Powered by Deep Web Technologies
Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)  

SciTech Connect

The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. Twenty-seven radionuclides have been identified as reportable for DWPF SB7b. Each of these radionuclides has a half-life greater than ten years and contributes more than 0.01% of the radioactivity on a Curie basis at some point from production through the 1100 year period between 2015 and 3115. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100- year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. The radionuclide measurements made for SB7b are the most extensive conducted to date. Some method development/refinement occurred during the conduct of these measurements, leading to lower detection limits and more accurate measurement of some isotopes than was previously possible.

Crawford, C. L.; Diprete, D. P.

2012-12-17T23:59:59.000Z

2

DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 5 (MACROBATCH 6)  

SciTech Connect

The Waste Acceptance Product Specifications (WAPS) 1.2 require that ''The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115''. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Tank 40 (Sludge Batch 4 (SB4)), Sludge Batch 5 (SB5) that was transferred to Tank 40 from Tank 51, and H-Canyon Np transfers completed after the start of processing. The blend of sludge in Tank 40 is also referred to as Macrobatch 6 (MB6). This report develops the list of reportable radionuclides and associated activities and determines the radionuclide activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to the radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2008-0010; Rev. 2 entitled Sludge Batch 5 SRNL Shielded Cells Testing. Specifically, this report details results from performing Subtask II, 5 of the TTR and, in part, meets Deliverable 7 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), WSRC-RP-2008-00137, Rev. 2 and Analytical Study Plan (ASP), WSRC-RP-2008-00138, Rev. 2. In order to determine the reportable radionuclides for SB5 (MB6), a list of radioisotopes that may meet the criteria as specified by the Department of Energy's (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes excluded from the projection calculations. Based on measurements and analytical detection limits, twenty-six radionuclides have been identified as reportable for DWPF SB5 as specified by WAPS 1.2. The 26 reportable radionuclides are: Cl-36, Ni-59, Ni-63, Sr-90, Zr-93, Nb-93m, Tc-99, Sn-126, Cs-137, Sm-151, U-233, U-234, Np-237, U-238, Pu-238, Pu-239, Pu-240, Am-241, Pu-241, Pu-242, Am-242m, Am-243, Cm-244, Cm-245, Cm-246, Cf-251. Chlorine-36 is reported for the first time based on the upper bounding activity determined from the aqua regia digested sludge slurry. The WCP and WQR require that all of radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB5 (MB6), all of the radionuclides in the Design Basis glass are reportable except for four radionuclides: Se-79, Pd-107, Cs-135, and Th-230. At no time through the year 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to

Bannochie, C.; Bibler, N.; Diprete, D.

2010-02-04T23:59:59.000Z

3

DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 6 (MACROBATCH 7)  

SciTech Connect

The Waste Acceptance Product Specifications (WAPS) 1.2 require that 'The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115'. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 5 (SB5) with H-Canyon Np transfers completed after the start of processing SB5, and Sludge Batch 6 (SB6) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 7 (MB7). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2009-0014; Rev. 2 entitled Sludge Batch 6 SRNL Shielded Cells Testing. Specifically, this report details results from performing Subtask III, Item 2 of the TTR and, in part, meets Deliverable 7 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2009-00473, Rev. 15 and Analytical Study Plan (ASP), SRNL-RP-2009-00474, Rev. 1. In order to determine the reportable radionuclides for SB6 (MB7), a list of radioisotopes that may meet the criteria as specified by the Department of Energy's (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes were excluded from the projection calculations. Based on measurements and analytical detection limits, 30 radionuclides have been identified as reportable for DWPF SB6 as specified by WAPS 1.2. The WCP and WQR require that all of the radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB6, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100-year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to the list of reportable radionuclides in order to meet WAPS 1.6. All of the Pu isotopes (Pu-238, -239, -240, -241, and -242) and other U isotopes (U-233, -234, and -238) identified in WAPS 1.6 were already determined to be reportable according to WAPS 1.2 This brings the total number of reportable radionuclides for SB6 to 32. The radionuclide measurements made for SB6 are the most extensive condu

Bannochie, C.; Diprete, D.

2011-06-01T23:59:59.000Z

4

DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 7B (MACROBATCH 9)  

SciTech Connect

The Waste Acceptance Product Specifications (WAPS) 1.2 require that “The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115”. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2011-0004; Rev. 0 entitled Sludge Batch 7b Qualification Studies. Specifically, this report details results from performing Subtask II, Item 2 of the TTR and, in part, meets Deliverable 6 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2011-00247, Rev. 0 and Analytical Study Plan (ASP), SRNL-RP-2011-00248, Rev. 0. In order to determine the reportable radionuclides for SB7b (MB9), a list of radioisotopes that may meet the criteria as specified by the Department of Energy’s (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes were excluded from the projection calculations. Based on measurements and analytical detection limits, 27 radionuclides have been identified as reportable for DWPF SB7b as specified by WAPS 1.2. The WCP and WQR require that all of the radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100-year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to the list of reportable radionuclides in order to meet WAPS 1.6. All of the Pu isotopes (Pu-238, -239, -240, -241, and -242) and other U isotopes (U-233, -234, and -238) identified in WAPS 1.6 were already determined to be reportable according to WAPS 1.2 This brings the total number of reportable radionuclides for SB7b to 29. The radionuclide measurements made for SB7b are similar to those performed in the previous SB7a MB8 work. Some method development/refine

Crawford, C. L.; Diprete, D. P.

2013-08-22T23:59:59.000Z

5

SLUDGE BATCH 7 (SB7) WASHING DEMONSTRATION TO DETERMINE SULFATE/OXALATE REMOVAL EFFICIENCY AND SETTLING BEHAVIOR  

SciTech Connect

To support Sludge Batch 7 (SB7) washing, a demonstration of the proposed Tank Farm washing operation was performed utilizing a real-waste test slurry generated from Tank 4, 7, and 12 samples. The purpose of the demonstration was twofold: (1) to determine the settling time requirements and washing strategy needed to bring the SB7 slurry to the desired endpoint; and (2) to determine the impact of washing on the chemical and physical characteristics of the sludge, particularly those of sulfur content, oxalate content, and rheology. Seven wash cycles were conducted over a four month period to reduce the supernatant sodium concentration to approximately one molar. The long washing duration was due to the slow settling of the sludge and the limited compaction. Approximately 90% of the sulfur was removed through washing, and the vast majority of the sulfur was determined to be soluble from the start. In contrast, only about half of the oxalate was removed through washing, as most of the oxalate was initially insoluble and did not partition to the liquid phase until the latter washes. The final sulfur concentration was 0.45 wt% of the total solids, and the final oxalate concentration was 9,900 mg/kg slurry. More oxalate could have been removed through additional washing, although the washing would have reduced the supernatant sodium concentration.The yield stress of the final washed sludge (35 Pa) was an order of magnitude higher than that of the unwashed sludge ({approx}4 Pa) and was deemed potentially problematic. The high yield stress was related to the significant increase in insoluble solids that occurred ({approx}8 wt% to {approx}18 wt%) as soluble solids and water were removed from the slurry. Reduction of the insoluble solids concentration to {approx}14 wt% was needed to reduce the yield stress to an acceptable level. However, depending on the manner that the insoluble solids adjustment was performed, the final sodium concentration and extent of oxalate removal would be prone to change. As such, the strategy for completing the final wash cycle is integral to maintaining the proper balance of chemical and physical requirements.

Reboul, S.; Click, D.; Lambert, D.

2010-12-10T23:59:59.000Z

6

UTILIZING STATISTICS TO DETERMINE HOW MUCH SAMPLING AND ANALYSISIS WARRANTED TO SUPPORT SAVANNAH RIVER SITEHIGH LEVEL WASTE SLUDGE BATCH PREPARATION  

SciTech Connect

Accelerated cleanup initiatives at the SRS include expediting radioactive sludge processing. Sludge is the highest risk component of waste since it contains the highest concentrations of long-lived radionuclides. The sludge is staged into ''batches'' that are then the feed material to the Defense Waste Processing Facility (DWPF) which vitrifies the waste into a safe form for permanent disposal. The preparation of each batch includes sampling and analysis of the slurried material. The results of the characterization are used as the bases for batch blending and processing decisions. Uncertainty is inherent in the information used for planning. There is uncertainty in the quantity of sludge contained in a tank, the waste composition, and the waste physical properties. The goal of this analysis is to develop the basis for the number of physical samples that should be taken from the slurried waste tank and the number of replicates of laboratory measurements that should be performed in order to achieve a specified uncertainty level. Recommendations for sampling and analysis strategies are made based on the results of the analysis.

Hamm, B

2007-05-17T23:59:59.000Z

7

SLUDGE BATCH 4 SIMULANT FLOWSHEET STUDIES: PHASE II RESULTS  

DOE Green Energy (OSTI)

The Defense Waste Processing Facility (DWPF) will transition from Sludge Batch 3 (SB3) processing to Sludge Batch 4 (SB4) processing in early fiscal year 2007. Tests were conducted using non-radioactive simulants of the expected SB4 composition to determine the impact of varying the acid stoichiometry during the Sludge Receipt and Adjustment Tank (SRAT) process. The work was conducted to meet the Technical Task Request (TTR) HLW/DWPF/TTR-2004-0031 and followed the guidelines of a Task Technical and Quality Assurance Plan (TT&QAP). The flowsheet studies are performed to evaluate the potential chemical processing issues, hydrogen generation rates, and process slurry rheological properties as a function of acid stoichiometry. Initial SB4 flowsheet studies were conducted to guide decisions during the sludge batch preparation process. These studies were conducted with the estimated SB4 composition at the time of the study. The composition has changed slightly since these studies were completed due to changes in the sludges blended to prepare SB4 and the estimated SB3 heel mass. The following TTR requirements were addressed in this testing: (1) Hydrogen and nitrous oxide generation rates as a function of acid stoichiometry; (2) Acid quantities and processing times required for mercury removal; (3) Acid quantities and processing times required for nitrite destruction; and (4) Impact of SB4 composition (in particular, oxalate, manganese, nickel, mercury, and aluminum) on DWPF processing (i.e. acid addition strategy, foaming, hydrogen generation, REDOX control, rheology, etc.).

Stone, M; David Best, D

2006-09-12T23:59:59.000Z

8

FRIT DEVELOPMENT FOR SLUDGE BATCH 6  

SciTech Connect

The Savannah River National Laboratory (SRNL) evaluated a large number of Sludge Batch 6 (SB6) composition projections to support frit optimization for SB6 vitrification at the Defense Waste Processing Facility (DWPF). The evaluations discussed in this report occurred over a period of about 4 months, and included about 40 composition projections, developed by both Savannah River Remediation (SRR) and SRNL. Paper study assessments were used to evaluate the sludge composition projections with arrays of potential frit compositions using the predictive models in the DWPF Product Composition Control System (PCCS). Both nominal sludge compositions and sludge compositions with anticipated compositional variation were considered. The model predictions were used to identify candidate frit compositions for each SB6 projection and to provide some guidance to SRR on washing and blending strategies for SB6 preparation. This report presents a chronological review of this process and summarizes the findings at each stage. Following initial feedback from this work, the number of washes in Tank 51 was reduced to increase the projected sodium concentration in SB6. Analyses of predicted frit performance before and after a potential decant of Tank 40 showed that the post-decant SB6 composition would be difficult to process with any frit composition and that this scenario should be avoided. Based on the most recent SB6 projections (February 2010 SB6 composition projections developed at SRNL using the measured SB6 qualification sample composition and the revised Tank Farm washing plan), Frit 418 appears to be viable for SB6 processing at a target waste loading of 36%. A Nominal Stage PCCS Measurement Acceptability Region (MAR) assessment gave projected operating windows of 25-41% waste loading, limited by predictions of nepheline crystallization. The projected operating window is reduced to 25-38% waste loading when anticipated compositional variation is considered, again limited by predictions of nepheline crystallization. Blend points between 62 and 40 inches of Sludge Batch 5 (SB5) heel in Tank 40 had no practical impact on the projected performance of Frit 418. This assessment is made from a paper study approach only and assumes that no decant of Tank 40 will occur during SB6 processing. A decant of Tank 40 would reduce the Na2O concentration in Tank 40 to a point where it would be very difficult to target a waste loading of 36% for SB6 with Frit 418. The performance of Frit 418 with SB6 is limited by predictions of nepheline crystallization, which is a durability limiting constraint. Alternatives to Frit 418 are available that can provide equivalent projected operating windows and are limited by process related constraints (i.e., liquidus temperature predictions) rather than durability limiting constraints. A separate memorandum has recently been issued that discusses the use of Frit 418 for SB6 vitrification.1 potential differences in melt rate among these alternative frits will be discussed in a forthcoming technical report.

Fox, K.; Edwards, T.; Zamecnik, J.

2010-05-13T23:59:59.000Z

9

SLUDGE BATCH 7B GLASS VARIABILITY STUDY  

SciTech Connect

The Defense Waste Processing Facility (DWPF) is preparing to initiate processing Sludge Batch 7b (SB7b). In support of the upcoming processing, the Savannah River National Laboratory (SRNL) provided a recommendation to utilize Frits 418 with a 6% Na{sub 2}O addition (26 wt% Na{sub 2}O in sludge) and 702 with a 4% Na{sub 2}O addition (24 wt% Na{sub 2}O in sludge) to process SB7b. This recommendation was based on assessments of the compositional projections for SB7b available at the time from the Savannah River Remediation (SRR). To support qualification of SB7b, SRNL executed a variability study to assess the applicability of the current durability models for SB7b. The durability models were assessed over the expected composition range of SB7b, including potential caustic additions, combined with Frits 702 and 418 over a 32-40% waste loading (WL) range. Thirty four glasses were selected based on Frits 418 and 702 coupled with the sludge projections with an additional 4-6% Na{sub 2}O to reflect the potential caustic addition. Six of these glasses, based on average nominal sludge compositions including the appropriate caustic addition, were developed for both Frit 418 and Frit 702 at 32, 36 and 40% WL to provide coverage in the center of the anticipated SB7b glass region. All glasses were fabricated and characterized using chemical composition analysis, X-ray diffraction (XRD) and the Product Consistency Test (PCT). To comply with the DWPF Glass Product Control Program, a total of thirty four glasses were fabricated to assess the applicability of the current DWPF PCCS durability models. Based on the measured PCT response, all of the glasses were acceptable with respect to the Environmental Assessment (EA) benchmark glass regardless of thermal history. The NL[B] values of the SB7b variability study glasses were less than 1.99 g/L as compared to 16.695 g/L for EA. A small number of the D-optimally selected 'outer layer' extreme vertices (EV) glasses were not predictable using the current Product Composition Control System (PCCS) models for durability, but were acceptable compared to the EA glass when tested. These glasses fell outside of the lower 95% confidence band, which demonstrates conservatism in the model. A few of the glasses fell outside of the upper 95% confidence band; however, these particular glasses have normalized release values that were much lower than the values of EA and should be of no practical concern. Per the requirements of the DWPF Glass Product Control Program, the PCCS durability models have been shown to be applicable to the SB7b sludge system with a range of Na{sub 2}O concentrations blended with Frits 418 or 702. PCT results from the glasses fabricated as part of the variability study were shown to be predictable by the current DWPF PCCS models and/or acceptable with respect to the EA benchmark glass regardless of thermal history or compositional view.

