Waste behavior during horizontal extrusion: Effect of waste strength for bentonite and kaolin/ludox simulants and strength estimates for wastes from Hanford waste tanks 241-SY-103, AW-101, AN-103, and S-102

Gauglitz, Phillip A.; Aikin, John

doi:10.2172/565570

Cited by 14 publications

(18 citation statements)

References 7 publications

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“…Sometimes the shear strength measurement was repeated one hour after the initial measurement to provide information about the effect of previous shear on the shear strength of these materials. Gauglitz and Aikin (1997) developed a methodology to estimate the shear strength of tank waste materials based on visual observations of horizontal extrusion behavior. A related core extrusion shear strength estimation technique was developed by Rassat et al (2003).…”

Section: Timementioning

confidence: 99%

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Estimate of Hanford Waste Rheology and Settling Behavior

Poloski¹,

Wells²,

Tingey³

et al. 2007

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The actual testing activities were performed and reported separately in referenced documentation. Because of this, many of the required topics below do not apply and are so noted. Test ObjectivesThis section is not applicable. No testing was performed for this investigation. Test ExceptionsThis section is not applicable. No test specification as well as test exception applies to this investigation as there was no testing was performed. Results and Performance Against Success CriteriaThis section is not applicable. No success criteria were established as there was no testing performed for this investigation. Quality RequirementsSince This report is based on data from testing as referenced. The PNNL assumes that the data from these references has been fully reviewed and documented in accordance with the analysts' QA Programs. PNNL only analyzed data from the referenced documentation. At PNNL, the performed calculations, the documentation and reporting of results and conclusions were performed in accordance with the RPP-WTP Quality Assurance Manual (RPP-WTP-QA-003, QAM). Internal verification and validation activities were addressed by conducting an independent technical review of the final data report in accordance with PNNL procedure QA-RPP-WTP-604. This review verifies that the reported results are traceable, that inferences and conclusions are soundly based, and that the reported work satisfies the Test Specification Success Criteria. This review procedure is part of PNNL's RPP-WTP Quality Assurance Manual). Test ConditionsThe scope of the RWG effort is specified in the approved WTP issue response plan (24590-WTP-PL-ENG-06-0013) and defined in subcontractor change notice (SCN) 007 and Test Specification 24590-PTF-TSP-RT-06-007, Rev 0.Demonstrate the simulant properties used for testing bracket expected actual waste properties. For non-cohesive solids (Phase 1) this includes particle size, solids density, solids concentration, liquid density, and liquid viscosity. For cohesive solids (Phase 2) this includes bulk slurry density, particle size, particle density, slurry rheology (such as consistency and yield stress) and shear strength of settled, aged sediments, as well as settled layer (heel) thickness.Waste received at the WTP will be subject to a feed specification supporting plant design and as agreed to in an Interface Control Document. This report compiles the existing Hanford Tank Farm rheological data addressed in italicized text above and establishes expected ranges for these properties for as-retrieved Hanford Tank Farm wastes. Various processes will be performed on these retrieved wastes which are expected to alter these property ranges from the as-retrieved conditions. Simulant development activities should focus on the expected properties of the waste streams under such processing conditions. v Simulant UseThis section is not applicable. No testing was performed for this investigation.

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Section: Timementioning

confidence: 99%

“…A related core extrusion shear strength estimation technique was developed by Rassat et al (2003). This technique is based strictly on extrusion length and was developed from the simulant extrusion results presented by Gauglitz and Aikin (1997).…”

Section: Timementioning

confidence: 99%

Estimate of Hanford Waste Rheology and Settling Behavior

Poloski¹,

Wells²,

Tingey³

et al. 2007

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“…For the SST wastes of current interest, ball rheometer data are not available. Gauglitz and Aikin (1997) reviewed horizontal extrusion data for several DST and SST tank wastes and used horizontal extrusion data fiom simulated wastes as calibration standards to estimate actual waste shear strengths. The estimated strengths for AW-101 and AN-103 using the extrusion technique were, in general, considerably lower than the shear strength measurements for tank samples reported by Rassat et al (1997), but they agreed reasonably well with the ball rheometer results.…”

Section: 3mentioning

confidence: 99%

Mechanisms of gas retention and release: Experimental results for Hanford single-shell waste tanks 241-A-101, 241-S-106, and 241-U-103

