1 Gd: 235 U(eq SLU ) should lead to the same or higher partitioning of gadolinium into the solid phase within the DWPF Chemical Process Cell, resulting in both liquid and solid phases with expected partitioning of Gd consistent with the prior solubility study. [Gap closed for SB11]  There are no expected impacts on DWPF melt temperature and melter operations due to the minimal ~0.2 weight percent (wt%) increase in Gd concentration relative to previous sludge batches.[Gap closed for SB11]  As observed previously, Gd is expected to enter the off-gas system via physical entrainment, but at a slightly higher concentration than what was observed for SB9 melter off-gas pluggage deposits (0.07 wt%). [Gap closed for SB11]  There are no expected impacts on DWPF recycle or the Recycle Collection Tank glycolate destruction process. [Gap closed for SB11]  Gd is projected to be a trace component in the SB11 glass (<0.5 wt%) and can be ignored for process control. Trace components do not significantly impact glass durability, thus the conclusions of the previous Product Consistency Test evaluation at a fissile mass loading of 2,500 g fissile/m 3 glass still applies to SB11. The ~0.1 wt% increase in Gd 2 O 3 concentration relative to the previous study will not impact the predictability of SB11 glass with the DWPF Product Composition Control System (PCCS) models for durability or the acceptability of glass according to the Waste Acceptance Product Specifications (WAPS) criterion for product consistency. [Gap closed for SB11]  No additional Toxicity Characteristic Leaching Procedure testing is necessary for SB11 and the hazardous waste specification of the SB11 DWPF waste form is unchanged a...

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Sludge Batch 10 Flowsheet Testing with Non-radioactive Simulants

Cited by 5 publications

References 7 publications

Radioactive Waste Sludge Washing and Demonstration of the Nitric-Glycolic Acid Flowsheet for Sludge Batch 10 Qualification

Radioactive Waste Sludge Washing and Demonstration of the Nitric-Glycolic Acid Flowsheet for Sludge Batch 10 Qualification

Modeling of Chemical Slurry Rheology in DWPF Sludge Batch (SB) 10 Simulants

Technical Evaluation of Accelerated Basin De-Inventory Material Addition to Sludge Batch 11

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