Johnson, F.; Edwards, T.

2011-10-25T23:59:59.000Z

10

Hydrogen Evolution and Sludge Suspension During the Preparation of the First Batch of Sludge at the Savannah River Site  

DOE Green Energy (OSTI)

The first batch of High Level Radioactive Sludge for the Defense Waste Processing Facility is being prepared in two 4.9 million liter waste tanks. The preparation involves removing water soluble salts by washing (water addition, sludge suspension, settling and decantation). Sludge suspension is accomplished using long shafted slurry pumps that are mounted on rotating turntables. During the sludge suspension runs in 1993 and 1994, the slurry pumps` cleaning radius was determined to be less than that expected from previous determinations using synthetic sludge in a full size waste tank mockup. Hydrogen concentrations in the tanks` vapor space were monitored during the sludge suspension activities. As expected, the initial agitation of the sludge increased the hydrogen concentration, however, with the controls in place the hydrogen concentration was maintained below seven percent of the lower flammability limit

Hay, M.S.; Lee, E.D.

1995-03-01T23:59:59.000Z

11

SLUDGE BATCH VARIABILITY STUDY WITH FRIT 418  

SciTech Connect

The Defense Waste Processing Facility (DWPF) initiated processing Sludge Batch 6 (SB6) in the summer of 2010. In support of processing, the Savannah River National Laboratory (SRNL) provided a recommendation to utilize Frit 418 to process SB6. This recommendation was based on assessments of the compositional projections for SB6 available at the time from the Liquid Waste Organization (LWO) and SRNL (using a model-based approach). To support qualification of SB6, SRNL executed a variability study to assess the applicability of the current durability models for SB6. The durability models were assessed over the expected Frit 418-SB6 composition range. Seventeen glasses were selected for the variability study based on the sludge projections used in the frit recommendation. Five of the glasses are based on the centroid of the compositional region, spanning a waste loading (WL) range of 32 to 40%. The remaining twelve glasses are extreme vertices (EVs) of the sludge region of interest for SB6 combined with Frit 418 and are all at 36% WL. These glasses were fabricated and characterized using chemical composition analysis, X-ray diffraction (XRD) and the Product Consistency Test (PCT). After initiating the SB6 variability study, the measured composition of the SB6 Tank 51 qualification glass produced at the SRNL Shielded Cells Facility indicated that thorium was present in the glass at an appreciable concentration (1.03 wt%), which made it a reportable element for SB6. This concentration of ThO{sub 2} resulted in a second phase of experimental studies. Five glasses were formulated that were based on the centroid of the new sludge compositional region combined with Frit 418, spanning a WL range of 32 to 40%. These glasses were fabricated and characterized using chemical composition analysis and the PCT. Based on the measured PCT response, all of the glasses (with and without thorium) were acceptable with respect to the Environmental Assessment (EA) reference glass regardless of thermal history. All of the normalized boron releases were less than 1 g/L. While all of the targeted glass compositions were predictable with respect to the Product Composition Control System (PCCS) models for durability, a small number of the measured glass compositions were located outside of the lower prediction limit indicating poorer durability than what was actually measured. These unpredictable glasses were in the same lithium metaborate (LM) preparation block during the chemical analyses, which resulted in measured compositions that were not representative of the target compositions. A review of the data did not indicate a clear cause for the problem. Re-digestion and re-measurement of three glasses from this preparation block yielded glass compositions closer to the target values and predicted PCT responses within the PCCS model uncertainty. Therefore, it is believed that the glasses were correctly fabricated and the targeted compositions are closer representations of the true compositions. Per the requirements of the DWPF Glass Product Control Program, the PCCS durability models have been shown to be applicable for the SB6/Frit 418 glass system. PCT results from the glasses fabricated as part of the variability study were shown to be predictable and/or acceptable with respect to the DWPF PCCS models. In addition, the inclusion of ThO{sub 2} was shown to have minimal impact on the acceptability and predictability of the variability study glasses.

Johnson, F.; Edwards, T.

2010-11-29T23:59:59.000Z

12

HIGH LEVEL WASTE SLUDGE BATCH 4 VARIABILITY STUDY  

Science Conference Proceedings (OSTI)

The Defense Waste Processing Facility (DWPF) is preparing for vitrification of High Level Waste (HLW) Sludge Batch 4 (SB4) in early FY2007. To support this process, the Savannah River National Laboratory (SRNL) has provided a recommendation to utilize Frit 503 for vitrifying this sludge batch, based on the composition projection provided by the Liquid Waste Organization on June 22, 2006. Frit 418 was also recommended for possible use during the transition from SB3 to SB4. A critical step in the SB4 qualification process is to demonstrate the applicability of the durability models, which are used as part of the DWPF's process control strategy, to the glass system of interest via a variability study. A variability study is an experimentally-driven assessment of the predictability and acceptability of the quality of the vitrified waste product that is anticipated from the processing of a sludge batch. At the DWPF, the durability of the vitrified waste product is not directly measured. Instead, the durability is predicted using a set of models that relate the Product Consistency Test (PCT) response of a glass to the chemical composition of that glass. In addition, a glass sample is taken during the processing of that sludge batch, the sample is transmitted to SRNL, and the durability is measured to confirm acceptance. The objective of a variability study is to demonstrate that these models are applicable to the glass composition region anticipated during the processing of the sludge batch - in this case the Frit 503 - SB4 compositional region. The success of this demonstration allows the DWPF to confidently rely on the predictions of the durability/composition models as they are used in the control of the DWPF process.

Fox, K; Tommy Edwards, T; David Peeler, D; David Best, D; Irene Reamer, I; Phyllis Workman, P

2006-10-02T23:59:59.000Z

13

SLUDGE BATCH 6/TANK 51 SIMULANT CHEMICAL PROCESS CELL SIMULATIONS  

DOE Green Energy (OSTI)

Qualification simulant testing was completed to determine appropriate processing conditions and assumptions for the Sludge Batch 6 (SB6) Shielded Cells demonstration of the DWPF flowsheet using the qualification sample from Tank 51 for SB6 after SRNL washing. It was found that an acid addition window of 105-139% of the DWPF acid equation (100-133% of the Koopman minimum acid equation) gave acceptable Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) results for nitrite destruction and hydrogen generation. Hydrogen generation occurred continuously after acid addition in three of the four tests. The three runs at 117%, 133%, and 150% stoichiometry (Koopman) were all still producing around 0.1 lb hydrogen/hr at DWPF scale after 42 hours of boiling in the SRAT. The 150% acid run reached 110% of the DWPF SRAT limit of 0.65 lb H{sub 2}/hr, and the 133% acid run reached 75% of the DWPF SME limit of 0.223 lb H{sub 2}/hr. Conversely, nitrous oxide generation was subdued compared to previous sludge batches, staying below 25 lb/hr in all four tests or about a fourth as much as in comparable SB4 testing. Two other processing issues were noted. First, incomplete mercury suspension impacted mercury stripping from the SRAT slurry. This led to higher SRAT product mercury concentrations than targeted (>0.45 wt% in the total solids). Associated with this issue was a general difficulty in quantifying the mass of mercury in the SRAT vessel as a function of time, especially as acid stoichiometry increased. About ten times more mercury was found after drying the 150% acid SME product to powder than was indicated by the SME product sample results. Significantly more mercury was also found in the 133% acid SME product samples than was found during the SRAT cycle sampling. It appears that mercury is segregating from the bulk slurry in the SRAT vessel, as mercury amalgam deposits for example, and is not being resuspended by the agitators. The second processing issue was significant ammonium ion formation as the acid stoichiometry was increased due to the high noble metal-high mercury feed conditions. Ammonium ion was found partitioned between the SRAT product slurry and the condensate from the lab-scale off-gas chiller downstream of the SRAT condenser. The ammonium ion was produced from nitrate ion by formic acid. Formate losses increased with increasing acid stoichiometry reaching 40% at the highest stoichiometry tested. About a third of the formate loss at higher acid stoichiometries appeared to be due to ammonia formation. The full extent of ammonia formation was not determined in these tests, since uncondensed ammonia vapor was not quantified; but total formation was bounded by the combined loss of nitrite and nitrate. Nitrate losses during ammonia formation led to nitrite-to-nitrate conversion values that were negative in three of the four tests. The negative results were an artifact of the calculation that assumes negligible SRAT nitrate losses. The sample data after acid addition indicated that some of the initial nitrite was converted to nitrate, so the amount of nitrate destroyed included nitrite converted to nitrate plus some of the added nitrate from the sludge and nitric acid. It is recommended that DWPF investigate the impact of SME product ammonium salts on melter performance (hydrogen, redox). It was recommended that the SB6 Shielded Cells qualification run be performed at 115% acid stoichiometry and allow about 35 hours of boiling for mercury stripping at the equivalent of a 5,000 lb/hr boil-up rate.

Koopman, David; Best, David

2010-04-28T23:59:59.000Z

14

SULFATE SOLUBILITY LIMIT VERIFICATION FOR DWPF SLUDGE BATCH 7A  

Science Conference Proceedings (OSTI)

During processing at the Defense Waste Processing Facility (DWPF), high sulfate concentrations in the feed are a concern to DWPF as it can lead to the formation of a detrimental, sulfate-rich, molten salt phase on the surface of the glass melt pool. To avoid these issues, a sulfate concentration limit was implemented into the Product Composition Control System (PCCS). Related to SB7a frit development efforts, the Savannah River National Laboratory (SRNL) assessed the viability of using the current 0.6 wt % SO{sub 4}{sup 2-} limit set for SB6 (in glass) and the possibility of increasing the SO{sub 4}{sup 2-} solubility limit in PCCS to account for anticipated sulfur concentrations, targeted waste loadings, and inclusion of secondary streams (e.g., Actinide Removal Process (ARP)) with two recommended frits (Frit 418 and Frit 702) for SB7a processing. For a nominal SB7a blend with a 63 inch SB6 heel remaining in Tank 40 (projection SB7a-63), a 0.60 wt% SO{sub 4}{sup 2-} in glass limit was determined for waste loadings of 34 wt% up to 40 wt% with Frit 418 based on crucible melts with batched chemicals. SRNL also examined the inclusion of ARP for the same blending scenario (SB7a-63-ARP) with Frit 418 and at least a 0.6 wt% SO{sub 4}{sup 2-} level, and waste loadings of 34 wt% to 40 wt% were also acceptable. When a visible yellow and/or white sulfate salt layer was visible on the surface of any cooled glass, it was assumed to have surpassed the solubility limit of SO{sub 4}{sup 2-} for that particular composition. All of the glasses fabricated at these concentrations did not exhibit a sulfate rich salt layer on the surface of the glass melt and retained the majority of the batched SO{sub 4}{sup 2-}. At higher levels of SO{sub 4}{sup 2-} 'spiked' into the projected sludge compositions over the aforementioned interval of waste loadings, with Frit 418, low viscosity sulfur layers were observed on the surface of glass melts which confirm exceeding the solubility limit. The same sludge scenarios were also tested with Frit 702 and all glasses did not exhibit sulfur layers on the surfaces of the glass melts at spiking levels up to 0.80 wt% SO{sub 4}{sup 2-}. An ultimate SO{sub 4}{sup 2-} limit was not defined with Frit 702, but if projected SO{sub 4}{sup 2-} concentrations are expected to increase with the onset of SB7a processing, a higher limit is achievable with Frit 702 than is achievable with Frit 418. Given the anticipated concentration of SO{sub 4}{sup 2-} for SB7a, a SO{sub 4}{sup 2-} limit of 0.6 wt % SO{sub 4}{sup 2-} is recommended for processing using Frit 418. Once the confirmed SB7a composition is known and should a higher limit be needed, SRNL can re-evaluate the limit based on the actual composition and provide an updated recommendation. It has been observed that higher levels of SO{sub 4}{sup 2-} in glass can be retained with compositional changes to the frit, as was demonstrated by the glasses fabricated using Frit 702. SRNL also recommends the continuation of studies to define a more 'global' sulfate concentration limit to account for future sludge batch composition uncertainties.

Billings, A.

2011-04-19T23:59:59.000Z

15

FLOWSHEET FOR ALUMINUM REMOVAL FROM SLUDGE BATCH 6  

Science Conference Proceedings (OSTI)

Samples of Tank 12 sludge slurry show a substantially larger fraction of aluminum than originally identified in sludge batch planning. The Liquid Waste Organization (LWO) plans to formulate Sludge Batch 6 (SB6) with about one half of the sludge slurry in Tank 12 and one half of the sludge slurry in Tank 4. LWO identified aluminum dissolution as a method to mitigate the effect of having about 50% more solids in High Level Waste (HLW) sludge than previously planned. Previous aluminum dissolution performed in a HLW tank in 1982 was performed at approximately 85 C for 5 days and dissolved nearly 80% of the aluminum in the sludge slurry. In 2008, LWO successfully dissolved 64% of the aluminum at approximately 60 C in 46 days with minimal tank modifications and using only slurry pumps as a heat source. This report establishes the technical basis and flowsheet for performing an aluminum removal process in Tank 51 for SB6 that incorporates the lessons learned from previous aluminum dissolution evolutions. For SB6, aluminum dissolution process temperature will be held at a minimum of 65 C for at least 24 days, but as long as practical or until as much as 80% of the aluminum is dissolved. As planned, an aluminum removal process can reduce the aluminum in SB6 from about 84,500 kg to as little as 17,900 kg with a corresponding reduction of total insoluble solids in the batch from 246,000 kg to 131,000 kg. The extent of the reduction may be limited by the time available to maintain Tank 51 at dissolution temperature. The range of dissolution in four weeks based on the known variability in dissolution kinetics can range from 44 to more than 80%. At 44% of the aluminum dissolved, the mass reduction is approximately 1/2 of the mass noted above, i.e., 33,300 kg of aluminum instead of 66,600 kg. Planning to reach 80% of the aluminum dissolved should allow a maximum of 81 days for dissolution and reduce the allowance if test data shows faster kinetics. 47,800 kg of the dissolved aluminum will be stored in Tank 8 and 21,000 kg will be stored in saltcake via evaporation. Up to 77% of the total aluminum planned for SB6 may be removed via aluminum dissolution. Storage of the aluminum-laden supernate in Tank 8 will require routine evaluation of the free hydroxide concentration in order to maintain aluminum in solution. Periodic evaluation will be established on concurrent frequency with corrosion program samples as previously established for aluminum-laden supernate from SB5 that is stored in Tank 11.