Rassat¹,

Caley²,

Bredt³

et al. 1998

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Executive SummaryThe 177 underground waste storage tanks at the Hadord Site contain millions of gallons of radioactive waste resulting fiom the purification of nuclear materials and related processes.Through various mechanisms, flammable gas mixtures of hydrogen, ammonia, methane, and nitrous oxide are generated and retained in significant quantities within the waste in many (-25) of these tanks. The potential for large releases of retained gas from these wastes creates a flammability hazard. It is a critical component of the effort to understand the flammability hazard and a primary goal of this laboratory investigation to establish an understanding of the mechanisms of gas retention and release in these wastes. The results of bubble retention experimental studies using waste samples from several waste tanks and a variety of waste types support resolution of the Flammable Gas Safety Issue. Gas bubble retention information gained in the pursuit of safe storage will, in turn, benefit future waste operations including salt-well pumping, waste transfers, and sluicinghetrieval. Waste SamplesPrevious laboratory studies on simulated and actual wastes established a framework within which to classify gas bubble retention mechanisms. The behavior observed in earlier gas retention experiments on four Hanford double-shell tank ( D S T ) wastes (24 1 -AN-1 03 , 24 1 -AW-10 1, 24 1 -SY-101, and 241-SY-103) and one single-shell tank (SST) waste (241-S-102) is captured within this general framework. Considering the relatively large number (19) of SSTs on the Hanford Flammable Gas Watch List, the experimental study of SST waste gas retention and release is limited. To answer this, the current gas retention experiments were conducted on four samples fiom three Hanford SSTs (one each fiom 241-A-101 and 241-S-106 and two fiom 241-U-103).These SSTs were selected using several criteria, including diversity of waste classification (type), behavior indicating that the waste retains, or has the potential of retaining, significant quantities of gas, status of supporting flammable gas data (e.g., retained gas sampler [RGS] results), and sample availability.Tank 241-A-101 (A-101) is of interest because RGS results indicate that the waste exists in an unexpected configuration, with the nonconvective (solids-containing) layer on top of the convective (liquid) layer. Tank A-101 contains double-shell slurry feed waste type, and it is reported to consist primarily of saltcake. The sample tested (Core 154, segment 5) was previously used (spent) in RGS testing.Tank 241-S-106 (S-106) contains noncomplexed waste type and is characterized as predominantly saltcake waste. This tank was of interest because barometric pressure evaluation (dL/dP) showed high gas retention (1519%) while the majority of RGS measurements showed a maximum of 10%. The S-106 gas retention sample was fiom the upper half of Core 183, segment 8.Tank 241-U-103 (U-103) also contains noncomplexed waste type but is reported to have a Two U-103 composite significant fraction of salt...

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“…An -extrusion length‖ methodology based on the simulant extrusion data of Gauglitz and Aikin (1997) for estimating the yield stress in shear of Hanford Waste was developed in Rassat et al (2003). This methodology relies on measuring the initial extrusion length of the waste core at plastic failure and produces shear strength values similar in magnitude and with similar trends as the ball rheometer results.…”

Section: Waste Core Extrusion Behaviormentioning

confidence: 99%

Assessment of Jet Erosion for Potential Post-Retrieval K-Basin Settled Sludge

Wells¹,

Enderlin²,

Gauglitz³

et al. 2009

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SummaryPackaged K-Basin sludge will be transported to the T Plant on the Hanford Site where it will be interim stored. The sludge will be retrieved from the storage containers and processed for disposal. A sample of high uranium content canister sludge, designated 96-13, -self-cemented‖ during laboratory storage. This sample was uncharacteristically strong compared to expected K-Basin material. The purpose for this work is to evaluate the potential retrieval of such sludge after storage at the T Plant via jet erosion.The specific objectives of this report are to determine the modes of erosion and the methods used to measure/assess the erodibility parameters of sludge and identify those parameters applicable to jet erosion. The erodibility parameters of sample 96-13 are characterized to the extent possible. These objectives have been met based on literature review, past experience at Pacific Northwest National Laboratory, and observation of sample 96-13 video during hot-cell activities.Sample 96-13 is characterized as a heterogeneous cohesive sediment with -paste‖ material (estimated shear strength 3 to 5 kPa) joining -chunks‖ (estimated shear strength 380 to 770 kPa). The bulk material shear strength is estimated at 15 to 65 kPa, which is within the range of shear strengths for cohesive sludges used for erosion investigations. These shear strength estimates are taken from visual observation of the 96-13 sample settling study disassembly video and are based on estimated applied forces, approximated contact areas, and the application of an estimate of the relation of compressive and shear stresses and must therefore be treated as qualitative. The estimated shear-strength results are qualitatively in agreement with the measured shear strength for hydrothermally treated K-Basin samples. General recommendations for measuring the shear strength of materials such as sample 96-13 are provided.

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Waste behavior during horizontal extrusion: Effect of waste strength for bentonite and kaolin/ludox simulants and strength estimates for wastes from Hanford waste tanks 241-SY-103, AW-101, AN-103, and S-102

Cited by 14 publications

References 7 publications

Estimate of Hanford Waste Rheology and Settling Behavior

Estimate of Hanford Waste Rheology and Settling Behavior

Mechanisms of gas retention and release: Experimental results for Hanford single-shell waste tanks 241-A-101, 241-S-106, and 241-U-103

Assessment of Jet Erosion for Potential Post-Retrieval K-Basin Settled Sludge

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