Pike, J; Jeffrey Gillam, J

2008-12-17T23:59:59.000Z

16

TANK 40 FINAL SLUDGE BATCH 8 CHEMICAL CHARACTERIZATION RESULTS  

SciTech Connect

A sample of Sludge Batch 8 (SB8) was pulled from Tank 40 in order to obtain radionuclide inventory analyses necessary for compliance with the Waste Acceptance Product Specifications (WAPS). The SB8 WAPS sample was also analyzed for chemical composition, including noble metals, and fissile constituents, and these results are reported here. These analyses along with the WAPS radionuclide analyses will help define the composition of the sludge in Tank 40 that is currently being fed to the Defense Waste Processing Facility (DWPF) as SB8. At SRNL, the 3-L Tank 40 SB8 sample was transferred from the shipping container into a 4-L high density polyethylene bottle and solids were allowed to settle. Supernate was then siphoned off and circulated through the shipping container to complete the transfer of the sample. Following thorough mixing of the 3-L sample, a 553 g sub-sample was removed. This sub-sample was then utilized for all subsequent slurry sample preparations. Eight separate aliquots of the slurry were digested, four with HNO{sub 3}/HCl (aqua regia) in sealed Teflon? vessels and four with NaOH/Na{sub 2}O{sub 2} (alkali or peroxide fusion) using Zr crucibles. Two Analytical Reference Glass ? 1 (ARG-1) standards were digested along with a blank for each preparation. Each aqua regia digestion and blank was diluted to 1:100 mL with deionized water and submitted to Analytical Development (AD) for inductively coupled plasma ? atomic emission spectroscopy (ICP-AES) analysis, inductively coupled plasma ? mass spectrometry (ICP-MS) analysis, atomic absorption spectroscopy (AA) for As and Se, and cold vapor atomic absorption spectroscopy (CV-AA) for Hg. Equivalent dilutions of the alkali fusion digestions and blank were submitted to AD for ICP-AES analysis. Tank 40 SB8 supernate was collected from a mixed slurry sample in the SRNL Shielded Cells and submitted to AD for ICP-AES, ion chromatography (IC), total base/free OH-/other base, total inorganic carbon/total organic carbon (TIC/TOC) analyses. Weighted dilutions of slurry were submitted for IC, TIC/TOC, and total base/free OH-/other base analyses. Activities for U-233, U-235, and Pu-239 were determined from the ICP-MS data for the aqua regia digestions of the Tank 40 WAPS slurry using the specific activity of each isotope. The Pu-241 value was determined from a Pu-238/-241 method developed by SRNL AD and previously described.

Bannochie, C.

2013-09-19T23:59:59.000Z

17

SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE  

SciTech Connect

Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest projected noble metals content for SB7b. Characterization was performed on the Tank 51 SB7b samples and SRNL performed DWPF simulations using the Tank 40 SB7b material. This report documents: (1) The preparation and characterization of the Tank 51 SB7b and Tank 40 SB7b samples. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the SB7b Tank 40 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a nonradioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the SRAT receipt, SRAT product, and SME product. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7b related data together in a single permanent record and to discuss the overall aspects of SB7b processing.

Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

2011-11-16T23:59:59.000Z

18

SULFATE SOLUBILITY LIMIT VERIFICATION FOR DWPF SLUDGE BATCH 7B  

SciTech Connect

The objective of this study was to determine a sulfate solubility limit in glass for Sludge Batch 7b (SB7b). The SB7b composition projection provided by Savannah River Remediation (SRR) on May 25, 2011 was used as the basis for formulating glass compositions to determine the sulfate limit. Additions of Na{sub 2}O to the projected sludge composition were made by the Savannah River National Laboratory (SRNL) due to uncertainty in the final concentration of Na{sub 2}O for SB7b, which is dependent on washing effectiveness and the potential need to add NaOH to ensure an acceptable projected operating window. Additions of 4, 6, and 8 wt % Na{sub 2}O were made to the nominal May 25, 2011 composition projection. An updated SB7b composition projection was received from SRR on August 4, 2011. Due to compositional similarities, no additional experimental work using the August 4, 2011 compositions was considered to be necessary for this study. Both Frit 418 and Frit 702 were included in this study. The targeted sulfate (SO{sub 4}{sup 2-}) concentrations of the study glasses were selected within the range of 0.6 to 0.9 wt % in glass. A total of 52 glass compositions were selected based on the compositional variables of Na{sub 2}O addition, Actinide Removal Process (ARP) stream addition, waste loading, frit composition, and sulfate concentration. The glasses were batched, melted, and characterized following SRNL procedures. Visual observations were recorded for each glass after it cooled and used as in indicator of sulfur retention. Representative samples of each of the glasses fabricated were subjected to chemical analysis to determine whether the targeted compositions were met, as well as to determine the quantity of sulfate that was retained after melting. In general, the measured composition data showed that there were only minor issues in meeting the targeted compositions for the study glasses, and the measured sulfate concentrations for each study glass were within 10% of the targeted values. The results for the SB7b glasses fabricated with Frit 418 showed an apparent trend of increasing sulfate retention with increasing Na{sub 2}O additions to the 5/25/11 sludge projection. This trend appears contradictory to other recent studies of sulfate retention in Defense Waste Processing Facility (DWPF) type glasses. Additional apparent contradictions to this trend were found in the data collected in the present study. Overall, the results for the SB7b sulfate study glasses with Frit 418 and the 5/25/11 projection with Na{sub 2}O additions showed that subtle changes in this complex glass composition impacted the degree of sulfate retention. These results do however provide confidence that a 0.6 wt % sulfate limit in glass is warranted for Frit 418 with the SB7b compositions evaluated in this study. The results for the SB7b glasses fabricated with Frit 702 are consistent with those of the previous SB7a study in that Frit 702 allowed for higher sulfate retention as compared to Frit 418 for the same sludge compositions. It is recommended that the DWPF implement a sulfate concentration limit of 0.6 wt % in glass for SB7b processing with Frit 418. If a higher than projected sulfate concentration is measured when SB7b processing begins (i.e., if a sulfate concentration higher than 0.6 wt % becomes necessary to achieve targeted waste loadings), DWPF should consider a transition to Frit 702. The sulfate limit could likely be raised to 0.8 wt % by transitioning to this frit. However, if DWPF considers transitioning from Frit 418 to Frit 702, additional glasses should be fabricated to confirm this higher limit due to the issues with incorrect B{sub 2}O{sub 3} concentrations for some of the glasses made with Frit 702 in this study. There are several factors other than sulfate retention that must also be carefully considered prior to changing frit compositions.

Fox, K.

2011-10-03T23:59:59.000Z

19

REPORTABLE RADIONUCLIDES IN DWPF SLUDGE BATCH 7A (MACROBATCH 8)  

Science Conference Proceedings (OSTI)

The Waste Acceptance Product Specifications (WAPS) 1.2 require that the waste producer 'shall report the curie inventory of radionuclides that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115.' As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type all radionuclides that have half-lives longer than 10 years and contribute greater than 0.01 percent of the total curie inventory from the time of production through the 1100 year period from 2015 through 3115. The initial list of radionuclides to be reported is based on the design-basis glass identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report. However, it is required that the list be expanded if other radionuclides with half-lives greater than 10 years are identified that meet the 'greater than 0.01% of the curie inventory' criterion. Specification 1.6 of the WAPS, International Atomic Energy Agency Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, and U-238; and Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete list of reportable radionuclides must also include these sets of U and Pu isotopes - and the U and Pu isotopic mass distributions must be identified. The DWPF receives HLW sludge slurry from Savannah River Site (SRS) Tank 40. For Sludge Batch 7a (SB7a), the waste in Tank 40 contained a blend of the heel from Sludge Batch 6 (SB6) and the Sludge Batch 7 (SB7) material transferred to Tank 40 from Tank 51. This sludge blend is also referred to as Macrobatch 8. Laboratory analyses of a Tank 40 sludge sample were performed to quantify the concentrations of pertinent radionuclides in the SB7a waste. Subsequently, radiological decay and in-growth were calculated over the time period from 2015 to 3115. This provided a basis for characterizing the radionuclide content of SB7a over time and for identifying the 'reportable radionuclides.' Details of the characterization methodology and the analytical results are the focus of this report. This work was performed at the request of the Waste Solidification Engineering Department of Savannah River Remediation, initiated via Technical Task Request (TTR) HLW-DWPF-TTR-2010-0031. A minor revision in the reporting requirements was requested via a subsequent email communication. The work was conducted in accordance with the protocols identified in Task Technical and Quality Assurance Plan SRNL-RP-2010-01218 and Analytical Study Plan SRNL-RP-2010-01219. All of the raw data related to this scope have been recorded in laboratory notebook SRNL-NB-2011-00061. The overall goal of this task was to characterize the radionuclide content of the SB7a waste sufficiently to meet the WAPS and DWPF reporting requirements. The specific objectives were: (1) Quantify the current concentrations of all radionuclides impacting (or potentially-impacting) the total curie content between calendar years 2011 and 3115. Also quantify the current concentrations of other radionuclides specifically requested in the TTR or required by the WAPS. (2) Calculate future concentrations of decayed and in-grown radionuclides impacting the total curie content between calendar years 2015 and 3115; (3) Identify as 'reportable' all radionuclides contributing {ge} 0.01% of the total curie content from 2015 to 3115 and having half-lives {ge} 10 years.

Reboul, S.; Diprete, D.; Click, D.; Bannochie, C.

2011-12-20T23:59:59.000Z

20

SLUDGE BATCH 6/TANK 40 SIMULANT CHEMICAL PROCESS CELL SIMULATIONS  

SciTech Connect

Phase III simulant flowsheet testing was completed using the latest composition estimates for SB6/Tank 40 feed to DWPF. The goals of the testing were to determine reasonable operating conditions and assumptions for the startup of SB6 processing in the DWPF. Testing covered the region from 102-159% of the current DWPF stoichiometric acid equation. Nitrite ion concentration was reduced to 90 mg/kg in the SRAT product of the lowest acid run. The 159% acid run reached 60% of the DWPF Sludge Receipt and Adjustment Tank (SRAT) limit of 0.65 lb H2/hr, and then sporadically exceeded the DWPF Slurry Mix Evaporator (SME) limit of 0.223 lb H2/hr. Hydrogen generation rates peaked at 112% of the SME limit, but higher than targeted wt% total solids levels may have been partially responsible for rates seen. A stoichiometric factor of 120% met both objectives. A processing window for SB6 exists from 102% to something close to 159% based on the simulant results. An initial recommendation for SB6 processing is at 115-120% of the current DWPF stoichiometric acid equation. The addition of simulated Actinide Removal Process (ARP) and Modular Caustic Side Solvent Extraction Unit (MCU) streams to the SRAT cycle had no apparent impact on the preferred stoichiometric factor. Hydrogen generation occurred continuously after acid addition in three of the four tests. The three runs at 120%, 118.4% with ARP/MCU, and 159% stoichiometry were all still producing around 0.1 lb hydrogen/hr at DWPF scale after 36 hours of boiling in the SRAT. The 120% acid run reached 23% of the SRAT limit and 37% of the SME limit. Conversely, nitrous oxide generation was subdued compared to previous sludge batches, staying below 29 lb/hr in all four tests or about a fourth as much as in comparable SB4 testing. Two processing issues, identified during SB6 Phase II flowsheet testing and qualification simulant testing, were monitored during Phase III. Mercury material balance closure was impacted by acid stoichiometry, and significant mercury was not accounted for in the highest acid run. Coalescence of elemental mercury droplets in the mercury water wash tank (MWWT) appeared to degrade with increasing stoichiometry. Observations were made of mercury scale formation in the SRAT condenser and MWWT. A tacky mercury amalgam with Rh, Pd, and Cu, plus some Ru and Ca formed on the impeller at 159% acid. It contained a significant fraction of the available Pd, Cu, and Rh as well as about 25% of the total mercury charged. Free (elemental) mercury was found in all of the SME products. Ammonia scrubbers were used during the tests to capture off-gas ammonia for material balance purposes. Significant ammonium ion formation was again observed during the SRAT cycle, and ammonia gas entered the off-gas as the pH rose during boiling. Ammonium ion production was lower than in the SB6 Phase II and the qualification simulant testing. Similar ammonium ion formation was seen in the ARP/MCU simulation as in the 120% flowsheet run. A slightly higher pH caused most of the ammonium to vaporize and collect in the ammonia scrubber reflux solution. Two periods of foaminess were noted. Neither required additional antifoam to control the foam growth. A steady foam layer formed during reflux in the 120% acid run. It was about an inch thick, but was 2-3 times more volume of bubbles than is typically seen during reflux. A similar foam layer also was seen during caustic boiling of the simulant during the ARP addition. While frequently seen with the radioactive sludge, foaminess during caustic boiling with simulants has been relatively rare. Two further flowsheet tests were performed and will be documented separately. One test was to evaluate the impact of process conditions that match current DWPF operation (lower rates). The second test was to evaluate the impact of SRAT/SME processing on the rheology of a modified Phase III simulant that had been made five times more viscous using ultrasonication.

Koopman, David

2010-04-28T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

The Impact of the Source of Alkali on Sludge Batch 3 Melt Rate (U)  

Science Conference Proceedings (OSTI)

Previous Savannah River National Laboratory (SRNL) melt rate tests in support of the Defense Waste Processing Facility (DWPF) have indicated that improvements in melt rate can be achieved through an increase in the total alkali of the melter feed. Higher alkali can be attained by the use of an ''underwashed'' sludge, a high alkali frit, or a combination of the two. Although the general trend between melt rate and total alkali (in particular Na{sub 2}O content) has been demonstrated, the question of ''does the source of alkali (SOA) matter?'' still exists. Therefore the purpose of this set of tests was to determine if the source of alkali (frit versus sludge) can impact melt rate. The general test concept was to transition from a Na{sub 2}O-rich frit to a Na{sub 2}O-deficient frit while compensating the Na{sub 2}O content in the sludge to maintain the same overall Na{sub 2}O content in the melter feed. Specifically, the strategy was to vary the amount of alkali in frits and in the sludge batch 3 (SB3) sludge simulant (midpoint or baseline feed was SB3/Frit 418 at 35% waste loading) so that the resultant feeds had the same final glass composition when vitrified. A set of SOA feeds using frits ranging from 0 to 16 weight % Na{sub 2}O (in 4% increments) was first tested in the Melt Rate Furnace (MRF) to determine if indeed there was an impact. The dry-fed MRF tests indicated that if the alkali is too depleted from either the sludge (16% Na{sub 2}O feed) or the frit (the 0% Na{sub 2}O feed), then melt rate was negatively impacted when compared to the baseline SB3/Frit 418 feed currently being processed at DWPF. The MRF melt rates for the 4 and 12% SOA feeds were similar to the baseline SB3/Frit 418 (8% SOA) feed. Due to this finding, a smaller subset of SOA feeds that could be processed in the DWPF (4 and 12% SOA feeds) was then tested in the Slurry-fed Melt Rate Furnace (SMRF). The results from a previous SMRF test with SB3/Frit 418 (Smith et al. 2004) were used as the SMRF melt rate of the baseline feed. The SOA SMRF test results agreed with those of the MRF tests for these two feeds as the melt rates were similar to the baseline SB3/Frit 418 feed. In other words, the source of alkali was close enough to the baseline feed as to not negatively impact melt rate. Based on these results, there appears to be an acceptable range of the source of alkali that results in the highest melt rate for a particular sludge batch. If, however, the alkali is too depleted from either the sludge or the frit, then melt rate will be lower. Although SB3 simulant sludge and Frit 418 were used for these tests, it was not the intent of these tests to determine an optimum source of alkali range for SB3. Rather, the findings of these tests should be used to help in the decision process for future sludge batch washing and/or blending strategies. The results, however, do confirm that the current processing of SB3 is being performed in the proper source of alkali range. Because all of this testing was performed on small-scale equipment with slurried, non-radioactive simulant, the exact impact of the source of alkali with SB3 in the DWPF melter could not be fully evaluated.

Smith, M

2005-04-01T23:59:59.000Z

22

ANALYSIS OF DWPF SLUDGE BATCH 6 (MACROBATCH 7) POUR STREAM GLASS SAMPLES  

SciTech Connect

The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 6 (SB6), also referred to as Macrobatch 7 (MB7), in June 2010. SB6 is a blend of the heel of Tank 40 from Sludge Batch 5 (SB5), H-Canyon Np transfers and SB6 that was transferred to Tank 40 from Tank 51.1 SB6 was processed using Frit 418. Sludge is received into the DWPF Chemical Processing Cell (CPC) and is processed through the Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator Tank (SME). The treated sludge slurry is then transferred to the Melter Feed Tank (MFT) and fed to the melter. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP) and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. The DWPF requested various analyses of radioactive glass samples obtained from the melter pour stream during processing of SB6 as well as reduction/oxidation (REDOX) analysis of MFT samples to determine the impact of Argon bubbling. Sample analysis followed the Task Technical and Quality Assurance Plan (TTQAP) and an Analytical Study Plan (ASP). Four Pour Stream (PS) glass samples and two MFT slurry samples were delivered to the Savannah River National Laboratory (SRNL) from the DWPF. Table 1-1 lists the sample information for each pour stream glass sample. SB6 PS3 (S03472) was selected as the official pour stream sample for SB6 and full analysis was requested. This report details the visual observations of the as-received SB6 PS No.3 glass sample as well as results for the chemical composition, Product Consistency Test (PCT), radionuclide content, noble metals, and glass density. REDOX results will be provided for all four pour stream samples and vitrified samples of MFT-558 and MFT-568A. Where appropriate, data from other pour stream samples will be provided.

Johnson, F.

2012-01-20T23:59:59.000Z

23

SLUDGE BATCH SUPPLEMENTAL SRAT RUNS EFFECTS OF YIELD STRESS AND CYCLE TIME INCREASE  

DOE Green Energy (OSTI)

The Defense Waste Processing Facility (DWPF) has transitioned from Sludge Batch 5 (SB5) processing to Sludge Batch 6 (SB6) processing. Phase III-Tank 40 Chemical Process Cell (CPC) flowsheet simulations have been completed to determine the initial processing conditions for the DWPF transition. The impact of higher yield stress (SB-25) and cycle time extension (SB6-26) on the physical and chemical effects of SB6 processing during the SRAT (Sludge Receipt and Adjustment Tank) cycle were evaluated. No significant impacts on the SRAT chemistry were noted during the higher yield stress run. In particular, no impact on mercury stripping was noted, indicating that settling of elemental mercury was not the primary factor in the low mercury recovery noted in the flowsheet testing. The SRAT product from this run retained the higher yield stress of the starting sludge. The run indicated that ultrasonication is an effective tool to increase the yield stress of simulants to targeted values and the chemistry of downstream processing is not impacted. Significant differences were noted in the cycle time extension test compared to the Phase III flowsheet baseline runs. Large decreases in the ammonia and hydrogen generation rates were noted along with reduced mercury stripping efficiency. The latter effect is similar to that of operating under a high acid stoichiometry. It is conceivable that, under the distinctly different conditions of high formic acid concentration (high acid run) or slow formic acid addition (extended run), that mercury could form amalgams with noble metals, possibly rendering both inert. Thus, the removal of free mercury and noble metals could decrease the rate of catalytic formic acid reactions which would decrease generation of ammonium and hydrogen. The potential underlying reasons for the behavior noted during this run would require additional testing.

Fernandez, A.

2010-08-10T23:59:59.000Z

24

RECOMMENDED FRIT COMPOSITION FOR INITIAL SLUDGE BATCH 5 PROCESSING AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

The Savannah River National Laboratory (SRNL) Frit Development Team recommends that the Defense Waste Processing Facility (DWPF) utilize Frit 418 for initial processing of high level waste (HLW) Sludge Batch 5 (SB5). The extended SB5 preparation time and need for DWPF feed have necessitated the use of a frit that is already included on the DWPF procurement specification. Frit 418 has been used previously in vitrification of Sludge Batches 3 and 4. Paper study assessments predict that Frit 418 will form an acceptable glass when combined with SB5 over a range of waste loadings (WLs), typically 30-41% based on nominal projected SB5 compositions. Frit 418 has a relatively high degree of robustness with regard to variation in the projected SB5 composition, particularly when the Na{sub 2}O concentration is varied. The acceptability (chemical durability) and model applicability of the Frit 418-SB5 system will be verified experimentally through a variability study, to be documented separately. Frit 418 has not been designed to provide an optimal melt rate with SB5, but is recommended for initial processing of SB5 until experimental testing to optimize a frit composition for melt rate can be completed. Melt rate performance can not be predicted at this time and must be determined experimentally. Note that melt rate testing may either identify an improved frit for SB5 processing (one which produces an acceptable glass at a faster rate than Frit 418) or confirm that Frit 418 is the best option.

Fox, K; Tommy Edwards, T; David Peeler, D

2008-06-25T23:59:59.000Z

25

FRIT OPTIMIZATION FOR SLUDGE BATCH PROCESSING AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

The Savannah River National Laboratory (SRNL) Frit Development Team recommends that the Defense Waste Processing Facility (DWPF) utilize Frit 418 for initial processing of high level waste (HLW) Sludge Batch 5 (SB5). The extended SB5 preparation time and need for DWPF feed have necessitated the use of a frit that is already included on the DWPF procurement specification. Frit 418 has been used previously in vitrification of Sludge Batches 3 and 4. Paper study assessments predict that Frit 418 will form an acceptable glass when combined with SB5 over a range of waste loadings (WLs), typically 30-41% based on nominal projected SB5 compositions. Frit 418 has a relatively high degree of robustness with regard to variation in the projected SB5 composition, particularly when the Na{sub 2}O concentration is varied. The acceptability (chemical durability) and model applicability of the Frit 418-SB5 system will be verified experimentally through a variability study, to be documented separately. Frit 418 has not been designed to provide an optimal melt rate with SB5, but is recommended for initial processing of SB5 until experimental testing to optimize a frit composition for melt rate can be completed. Melt rate performance can not be predicted at this time and must be determined experimentally. Note that melt rate testing may either identify an improved frit for SB5 processing (one which produces an acceptable glass at a faster rate than Frit 418) or confirm that Frit 418 is the best option.

Fox, K.

2009-01-28T23:59:59.000Z

26

SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 7A QUALIFICATION  

SciTech Connect

Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry (Sludge Batch 7a*) be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). Sludge Batch 7a (SB7a) is composed of portions of Tanks 4, 7, and 12; the Sludge Batch 6 heel in Tank 51; and a plutonium stream from H Canyon. SRNL received the Tank 51 qualification sample (sample ID HTF-51-10-125) following sludge additions to Tank 51. This report documents: (1) The washing (addition of water to dilute the sludge supernate) and concentration (decanting of supernate) of the SB7a - Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the washed Tank 51 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a non-radioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7a related data together in a single permanent record and to discuss the overall aspects of SB7a processing.

Pareizs, J.; Billings, A.; Click, D.

2011-07-08T23:59:59.000Z

27

SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 5 QUALIFICATION  

SciTech Connect

Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that underwent aluminum dissolution in late 2007 to reduce the total mass of sludge solids and aluminum being fed to the Defense Waste Processing Facility (DWPF) and Purex sludge transferred from Tank 7. Following aluminum dissolution, the addition of Tank 7 sludge and excess Pu to Tank 51, Liquid Waste Operations (LWO) provided the Savannah River National Laboratory (SRNL) a 3-L sample of Tank 51 sludge for SB5 qualification. SB5 qualification included washing the sample per LWO plans/projections (including the addition of a Pu/Be stream from H Canyon), DWPF Chemical Process Cell (CPC) simulations, waste glass fabrication (vitrification), and waste glass chemical durability evaluation. This report documents: (1) The washing (addition of water to dilute the sludge supernatant) and concentration (decanting of supernatant) of the Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF CPC simulation using the washed Tank 51 sample. This includes a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid is added to the sludge to destroy nitrite and remove mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit is added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters for the CPC processing were based on work with a non radioactive simulant. (3) Vitrification of a portion of the SME product and Product Consistency Test (PCT) evaluation of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This work is controlled by a Task Technical and Quality Assurance Plan (TTQAP) , and analyses are guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF.

Pareizs, J; Cj Bannochie, C; Damon Click, D; Dan Lambert, D; Michael Stone, M; Bradley Pickenheim, B; Amanda Billings, A; Ned Bibler, N

2008-11-10T23:59:59.000Z

28

Sludge Washing And Demonstration Of The DWPF Flowsheet In The SRNL Shielded Cells For Sludge Batch 8 Qualification  

SciTech Connect

The current Waste Solidification Engineering (WSE) practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks to Tank 51. Tank 51 sludge is washed and transferred to Tank 40, the current Defense Waste Processing Facility (DWPF) feed tank. Prior to transfer of Tank 51 to Tank 40, the Savannah River National Laboratory (SRNL) typically simulates the Tank Farm and DWPF processes using a Tank 51 sample (referred to as the qualification sample). WSE requested the SRNL to perform characterization on a Sludge Batch 8 (SB8) sample and demonstrate the DWPF flowsheet in the SRNL shielded cells for SB8 as the final qualification process required prior to SB8 transfer from Tank 51 to Tank 40. A 3-L sample from Tank 51 (the SB8 qualification sample; Tank Farm sample HTF-51-12-80) was received by SRNL on September 20, 2012. The as-received sample was characterized prior to being washed. The washed material was further characterized and used as the material for the DWPF process simulation including a Sludge Receipt and Adjustment Tank (SRAT) cycle, a Slurry Mix Evaporator (SME) cycle, and glass fabrication and chemical durability measurements.

Pareizs, J. M.; Crawford, C. L.

2013-04-26T23:59:59.000Z

29

Verification Of The Defense Waste Processing Facility's (DWPF) Process Digestion Methods For The Sludge Batch 8 Qualification Sample  

SciTech Connect

This report contains the results and comparison of data generated from inductively coupled plasma – atomic emission spectroscopy (ICP-AES) analysis of Aqua Regia (AR), Sodium Peroxide/Sodium Hydroxide Fusion Dissolution (PF) and Cold Chem (CC) method digestions and Cold Vapor Atomic Absorption analysis of Hg digestions from the DWPF Hg digestion method of Sludge Batch 8 (SB8) Sludge Receipt and Adjustment Tank (SRAT) Receipt and SB8 SRAT Product samples. The SB8 SRAT Receipt and SB8 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB8 Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 7b (SB7b), to form the SB8 Blend composition.

Click, D. R.; Edwards, T. B.; Wiedenman, B. J.; Brown, L. W.

2013-03-18T23:59:59.000Z

30

SRS SLUDGE BATCH QUALIFICATION AND PROCESSING; HISTORICAL PERSPECTIVE AND LESSONS LEARNED  

SciTech Connect

This report provides a historical overview and lessons learned associated with the SRS sludge batch (SB) qualification and processing programs. The report covers the framework of the requirements for waste form acceptance, the DWPF Glass Product Control Program (GPCP), waste feed acceptance, examples of how the program complies with the specifications, an overview of the Startup Program, and a summary of continuous improvements and lessons learned. The report includes a bibliography of previous reports and briefings on the topic.

Cercy, M.; Peeler, D.; Stone, M.

2013-09-25T23:59:59.000Z

31

Analysis Of DWPF Sludge Batch 7a (Macrobatch 8) Pour Stream Samples  

SciTech Connect

The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 7a (SB7a), also referred to as Macrobatch 8 (MB8), in June 2011. SB7a is a blend of the heel of Tank 40 from Sludge Batch 6 (SB6) and the SB7a material that was transferred to Tank 40 from Tank 51. SB7a was processed using Frit 418. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP), which is governed by the DWPF Waste Compliance Plan, and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. Three pour stream glass samples and two Melter Feed Tank (MFT) slurry samples were collected while processing SB7a. These additional samples were taken during SB7a to understand the impact of antifoam and the melter bubblers on glass redox chemistry. The samples were transferred to the Savannah River National Laboratory (SRNL) where they were analyzed.

2012-10-24T23:59:59.000Z

32

Investigation of Sludge Batch 3 (Macrobatch 4) Glass Sample Anomalous Behavior  

Science Conference Proceedings (OSTI)

Two Defense Waste Processing Facility (DWPF) glass samples from Sludge Batch 3 (SB3) (Macrobatch 4) were received by the Savannah River National Laboratory (SRNL) on February 23, 2005. One sample, S02244, was designated for the Product Consistency Test (PCT) and elemental and radionuclide analyses. The second sample, S02247, was designated for archival storage. The samples were pulled from the melter pour stream during the feeding of Melter Feed Tank (MFT) Batch 308 and therefore roughly correspond to feed from Slurry Mix Evaporator (SME) Batches 306-308. During the course of preparing sample S02244 for PCT and other analyses two observations were made which were characterized as ''unusual'' or anomalous behavior relative to historical observations of glasses prepared for the PCT. These observations ultimately led to a series of scoping tests in order to determine more about the nature of the behavior and possible mechanisms. The first observation was the behavior of the ground glass fraction (-100 +200 mesh) for PCT analysis when contacted with deionized water during the washing phase of the PCT procedure. The behavior was analogous to that of an organic compound in the presence of water: clumping, floating on the water surface, and crawling up the beaker walls. In other words, the glass sample did not ''wet'' normally, displaying a hydrophobic behavior in water. This had never been seen before in 18 years SRNL PCT tests on either radioactive or non-radioactive glasses. Typical glass behavior is largely to settle to the bottom of the water filled beaker, though there may be suspended fines which result in some cloudiness to the wash water. The typical appearance is analogous to wetting sand. The second observation was the presence of faint black rings at the initial and final solution levels in the Teflon vessels used for the mixed acid digestion of S02244 glass conducted for compositional analysis. The digestion is composed of two stages, and at both the intermediate and the final content levels in the digestion vessel the rings were present. The rings had not been seen previously during glass digestions and were not present in the Analytical Reference Glass (ARG) standard samples digested, in separate vessels, along with the DWPF glass. What follows in this report are the results and analyses from various scoping experiments done in order to explain the anomalous behavior observed with DWPF glass S02244, along with a comparison with tests on sample S02247 where the anomalous wetting behavior was not observed.

Bannochie, C. J.; Bibler, N. E.; Peeler, D. K.

2005-08-15T23:59:59.000Z

33

SLUDGE BATCH 4 FOLLOW-UP QUALIFICATION STUDIES TO EVALUATE HYDROGEN GENERATION  

DOE Green Energy (OSTI)

Follow-up testing was conducted to better understand the excessive hydrogen generation seen in the initial Sludge Batch 4 (SB4) qualification Sludge Receipt and Adjustment Tank/Slurry Mix Evaporator (SRAT/SME) simulation in the Savannah River National Laboratory (SRNL) Shielded Cells. This effort included both radioactive and simulant work. The initial SB4 qualification test produced 0.59 lbs/hr hydrogen in the SRAT, which was just below the DWPF SRAT limit of 0.65 lbs/hr, and the test produced over 0.5 lbs/hr hydrogen in the SME cycle on two separate occasions, which were over the DWPF SME limit of 0.223 lbs/hr.

Pareizs, J; David Koopman, D; Dan Lambert, D; Cj Bannochie, C

2007-08-23T23:59:59.000Z

34

VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY'S (DWPF) PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 7A QUALIFICATION SAMPLE  

Science Conference Proceedings (OSTI)

For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs confirmation of the applicability of the digestion method to be used by the DWPF lab for elemental analysis of Sludge Receipt and Adjustment Tank (SRAT) receipt samples and SRAT product process control samples. DWPF SRAT samples are typically dissolved using a room temperature HF-HNO{sub 3} acid dissolution (i.e., DWPF Cold Chem Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICP-AES). This report contains the results and comparison of data generated from performing the Aqua Regia (AR), Sodium peroxide/Hydroxide Fusion (PF) and DWPF Cold Chem (CC) method digestions of Sludge Batch 7a (SB7a) SRAT Receipt and SB7a SRAT Product samples. The SB7a SRAT Receipt and SB7a SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constituates the SB7a Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 6 (SB6), to form the Sb7a Blend composition.

Click, D.; Edwards, T.; Jones, M.; Wiedenman, B.

2011-03-14T23:59:59.000Z

35

ANALYSIS OF DWPF SLUDGE BATCH 7A (MACROBATCH 8) POUR STREAM SAMPLES  

SciTech Connect

The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 7a (SB7a), also referred to as Macrobatch 8 (MB8), in June 2011. SB7a is a blend of the heel of Tank 40 from Sludge Batch 6 (SB6) and the SB7a material that was transferred to Tank 40 from Tank 51. SB7a was processed using Frit 418. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP), which is governed by the DWPF Waste Compliance Plan, and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. Three pour stream glass samples and two Melter Feed Tank (MFT) slurry samples were collected while processing SB7a. These additional samples were taken during SB7a to understand the impact of antifoam and the melter bubblers on glass redox chemistry. The samples were transferred to the Savannah River National Laboratory (SRNL) where they were analyzed. The following conclusions were drawn from the analytical results provided in this report: (1) The sum of oxides for the official SB7a pour stream glass is within the Product Composition Control System (PCCS) limits (95-105 wt%). (2) The average calculated Waste Dilution Factor (WDF) for SB7a is 2.3. In general, the measured radionuclide content of the official SB7a pour stream glass is in good agreement with the calculated values from the Tank 40 dried sludge results from the SB7a Waste Acceptance Program Specification (WAPS) sample. (3) As in previous pour stream samples, ruthenium and rhodium inclusions were detected by Scanning Electron Microscopy-Electron Dispersive Spectroscopy (SEM-EDS) in the official SB7a pour stream sample. (4) The Product Consistency Test (PCT) results indicate that the official SB7a pour stream glass meets the waste acceptance criteria for durability with a normalized boron release of 0.64 g/L, which is an order of magnitude less than the Environmental Assessment (EA) glass. (5) The measured density of the SB7a pour stream glass was 2.7 g/cm{sup 3}. (6) The Fe{sup 2+}/{Sigma}Fe ratios of the SB7a pour stream samples were in the range of 0.04-0.13, while the MFT sample glasses prepared by SRNL were in the range of 0.02-0.04.

Johnson, F.

2012-05-01T23:59:59.000Z

36

INITIAL SLUDGE BATCH 4 TANK 40 DECANT VARIABILITY STUDY WITH FRIT 510  

Science Conference Proceedings (OSTI)

Sludge Batch 4 (SB4) is currently being processed in the Defense Waste Processing Facility (DWPF) using Frit 510. The slurry pumps in Tank 40 are experiencing in-leakage of bearing water, which is causing the sludge slurry feed in Tank 40 to become dilute at a rapid rate. Currently, the DWPF is removing this dilution water by performing caustic boiling during the Sludge Receipt and Adjustment Tank (SRAT) cycle. In order to alleviate prolonged SRAT cycle times that may eventually impact canister production rates, decant scenarios of 100, 150, and 200 kilogallons of supernate were proposed for Tank 40 during the DWPF March outage. Based on the results of the preliminary assessment issued by the Savannah River National Laboratory (SRNL), the Liquid Waste Organization (LWO) issued a Technical Task Request (TTR) for SRNL to (1) perform a more detailed evaluation using updated SB4 compositional information and (2) assess the viability of Frit 510 and determine any potential impacts on the SB4 system. As defined in the TTR, LWO requested that SRNL validate the sludge--only SB4 flowsheet and the coupled operations flowsheet using the 100K gallon decant volume as well as the addition of 3 wt% sodium on a calcined oxide basis. Approximately 12 historical glasses were identified during a search of the ComProTM database that are located within at least one of the five glass regions defined by the proposed SB4 flowsheet options. While these glasses meet the requirements of a variability study there was some concern that the compositional coverage did not adequately bound all cases. Therefore, SRNL recommended that a supplemental experimental variability study be performed to support the various SB4 flowsheet options that may be implemented for future SB4 operations in DWPF. Eighteen glasses were selected based on nominal sludge projections representing the current as well as the proposed flowsheets over a WL interval of interest to DWPF (32-42%). The intent of the experimental portion of the variability study is to demonstrate that the glasses of the Frit 510-modified SB4 compositional region (Cases No.1-5) are both acceptable relative to the Environmental Assessment (EA) reference glass and predictable by the current DWPF process control models for durability. Frit 510 is a viable option for the processing of SB4 after a Tank 40 decant and the addition of products from the Actinide Removal Process (ARP). The addition of ARP did not have any negative impacts on the acceptability and predictability of the variability study glasses. The results of the variability study indicate that all of the study glasses (both quenched and centerline canister cooled (ccc)) have normalized releases for boron that are well below the reference EA glass (16.695 g/L). The durabilities of all of the study glasses are predictable using the current Product Composition Control System (PCCS) durability models with the exception of SB4VAR24ccc (Case No.2 at 41%). PCCS is not applicable to non-homogeneous glasses (i.e. glasses containing crystals such as acmite and nepheline), thus SB4VAR24ccc should not be predictable as it contains nepheline. The presence of nepheline has been confirmed in both SB4VAR13ccc and SB4VAR24ccc by X-ray diffraction (XRD). These two glasses are the first results which indicate that the current nepheline discriminator value of 0.62 is not conservative. The nepheline discriminator was implemented into PCCS for SB4 based on the fact that all of the historical glasses evaluated with nepheline values of 0.62 or greater did not contain nepheline via XRD analysis. Although these two glasses do cause some concern over the use of the 0.62 nepheline value for future DWPF glass systems, the impact to the current SB4 system is of little concern. More specifically, the formation of nepheline was observed in glasses targeting 41 or 42% WL. Current processing of the Frit 510-SB4 system in DWPF has nominally targeted 34% WL. For the SB4 variability study glasses targeting these lower WLs, nepheline formation was not observed and the minimal differe

Raszewski, F; Tommy Edwards, T; David Peeler, D; David Best, D; Irene Reamer, I; Phyllis Workman, P

2008-05-27T23:59:59.000Z

37

THE SLUDGE BATCH 7A GLASS VARIABILITY STUDY WITH FRIT 418 AND FRIT 702  

SciTech Connect

The Defense Waste Processing Facility (DWPF) is preparing to initiate processing of Sludge Batch 7a (SB7a) in May 2011. To support qualification of SB7a, the Savannah River National Laboratory (SRNL) was requested to execute a variability study (VS) to assess the applicability of the current Product Composition Control System (PCCS) durability models for the Frit 418-SB7a compositional region of interest. The objective of this study was to demonstrate applicability of the current durability models to the SB7a compositional region of interest and acceptability of the SB7a glasses with respect to the Environmental Assessment (EA) glass in terms of durability as defined by the Product Consistency Test (PCT). To support programmatic objectives, twenty-eight SB7a glasses were selected based on the nominal sludge projections used to support the frit recommendation. Twenty-three of the SB7a VS glasses were based on the use of Frit 418, while 5 glasses were based on the use of Frit 702. Frit 702 was also identified as a viable candidate for SB7a, especially if SO{sub 4} concentrations are found to be higher than anticipated. Frit 702 has shown a higher SO{sub 4} retention capability as compared to Frit 418. With respect to acceptability, the PCT results of the SB7a-VS glasses are acceptable relative to the EA glass regardless of thermal history (quenched or canister centerline cooled) or compositional view (target or measured). More specifically, all of the SB7a glasses have normalized boron release values (NL [B]) less than 0.9 g/L as compared to the benchmark NL [B] value for EA of 16.695 g/L. With respect to the applicability of the current durability models to the SB7a VS compositional region of interest, all of the study glasses (based on target compositions) lie within the 95% confidence intervals of the model predictions. When model applicability is based on the measured compositions, all of the SB7a VS glasses are predictable with the exception of SB7aVS-02 and SB7aVS-06. Although the NL [B] values of these two glasses range from 0.66 to 0.73 g/L (considered very acceptable), the PCT responses are not considered predictable by the current durability models. The current durability models are conservative for these glasses since they are more durable than predicted by the models. These two glasses are extreme vertices (EV) based compositions coupled with Frit 418 at 36% WL and target the maximum Na{sub 2}O content (15.01 wt% Na{sub 2}O) of the SB7a VS glasses. Higher alkali glasses for which the model overpredicts the PCT response have been observed previously in the Sludge Batch 3 (SB3) Phase 1 VS and the Sludge Batch 6 (SB6) VS.

Peeler, D.; Edwards, T.

2011-03-24T23:59:59.000Z

38

SLUDGE BATCH 5 ACCEPTANCE EVALUATION RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB5 QUALIFICATION SAMPLE PREPARED AT SRNL  

SciTech Connect

Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Five (SB5) for processing in the Defense Waste Processing Facility (DWPF). Part of this SB5 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40 to complete the formation of SB5. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB4. The radionuclide concentrations were measured or estimated in the Tank 51 SB5 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry taken on March 21, 2008. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under direction of the Liquid Waste Organization it was then modified by five washes, six decants, an addition of Pu/Be from Canyon Tank 16.4, and an addition of NaNO2. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Ta Determining the radionuclide concentrations in this Tank 51 SB5 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2008-0010. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task 2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task 5) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB5 will be taken and transferred to SRNL for measurement of these radionuclides. Data presented in this report represents the measured or estimated radionuclide concentrations obtained from several standard and special analytical methods performed by Analytical Development (AD) personnel within SRNL. The method for I-129 measurement in sludge is described in detail. Most of these methods were performed on solutions resulting from the dissolutions of the slurry samples. Concentrations are given for twenty-nine radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated. Results also indicate that 98% of the Tc-99 and 92% of the I-129 that could have been in this sludge batch have been removed by chemical processing steps in the SRS Canyons or Tank Farm.

Bannochie, C; Ned Bibler, N; David Diprete, D

2008-07-28T23:59:59.000Z

39

ELIMINATION OF THE CHARACTERIZATION OF DWPF POUR STREAM SAMPLE AND THE GLASS FABRICATION AND TESTING OF THE DWPF SLUDGE BATCH QUALIFICATION SAMPLE  

Science Conference Proceedings (OSTI)

A recommendation to eliminate all characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification sample was made by a Six-Sigma team chartered to eliminate non-value-added activities for the Defense Waste Processing Facility (DWPF) sludge batch qualification program and is documented in the report SS-PIP-2006-00030. That recommendation was supported through a technical data review by the Savannah River National Laboratory (SRNL) and is documented in the memorandums SRNL-PSE-2007-00079 and SRNL-PSE-2007-00080. At the time of writing those memorandums, the DWPF was processing sludge-only waste but, has since transitioned to a coupled operation (sludge and salt). The SRNL was recently tasked to perform a similar data review relevant to coupled operations and re-evaluate the previous recommendations. This report evaluates the validity of eliminating the characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification samples based on sludge-only and coupled operations. The pour stream sample has confirmed the DWPF's ability to produce an acceptable waste form from Slurry Mix Evaporator (SME) blending and product composition/durability predictions for the previous sixteen years but, ultimately the pour stream analysis has added minimal value to the DWPF's waste qualification strategy. Similarly, the information gained from the glass fabrication and PCT of the sludge batch qualification sample was determined to add minimal value to the waste qualification strategy since that sample is routinely not representative of the waste composition ultimately processed at the DWPF due to blending and salt processing considerations. Moreover, the qualification process has repeatedly confirmed minimal differences in glass behavior from actual radioactive waste to glasses fabricated from simulants or batch chemicals. In contrast, the variability study has significantly added value to the DWPF's qualification strategy. The variability study has evolved to become the primary aspect of the DWPF's compliance strategy as it has been shown to be versatile and capable of adapting to the DWPF's various and diverse waste streams and blending strategies. The variability study, which aims to ensure durability requirements and the PCT and chemical composition correlations are valid for the compositional region to be processed at the DWPF, must continue to be performed. Due to the importance of the variability study and its place in the DWPF's qualification strategy, it will also be discussed in this report. An analysis of historical data and Production Records indicated that the recommendation of the Six Sigma team to eliminate all characterization of pour stream glass samples and the glass fabrication and PCT performed with the qualification glass does not compromise the DWPF's current compliance plan. Furthermore, the DWPF should continue to produce an acceptable waste form following the remaining elements of the Glass Product Control Program; regardless of a sludge-only or coupled operations strategy. If the DWPF does decide to eliminate the characterization of pour stream samples, pour stream samples should continue to be collected for archival reasons, which would allow testing to be performed should any issues arise or new repository test methods be developed.

Amoroso, J.; Peeler, D.; Edwards, T.

2012-05-11T23:59:59.000Z

40

Organic and nitrogen removal from landfill leachate in aerobic granular sludge sequencing batch reactors  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer Aerobic granular sludge SBR was used to treat real landfill leachate. Black-Right-Pointing-Pointer COD removal was analyzed kinetically using a modified model. Black-Right-Pointing-Pointer Characteristics of nitrogen removal at different ammonium inputs were explored. Black-Right-Pointing-Pointer DO variations were consistent with the GSBR performances at low ammonium inputs. - Abstract: Granule sequencing batch reactors (GSBR) were established for landfill leachate treatment, and the COD removal was analyzed kinetically using a modified model. Results showed that COD removal rate decreased as influent ammonium concentration increasing. Characteristics of nitrogen removal at different influent ammonium levels were also studied. When the ammonium concentration in the landfill leachate was 366 mg L{sup -1}, the dominant nitrogen removal process in the GSBR was simultaneous nitrification and denitrification (SND). Under the ammonium concentration of 788 mg L{sup -1}, nitrite accumulation occurred and the accumulated nitrite was reduced to nitrogen gas by the shortcut denitrification process. When the influent ammonium increased to a higher level of 1105 mg L{sup -1}, accumulation of nitrite and nitrate lasted in the whole cycle, and the removal efficiencies of total nitrogen and ammonium decreased to only 35.0% and 39.3%, respectively. Results also showed that DO was a useful process controlling parameter for the organics and nitrogen removal at low ammonium input.

Wei Yanjie [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Key Laboratory of Environmental Protection in Water Transport Engineering Ministry of Communications, Tianjin Research Institute of Water Transport Engineering, Tianjin 300456 (China); Ji Min, E-mail: jmtju@yahoo.cn [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Li Ruying [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Qin Feifei [Tianjin Tanggu Sino French Water Supply Co. Ltd., Tianjin 300450 (China)

2012-03-15T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

SLUDGE BATCH 7 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB7 QUALIFICATION SAMPLE PREPARED AT SRNL  

SciTech Connect

Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Seven (SB7) for processing in the Defense Waste Processing Facility (DWPF). The SB7 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB6. The radionuclide concentrations were measured or estimated in the Tank 51 SB7 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter qualification sample of Tank 51 sludge slurry (HTF-51-10-125) received on September 18, 2010. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. With consultation from the Liquid Waste Organization, the qualification sample was then modified by several washes and decants, which included addition of Pu from H Canyon and sodium nitrite per the Tank Farm corrosion control program. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB7 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2010-0031. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task III.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB7 will be taken and transferred to SRNL for measurement of these radionuclides. The results presented in this report are those necessary for DWPF to assess if the Tank 51 SB7 sample prepared at SRNL meets the requirements for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria evaluation, and the DWPF Solid Waste Characterization Program. Concentrations are given for thirty-four radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated.

Pareizs, J.; Hay, M.

2011-02-22T23:59:59.000Z

42

DETERMINATION OF THE FRACTION OF GIBBSITE AND BOEHMITE FORMS OF ALUMINUM IN TANK 51H SLUDGE  

Science Conference Proceedings (OSTI)

The Savannah River National Laboratory (SRNL) was tasked with developing a test to determine the fraction of the gibbsite and boehmite forms of aluminum in the sludge solids. Knowledge of the fractions of gibbsite and boehmite in the sludge contained in various waste tanks would facilitate better sludge mass reduction estimates and allow better planning/scheduling for sludge batch preparation. The composite sludge sample prepared for use in the test from several small samples remaining from the original 3-L sample appears to be representative of the original sample based on the characterization data. A Gibbsite/Boehmite Test was developed that uses 8 M NaOH and a temperature of 65 C to dissolve aluminum. The soluble aluminum concentration data collected during the test indicates that, for the three standards containing gibbsite, all of the gibbsite dissolved in approximately 2 hours. Under the test conditions boehmite dissolved at more than an order of magnitude more slowly than gibbsite. An estimate based on the soluble aluminum concentration from the sludge sample at two hours into the test indicates the sludge solids contain a form of aluminum that dissolves at a rate similar to the 100% Boehmite standard. Combined with the XRD data from the original 3-L sample, these results provide substantial evidence that the boehmite form of aluminum predominates in the sludge. A calculation from the results of the Gibbsite/Boehmite test indicates the sludge contains {approx}3% gibbsite and {approx}97% boehmite. The sludge waste in Tank 51H was recently treated under Low Temperature Aluminum Dissolution (LTAD) conditions and a substantial fraction of aluminum (i.e., sludge mass) was removed, avoiding production of over 100 glass canisters in Defense Waste Processing Facility (DWPF). Results of the Gibbsite/Boehmite test indicate that the aluminum in this sludge was in the form of the more difficult to dissolve boehmite form of aluminum. Since boehmite may be the dominant form of aluminum in Savannah River Site (SRS) waste tank sludge, this result suggests that the conditions of the LTAD process can be used to dissolve both the gibbsite and boehmite forms of aluminum in tank sludge and costly tank infrastructure upgrades required for the higher temperature baseline process can be avoided. However, this conclusion should be confirmed by testing additional waste tank samples.

Hay, M; Kofi Adu-Wusu, K; Daniel McCabe, D

2008-08-31T23:59:59.000Z

43

FRIT DEVELOPMENT FOR HIGH LEVEL WASTE SLUDGE BATCH 5: COMPOSITIONAL TRENDS FOR VARYING ALUMINUM CONCENTRATIONS  

Science Conference Proceedings (OSTI)

The objective of this study was to experimentally measure the properties and performance of a series of glasses with compositions that could represent Sludge Batch 5 (SB5) as processed at the Defense Waste Processing Facility (DWPF). The data was used to provide recommendations to the Liquid Waste Organization (LWO) regarding blending and washing strategies in preparing SB5 based on acceptability of the glass compositions. These data were also used to guide frit optimization efforts as the SB5 composition was finalized. Glass compositions for this study were developed by combining a series of SB5 composition projections with a group of frits. Three composition projections for SB5 were developed using a model-based approach at Savannah River National Laboratory (SRNL). These compositions, referred to as SB5 Cases B, C and D, projected removal of 25, 50 and 75% (respectively) of the aluminum in Tank 51 through the low temperature aluminum dissolution process. The frits for this study (Frits 530 through 537) were selected based on their predicted operating windows (i.e., ranges of waste loadings over which the predicted properties of the glasses were acceptable) and their potential (based on historical trends) to provide acceptable melt rates for SB5. Six additional glasses were designed to evaluate alternatives for uranium in DWPF-type glasses used for variability studies and some scoping studies. Since special measures are necessary when working with uranium-containing glasses in the laboratory, it is desirable as a cost and time saving measure to find an alternative for uranium to support frit optimization efforts. Hafnium and neodymium were investigated as potential surrogates for uranium, and other glasses were made by simply excluding the radioactive components and renormalizing the glass composition. The study glasses were fabricated and characterized at SRNL. Chemical composition analyses suggested only minor difficulties in meeting the targeted compositions for some of the oxides for some of the glasses. Although minor differences were observed, they did not have a significant impact on the conclusions made in this study. Several of the study compositions showed retention of more than 0.5 wt% SO{sub 4}{sup 2-} in glass. Trevorite (a spinel) was the only crystalline phase that was positively identified in a few of the study glasses after the canister centerline cooled (CCC) heat treatment. Spinels are not of concern as they have been shown to have little impact on the durability of high level waste glasses. The crystallization behavior of the surrogate glasses was generally the same as that of their U{sub 3}O{sub 8}-containing counterparts. There are two pairs that were exceptions: SB5-04 (amorphous) and SB5-24 (possible trevorite), along with SB5-07 (amorphous) and SB5-25 (trevorite). In these cases, the surrogate glasses (SB5-24 and SB5-25) appear to be more conservative (more prone to crystallization) than their U{sub 3}O{sub 8}-containing counterparts. Chemical durability was quantified using the Product Consistency Test (PCT). The normalized leachate (NL) values for B, Li, Na and Si for all of the study glasses were well below those of the Environmental Assessment (EA) benchmark glass, regardless of heat treatment or compositional view. This indicates that all of the glasses had very acceptable durability performance. The highest NL [B] for the study glasses was 0.914 g/L (the quenched version of glass SB5-13), normalized using the measured, bias-correct composition. There was little practical impact of the CCC heat treatment on the PCT responses of the study glasses. The measured PCT responses were predictable by the current {Delta}G{sub p} models. In general, the PCT responses for the surrogate glasses or the glasses without U{sub 3}O{sub 8} were quite similar to their U{sub 3}O{sub 8}-containing counterparts. The average percent error in NL [B] normalized by the measured, bias-corrected compositions for the surrogate glasses compared with their radioactive counterparts was 8.8%. The largest difference in NL

Fox, K; Tommy Edwards; David Best; Irene Reamer; Phyllis Workman

2008-08-28T23:59:59.000Z

44

ANALYTICAL PLANS SUPPORTING THE SLUDGE BATCH 8 GLASS VARIABILITY STUDY BEING CONDUCTED BY ENERGYSOLUTIONS AND CUA'S VITREOUS STATE LABORATORY  

SciTech Connect

EnergySolutions (ES) and its partner, the Vitreous State Laboratory (VSL) of The Catholic University of America (CUA), are to provide engineering and technical services support to Savannah River Remediation, LLC (SRR) for ongoing operation of the Defense Waste Processing Facility (DWPF) flowsheet as well as for modifications to improve overall plant performance. SRR has requested via a statement of work that ES/VSL conduct a glass variability study (VS) for Sludge Batch 8. SRR issued a technical task request (TTR) asking that the Savannah River National Laboratory (SRNL) provide planning and data reduction support for the ES/VSL effort. This document provides two analytical plans for use by ES/VSL: one plan is to guide the measurement of the chemical composition of the study glasses while the second is to guide the measurement of the durability of the study glasses. The measurements generated by ES/VSL are to be provided to SRNL for data reduction and evaluation. SRNL is to review the results of its evaluation with ES/VSL and SRR. The results will subsequently be incorporated into a joint report with ES/VSL as a deliverable to SRR to support the processing of SB8 at DWPF.

Edwards, T.; Peeler, D.

2012-11-26T23:59:59.000Z

45

Analytical Plans Supporting The Sludge Batch 8 Glass Variability Study Being Conducted By Energysolutions And Cua's Vitreous State Laboratory  

Science Conference Proceedings (OSTI)

EnergySolutions (ES) and its partner, the Vitreous State Laboratory (VSL) of The Catholic University of America (CUA), are to provide engineering and technical services support to Savannah River Remediation, LLC (SRR) for ongoing operation of the Defense Waste Processing Facility (DWPF) flowsheet as well as for modifications to improve overall plant performance. SRR has requested via a statement of work that ES/VSL conduct a glass variability study (VS) for Sludge Batch 8. SRR issued a technical task request (TTR) asking that the Savannah River National Laboratory (SRNL) provide planning and data reduction support for the ES/VSL effort. This document provides two analytical plans for use by ES/VSL: one plan is to guide the measurement of the chemical composition of the study glasses while the second is to guide the measurement of the durability of the study glasses. The measurements generated by ES/VSL are to be provided to SRNL for data reduction and evaluation. SRNL is to review the results of its evaluation with ES/VSL and SRR. The results will subsequently be incorporated into a joint report with ES/VSL as a deliverable to SRR to support the processing of SB8 at DWPF.

Edwards, T. B.; Peeler, D. K.

2012-11-26T23:59:59.000Z

46

Utilisation of single added fatty acids by consortia of digester sludge in batch culture  

SciTech Connect

Inocula derived from an anaerobic digester were used to study (i) their potential for methane production and (ii) the utilisation rates of different short chain fatty acids (SCFAs) by the microbial community in defined media with mono-carbon sources (formic-, acetetic-, propionic-, butyric acid) in batch culture. It could be demonstrated that the microbial reactor population could be transferred successfully to the lab, and its ability to build up methane was present even with deteriorating biogas plant performance. Therefore, this reduction in performance of the biogas plant was not due to a decrease in abundance, but due to an inactivity of the microbial community. Generally, the physico-chemical properties of the biogas plant seemed to favour hydrogenotrophic methanogens, as seen by the high metabolisation rates of formate compared with all other carbon sources. In contrast, acetoclastic methanogenesis could be shown to play a minor role in the methane production of the investigated biogas plant, although the origin of up to 66% of methane is generally suggested to be generated through acetoclastic pathway.

Wagner, Andreas Otto, E-mail: Andreas.Wagner@uibk.ac.a [University of Innsbruck, Institute of Microbiology, Technikerstr. 25, A-6020 Innsbruck (Austria); Gstrauntaler, Gudrun [Abfallbeseitigungsverband Westtirol, Breite Mure, A-6426 Roppen (Austria); Illmer, Paul [University of Innsbruck, Institute of Microbiology, Technikerstr. 25, A-6020 Innsbruck (Austria)

2010-10-15T23:59:59.000Z

47

Analyses by the Defense Waste Processing Facility Laboratory of Thorium Glasses from the Sludge Batch 6 Variability Study  

Science Conference Proceedings (OSTI)

The Savannah River Remediation (SRR) Defense Waste Processing Facility (DWPF) is currently processing Sludge Batch 6 (SB6) with Frit 418. At times during the processing of this glass system, thorium is expected to be at concentrations in the final wasteform that make it a reportable element for the first time since startup of radioactive operations at the DWPF. The Savannah River National Laboratory (SRNL) supported the qualification of the processing of this glass system at the DWPF. A recommendation from the SRNL studies was the need for the DWPF Laboratory to establish a method to measure thorium by Inductively Coupled Plasma - Atomic Emission Spectroscopy (ICPAES). This recommendation led to the set of thorium-bearing glasses from the SB6 Variability Study (VS) being submitted to the DWPF Laboratory for chemical composition measurement. The measurements were conducted by the DWPF Laboratory using the sodium peroxide fusion preparation method routinely employed for analysis of samples from the Slurry Mix Evaporator (SME). These measurements are presented and reviewed in this report. The review indicates that the measurements provided by the DWPF Laboratory are comparable to those provided by Analytical Development's laboratory at SRNL for these same glasses. As a result, the authors of this report recommend that the DWPF Laboratory begin using its routine peroxide fusion dissolution method for the measurement of thorium in SME samples of SB6. The purpose of this technical report is to present the measurements generated by the DWPF Laboratory for the SB6 VS glasses and to compare the measurements to the targeted compositions for these VS glasses as well as to SRNL's measurements (both sets, targeted and measured, of compositional values were reported by SRNL in [2]). The goal of these comparisons is to provide information that will lead to the qualification of peroxide fusion dissolution as a method for the measurement by the DWPF Laboratory of thorium in SME glass samples.

Edwards, T.; Click, D.; Feller, M.

2011-02-28T23:59:59.000Z

48

Sludge Mass Reduction Update  

NLE Websites -- All DOE Office Websites (Extended Search)

Preparations Preparations within the Tank Farm D. Bumgardner Liquid Waste Engineering Washington Savannah River Company 12 May 2009 2 Agenda Liquid Waste System Overview Sludge Characteristics Sludge Batch Planning Sludge Batch Preparation Sequence - Aluminum Dissolution - Sludge Washing - Sludge Batch Qualification/Acceptance Questions 3 Liquid Waste Processing at SRS ARP - Actinide Removal Process AFP - Actinide Finishing Process ASP - Actinide Strike Process CSS - Clarified Salt Solution CSSX - Caustic-side Solvent Extraction DDA - Deliquification, Dissolution, and Adjustment DSS - Decontaminated Salt Solution DWPF - Defense Waste Processing Facility ETP - Effluent Treatment Project GWSB - Glass Waste Storage Building HLW - High-Level Waste LLW - Low-Level Waste MCU - Modular CSSX Unit

49

Microsoft Word - Sludge Test Area CX Determination Form12172012  

NLE Websites -- All DOE Office Websites (Extended Search)

Sludge Test Facility at the Transuranic (TRU) Waste Processing Center (TWPC) [CX-TWPC-13-0001] Sludge Test Facility at the Transuranic (TRU) Waste Processing Center (TWPC) [CX-TWPC-13-0001] Program or Field Office: Environmental Management - Oak Ridge Location(s) (City/County/State): Oak Ridge, Tennessee Proposed Action Description: The proposed action is to construct and operate a sludge test facility at the Transuranic (TRU) Waste Processing Center (TWPC) to conduct testing activities for sludge mobilization, mixing, and removal from the Melton Valley Storage Tanks (MVST). The testing is needed to develop appropriate, compliant treatment to a final waste form that will meet the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC). This testing is needed for the mobilization, removal, and treatment of the sludge regardless of

50

The determination of PCBs in Rocky Flats Type IV waste sludge by gas chromatography/electron capture detection. Part 2  

SciTech Connect

Before disposal, radioactive sludge (Type IV) from Rocky Flats Plant (RFP) must be evaluated for polychlorinated biphenyl (PCB) content. The Type IV sludge consists of organic solvents, degreasers, cutting oils, and transuranic (TRU) waste mixed with calcium silicate (MicroCel E{reg_sign} and Oil Dri{reg_sign} to form a grease or paste-like material. For laboratory testing, a nonradioactive simulated Type 17V RFP sludge was prepared at Argonne National Laboratory-East (ANL-E). This sludge has a composition similar to that expected from field samples. In an earlier effort, a simplified method was developed for extraction, cleanup of extract, and determination of PCBs in samples of simulated sludge spiked with Aroclors 1254 and 1260. The simplified method has now been used to determine the presence and quantities of other Aroclors in the simulated sludge, namely, Aroclors 10 1 6, 1221, 1232, 1242, and 1248. The accuracy and precision of the data for these Aroclors were found to be similar to the data for sludges spiked with Aroclors 1254 and 1260. Since actual sludges may vary in composition, the method was also verified by analyzing another source of Type IV simulated sludge, prepared by Argonne National Laboratory-West (ANL-W).

Parish, K.J.; Applegate, D.V.; Postlethwait, P.D.; Boparai, A.S.; Reedy, G.T.

1994-12-01T23:59:59.000Z

51

Hazardous Waste Code Determination for First/Second-Stage Sludge Waste Stream (IDCs 001, 002, 800)  

Science Conference Proceedings (OSTI)

This document, Hazardous Waste Code Determination for the First/Second-Stage Sludge Waste Stream, summarizes the efforts performed at the Idaho National Engineering and Environmental Laboratory (INEEL) to make a hazardous waste code determination on Item Description Codes (IDCs) 001, 002, and 800 drums. This characterization effort included a thorough review of acceptable knowledge (AK), physical characterization, waste form sampling, chemical analyses, and headspace gas data. This effort included an assessment of pre-Waste Analysis Plan (WAP) solidified sampling and analysis data (referred to as preliminary data). Seventy-five First/Second-Stage Sludge Drums, provided in Table 1-1, have been subjected to core sampling and analysis using the requirements defined in the Quality Assurance Program Plan (QAPP). Based on WAP defined statistical reduction, of preliminary data, a sample size of five was calculated. That is, five additional drums should be core sampled and analyzed. A total of seven drums were sampled, analyzed, and validated in compliance with the WAP criteria. The pre-WAP data (taken under the QAPP) correlated very well with the WAP compliant drum data. As a result, no additional sampling is required. Based upon the information summarized in this document, an accurate hazardous waste determination has been made for the First/Second-Stage Sludge Waste Stream.

Arbon, R.E.

2001-01-31T23:59:59.000Z

52

Sludge Mass Reduction Update  

NLE Websites -- All DOE Office Websites (Extended Search)

Farm Mixing and Sampling to Support DWPF Operations Farm Mixing and Sampling to Support DWPF Operations David Larsen, PMP, PSP Hasmukh Shah Liquid Waste Engineering Washington Savannah River Company May 21, 2009 2 LWO-LWP-2009-00021 Overview Background Mixing - Historical - Criteria - Current Strategy Sampling Techniques and Procedure Defense Waste Processing Facility (DWPF) Requirements - Waste Acceptance Criteria - Tank Farm Compliance 3 LWO-LWP-2009-00021 Sludge Batch Preparation and Feed Tank 51 (Batch Tank) Sludge from one or more waste storage tanks *Mixing by Pumps *Wash *Settle *Decant *Sample Qualified Batch Transferred Forward *Mixing by Pumps *Sample Bulk Waste Removal Tank(s) Tank 40 (Blend Tank) *10,000 gal vessel *Mixing by Agitator *Sample *10,000 gal vessel *Mixing by Agitator *Sample *Wetting *Mixing by Pumps

53

WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS USING POST ALUMINUM DISSOLUTION TANK 51 SLUDGE SLURRY  

Science Conference Proceedings (OSTI)

The remaining contents of Tank 51 from Sludge Batch 4 will be blended with Purex sludge from Tank 7 to constitute Sludge Batch 5 (SB5). The Savannah River Site (SRS) Liquid Waste Organization (LWO) has completed caustic addition to Tank 51 to perform low temperature Al dissolution on the H-Modified (HM) sludge material to reduce the total mass of sludge solids and Al being fed to the Defense Waste Processing Facility (DWPF). The Savannah River National Lab (SRNL) has also completed aluminum dissolution tests using a 3-L sample of Tank 51 sludge slurry through funding by DOE EM-21. This report documents assessment of downstream impacts of the aluminum dissolved sludge, which were investigated so technical issues could be identified before the start of SB5 processing. This assessment included washing the aluminum dissolved sludge to a Tank Farm projected sodium concentration and weight percent insoluble solids content and DWPF Chemical Process Cell (CPC) processing using the washed sludge. Based on the limited testing, the impact of aluminum dissolution on sludge settling is not clear. Settling was not predictable for the 3-L sample. Compared to the post aluminum dissolution sample, settling after the first wash was slower, but settling after the second wash was faster. For example, post aluminum dissolution sludge took six days to settle to 60% of the original sludge slurry height, while Wash 1 took nearly eight days, and Wash 2 only took two days. Aluminum dissolution did impact sludge rheology. A comparison between the as-received, post aluminum dissolution and washed samples indicate that the downstream materials were more viscous and the concentration of insoluble solids less than that of the starting material. This increase in viscosity may impact Tank 51 transfers to Tank 40. The impact of aluminum dissolution on DWPF CPC processing cannot be determined because acid addition for the Sludge Receipt and Adjustment Tank (SRAT) cycle was under-calculated and thus under-added. Although the sludge was rheologically thick throughout the SRAT and Slurry Mix Evaporator (SME) cycles, this may have been due to the under addition of acid. Aluminum dissolution did, however, impact analyses of the SRAT receipt material. Two methods for determining total base yielded significantly different results. The high hydroxide content and the relatively high soluble aluminum content of the washed post aluminum dissolution sludge likely contributed to this difference and the ultimate under addition of acid. It should be noted that the simulant used to provide input for the SRAT cycle was an inadequate representation of the waste in terms of acid demand, likely due to the differences in the form of aluminum and hydroxide in the simulant and actual waste. Based on the results of this task, it is recommended that: (1) Sludge settling and rheology during washing of the forthcoming Sludge Batch 5 qualification sample be monitored closely and communicated to the Tank Farm. (2) SRNL receive a sample of Tank 51 after all chemical additions have been made and prior to the final Sludge Batch 5 decant for rheological assessment. Rheology versus wt% insoluble solids will be performed to determine the maximum amount of decant prior to the Tank 51 to Tank 40 transfer. (3) As a result of the problem with measuring total base and subsequently under-calculating acid for the DWPF CPC processing of the post aluminum dissolution sludge; (4) Studies to develop understanding of how the sludge titrates (i.e., why different titration methods yield different results) should be performed. (5) Simulants that better match the properties of post aluminum dissolution sludge should be developed. (6) Work on developing an acid calculation less dependant on the total base measurement should be continued.

Pareizs, J; Cj Bannochie, C; Damon Click, D; Erich Hansen, E; Dan Lambert, D; Michael Stone, M

2008-04-28T23:59:59.000Z

54

Hazardous Waste Code Determinations for the First/Second Stage Sludge Waste Stream (IDCs 001, 002, 800)  

Science Conference Proceedings (OSTI)

This document, Hazardous Waste Code Determination for the First/Second-Stage Sludge Waste Stream, summarizes the efforts performed at the Idaho National Engineering and Environmental Laboratory (INEEL) to make a hazardous waste code determination on Item Description Codes (IDCs) 001, 002, and 800 drums. This characterization effort included a thorough review of acceptable knowledge (AK), physical characterization, waste form sampling, chemical analyses, and headspace gas data. This effort included an assessment of pre-Waste Analysis Plan (WAP) solidified sampling and analysis data (referred to as preliminary data). Seventy-five First/Second-Stage Sludge Drums, provided in Table 1-1, have been subjected to core sampling and analysis using the requirements defined in the Quality Assurance Program Plan (QAPP). Based on WAP defined statistical reduction, of preliminary data, a sample size of five was calculated. That is, five additional drums should be core sampled and analyzed. A total of seven drums were sampled, analyzed, and validated in compliance with the WAP criteria. The pre-WAP data (taken under the QAPP) correlated very well with the WAP compliant drum data. As a result, no additional sampling is required. Based upon the information summarized in this document, an accurate hazardous waste determination has been made for the First/Second-Stage Sludge Waste Stream.

Arbon, Rodney Edward

2001-01-01T23:59:59.000Z

55

Measuring and Predicting Fission Product Noble Metals in SRS HLW Sludges  

DOE Green Energy (OSTI)

The noble metals Ru, Rh, Pd, and Ag were produced in the Savannah River Site (SRS) reactors as products of the fission of U-235. Consequently they are in the High Level Waste (HLW) sludges that are currently being immobilized into a borosilicate glass in the Defense Waste Processing Facility (DWPF). The noble metals are a concern in the DWPF because they catalyze the decomposition of formic acid used in the process to produce the flammable gas hydrogen. As the concentration of these noble metals in the sludge increases, more hydrogen will be produced when this sludge is processed. In the SRS Tank Farm it takes approximately two years to prepare a sludge batch for processing in the DWPF. This length of time is necessary to mix the appropriate sludges, blend them to form a sludge batch and then wash it to enable processing in the DWPF. This means that the exact composition of a sludge batch is not known for {approx}two years. During this time, studies with simulated nonradioactive sludges must be performed to determine the desired DWPF processing parameters for the new sludge batch. Consequently, prediction of the noble metal concentrations is desirable to prepare appropriate simulated sludges for studies of the DWPF process for that sludge batch. These studies give a measure of the amount of hydrogen that will be produced when that sludge batch is processed. This report describes in detail the measurement of these noble metal concentrations in sludges and a way to predict their concentrations from an estimate of the lanthanum concentration in the sludge. Results for two sludges are presented in this report. These are Sludge Batch 3 (SB3) currently being processed by the DWPF and a sample of unwashed sludge from Tank 11 that will be part of Sludge Batch 4. The concentrations of the noble metals in HLW sludges are measured by using mass spectroscopy to determine concentrations of the isotopes that comprise each noble metal. For example, the noble metal Ru is comprised of isotopes with masses 101, 102, and 104. The element Rh has a single isotope with mass 103. The element Pd is comprised of five isotopes. These are at masses 105-108 and mass 110. As does Rh, Ag has only one isotope. This is at mass 109. However, results in this report show that the Ag concentration in the two samples was due to natural Ag being in the samples. Natural Ag has masses at 107 and 109. The Ag-107 interferes with the measurement of Pd-107. This Ag was used in one of the processes at SRS. The results also show that natural Cd is in the two samples. Cadmium has isotopes at masses 106, 108 and 110, thus it interferes with the analysis of the Pd isotopes at these masses. Cadmium was also used in one of the processes at SRS. However, the concentrations of the Pd isotopes at masses 106, 107, 108 and 110 could be calculated using the fission yields for the Pd isotopes, and the measured concentration of Pd at mass 105 where there is no Ag or Cd interference. Based on the measurements of the concentrations of the isotopes of each noble metal, the total concentration of that noble metal can be determined by summing the concentrations of the individual isotopes. The results in this report show that the relative concentrations of the isotopes of Ru and Rh are in proportion to their yields from the fission of U-235 in the reactors. These results were expected since these elements are very insoluble in caustic and thus are primarily in the sludge tanks rather then the salt tanks of the SRS Tank Farm. The relative concentration of Pd is somewhat lower than that based on the relative fission yields of its five isotopes. This indicates that some of the Pd is in the salt tanks rather than the sludge tanks of the Tank Farm. The concentrations of the noble metals were predicted using the High Level Waste Characterization System (WCS) at SRS. This system keeps record of the inventory of the major compounds and select radionuclides that are in each of the SRS HLW tanks. Using this system, the Closure Business Unit (CBU) can predict the major composition of a sludge ba

Bibler, N

2005-04-05T23:59:59.000Z

56

Example Hopper Batch Scripts  

NLE Websites -- All DOE Office Websites (Extended Search)

Example Batch Scripts Example Batch Scripts Sample Batch Scripts One of the most noted differences between the Hopper system and other NERSC systems is the number of cores per node...

57

Edison Batch Jobs  

NLE Websites -- All DOE Office Websites (Extended Search)

the control of a "batch script," which is a text file containing a number of job directives and LINUX commands or utilities. Batch scripts are submitted to the "batch system,"...

58

Edison Batch Jobs  

NLE Websites -- All DOE Office Websites (Extended Search)

Batch Jobs Batch Jobs Batch Jobs Overview Batch jobs are jobs that run non-interactively under the control of a "batch script," which is a text file containing a number of job directives and LINUX commands or utilities. Batch scripts are submitted to the "batch system," where they are queued awaiting free resources on Edison. The batch system on Edison is known as "Torque." Bare-Bones Batch Script The simplest Edison batch script will look something like this. #PBS -q regular #PBS -l mppwidth=48 #PBS -l walltime=00:10:00 cd $PBS_O_WORKDIR aprun -n 48 ./my_executable This example illustrates the basic parts of a script: Job directive lines begin with #PBS. These "Torque Directives" tell the batch system how many nodes to reserve for your job and how long to

59

Hopper Batch Jobs  

NLE Websites -- All DOE Office Websites (Extended Search)

Batch Jobs Batch Jobs Batch Jobs Overview Batch jobs are jobs that run non-interactively under the control of a "batch script," which is a text file containing a number of job directives and LINUX commands or utilities. Batch scripts are submitted to the "batch system," where they are queued awaiting free resources on Hopper. The batch system on Hopper is known as "Torque." Bare-Bones Batch Script The simplest Hopper batch script will look something like this. #PBS -q regular #PBS -l mppwidth=48 #PBS -l walltime=00:10:00 cd $PBS_O_WORKDIR aprun -n 48 ./my_executable This example illustrates the basic parts of a script: Job directive lines begin with #PBS. These "Torque Directives" tell the batch system how many nodes to reserve for your job and how long to

60

Edison Batch Jobs  

NLE Websites -- All DOE Office Websites (Extended Search)

Batch Jobs Batch Jobs Batch Jobs Overview Batch jobs are jobs that run non-interactively under the control of a "batch script," which is a text file containing a number of job directives and LINUX commands or utilities. Batch scripts are submitted to the "batch system," where they are queued awaiting free resources on Edison. The batch system on Edison is known as "Torque." Bare-Bones Batch Script The simplest Edison batch script will look something like this. #PBS -q regular #PBS -l mppwidth=32 #PBS -l walltime=00:10:00 cd $PBS_O_WORKDIR aprun -n 32 ./my_executable This example illustrates the basic parts of a script: Job directive lines begin with #PBS. These "Torque Directives" tell the batch system how many nodes to reserve for your job and how long to

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Safety-Basis Thermal Analysis for KE Basin Sludge Transport and Storage  

DOE Green Energy (OSTI)

A series of safety-basis thermal and gas generation analyses were completed and independently reviewed to assess the thermal performance of a large diameter container (LDC) containing KE Basin sludge. The results demonstrate: (1) the sludge transport system (STS) containing a LDC can safely transport a KE basin sludge payload up to 2.0 m{sup 3} and, (2) large diameter containers with sludge payloads up to 2.0 m{sup 3} can be safely stored in a process cell at T Plant. The transport and storage analyses are based on a conservative set of assumptions, including limiting environmental conditions. Conclusions drawn from the transport and storage results were not impacted by changes in the radial gap between the cask and LDC, purge gas (i.e., either helium or nitrogen), sludge porosity, or thermal conductivity. The design of the transport cask and large diameter container can accommodate reasonable changes in these values. Both transport from KE Basin and long-term storage at T Plant are addressed for sludge payloads up to 2.0 m{sup 3}. Additional analyses determined the expected range of T Plant environmental temperatures, the hydrogen and oxygen generation rate due to the radiolysis of water, and the maximum hydrogen concentration within a process cell due to chemical reactions and the radiolysis of water. All sludge temperature and hydrogen concentration criteria for transport and storage are met. The analyses assumed a safety-basis sludge mixture defined as 60% by volume floor and 40% by volume canister sludge with 35% retained gas, and a conservative segregated (axial) distribution of metallic uranium (resulting from particulate settling) with associated safety-basis properties. The analyses recognized that the retrieval process would produce non-uniform sludge distributions. Four batch process loadings of 0.5m{sup 3} each are assumed. Each process batch loading will settle and segregate (separate) into two layers: an active layer containing all the metallic uranium which is chemically active, and a non-active layer containing uranium oxide, non-uranium material, and no metallic uranium. This is a conservative representation of operational controls designed to limit the metallic uranium concentration. The sludge layers are assumed to remain intact during transport and storage.

HEARD, F.J.; SATHYANARAYANA, J.J.

2002-09-30T23:59:59.000Z

62

Example Edison Batch Scripts  

NLE Websites -- All DOE Office Websites (Extended Search)

Example Batch Scripts Example Batch Scripts The default number of cores per node on Edison is 16, and the default "mppnppn" setting is 16. However, if you run with hyperthreading...

63

Adding coal dust to coal batch  

Science Conference Proceedings (OSTI)

The granulometric composition of coke dust from the dry-slaking machine is determined. The influence of additions of 3-7% coke dust on the quality of industrial coking batch and the coke obtained by box coking is estimated. Adding 1% coke dust to coking batch does not markedly change the coke quality. Industrial equipment for the supply of dry-slaking dust to the batch is described.

V.S. Shved; A.V.Berezin [OAO Koks, Kemerovo (Russian Federation)

2009-05-15T23:59:59.000Z

64

Confirmation Run of the DWPF SRAT Cycle Using the Sludge-Only Flowsheet with Tank 40 Radioactive Sludge and Frit 200 in the Shielded Cells Facility  

SciTech Connect

Several basic data reports have been issued concerning the recent demonstration of the Defense Waste Processing Facility (DWPF) Sludge Receipt and Adjustment Tank (SRAT) Cycle and Slurry Mix Evaporator (SME) Cycle, conducted at the Savannah River Technology Center (SRTC). The SRTC demonstration was completed using the DWPF ''Sludge-Only'' flowsheet with washed Tank 40 sludge slurry (Sludge Batch 2 or Macrobatch 3) in the Shielded Cells facility. The DWPF ''Sludge-Only'' flowsheet calls for processing radioactive sludge slurry using nitric acid, concentrated formic acid, and frit 200.

Fellinger, T.L.

2002-08-29T23:59:59.000Z

65

PDSF Interactive Batch Jobs  

NLE Websites -- All DOE Office Websites (Extended Search)

Interactive Batch Jobs Interactive Batch Jobs Running Interactive Batch Jobs You cannot login to the PDSF batch nodes directly but you can run an interactive session on a batch node using either qlogin or qsh. This can be useful if you are doing something that is potentially disruptive or if the interactive nodes are overloaded. qlogin will give you an interactive session in the same window as your original session on PDSF, however, you must have your ssh keys in place. Due to system limitations there is a small (but important) difference in the user environment you get when you use qlogin. When you receive a shell prompt with qlogin, your CHOS environment is not set up for you. In order to set up the CHOS environment of your choice you will need to manually chos into the chos environment of your choice:

66

Microsoft PowerPoint - S08-02_Rios-Armstrong_SRS Experience Preparing Salt Batches.ppt  

NLE Websites -- All DOE Office Websites (Extended Search)

Savannah River Site (SRS) Experience Savannah River Site (SRS) Experience with Preparing Salt Batches Presentation to: EM Waste Processing Technical Exchange Date: November 17 th , 2010 Author: Maria A. Rios-Armstrong Position: Small Column Ion Exchange (SCIX) Process Engineering Lead Savannah River Remediation SRR-SPT-2010-00222 Print Close 2 Agenda * SRS Composite Inventory * Salt Processing * SRS Liquid Waste System * Background * Interim Salt Disposition Project (ISDP) Salt Batches - ISDP Salt Batch 1 - ISDP Salt Batch 2 - ISDP Salt Batch 3 - ISDP Salt Batch 4 * Future Salt Batches * Summary * Questions Print Close 3 SRS Composite Inventory Saltcake Sludge Volume 37.1 Million Gallons (Mgal) Curies 183 MCi (52%) 169 MCi (48%) 352 Million Curies (MCi) 171 MCi (49%) Sludge 34.2 Mgal (92%) 2.9 Mgal (8%) 18.4 Mgal (49%) Inventory values as of 2010-06-30

67

PDSF Batch Job Example  

NLE Websites -- All DOE Office Websites (Extended Search)

PDSF Batch Job Example PDSF Batch Job Example PDSF Batch Job Example On this page we show an example of how to run a simple batch job, monitor it, check its output, and look at the SGE accounting information about it. We start with a simple script named hello.csh, which just sleeps a bit and then writes some output: pdsf4 72% cat hello.csh #!/bin/csh sleep 600 echo "Hello, World" The simplest way to submit it is to just use qsub without any options: pdsf4 74% qsub hello.csh Your job 1787239 ("hello.csh") has been submitted We can check on its status with qstat. Use the -u option to get only your jobs: pdsf4 75% qstat -u hjort job-ID prior name user state submit/start at queue slots ja-task-ID -----------------------------------------------------------------------------------------------------------------

68

Batch Script Examples  

NLE Websites -- All DOE Office Websites (Extended Search)

Batch Script Examples Batch Script Examples Batch Script Examples My First Script This is a simple example that you can use to make sure that your settings are correct before submitting more complicated jobs. First, copy the contents of hello.sh into a file. genepool% cat hello.sh #!/bin/bash sleep 120 echo "Hello World" Then submit your job with the qsub command genepool% qsub hello.sh Monitor your job with the qstat command: genepool% qstat -u You can also get more detailed information about your job using: genepool% qstat -j The job id can be found using the qstat -u command. Basic Batch Script Here is an example of a basic script that specifies the working directory, the shell and the queue. The #$ must be used to specify the grid engine

69

Example Edison Batch Scripts  

NLE Websites -- All DOE Office Websites (Extended Search)

Example Batch Scripts Example Batch Scripts Example Batch Scripts The default number of cores per node on Edison is 16, and the default "mppnppn" setting is 16. However, if you run with hyperthreading (HT), Edison compute nodes have 32 cores per node, and the mppnppn value needs to be set to 32. In addition, the "-j 2" option needs to be added to the "aprun" command. In most of the following example batch scripts, the default number of 16 cores per node is used. Basic Scripts Sample Job script This script uses the default 16 cores per node. This job will run on 64 nodes, with 1024 cores. #PBS -q debug #PBS -l mppwidth=1024 #PBS -l walltime=00:10:00 #PBS -N my_job #PBS -j oe #PBS -V cd $PBS_O_WORKDIR aprun -n 1024 ./my_executable Sample job script to run with Hyperthreading (HT)

70

Example Edison Batch Scripts  

NLE Websites -- All DOE Office Websites (Extended Search)

Example Batch Scripts Example Batch Scripts Example Batch Scripts Edison has 24 cores (physical cores) per node, so the default "mppnppn" value is set to 24 for all queues. If you run with hyperthreading (HT), Edison has 48 logical cores per node, and the mppnppn value can be set to 48. However, this is not required. The "-j 2" option of the "aprun" command allows you to use all 48 logical cores on the nodes. In most of the following example batch scripts, we assume that jobs are run without Hyperthreading unless explicitly mentioned, therefore the default mppnppn value, 24, is used. Basic Scripts Sample Job script This script uses the default 24 cores per node. This job will run on 64 nodes, with 1536 cores. #PBS -q debug #PBS -l mppwidth=1536 #PBS -l walltime=00:10:00

71

Submitting Batch Jobs on Carver  

NLE Websites -- All DOE Office Websites (Extended Search)

Submitting Batch Jobs Submitting Batch Jobs Submitting Batch Jobs Overview A batch job is the most common way users run production applications on NERSC machines. Carver's batch system is based on the PBS model, implemented with the Moab scheduler and Torque resource manager. Typically, the user submits a batch script to the batch system. This script specifies, at the very least, how many nodes and cores the job will use, how long the job will run, and the name of the application to run. The job will advance in the queue until it has reached the top. At this point, Torque will allocate the requested number of nodes to the batch job. The batch script itself will execute on the "head node" (sometimes known as the "MOM" node). See Queues and Policies for details of batch queues, limits,

72

Parallel Batch Scripts  

NLE Websites -- All DOE Office Websites (Extended Search)

Parallel Batch Scripts Parallel Batch Scripts Parallel Batch Scripts Parallel Environments on Genepool You can run parallel jobs that use MPI or OpenMP on Genepool as long as you make the appropriate changes to your submission script! To investigate the parallel environments that are available on Genepool, you can use Command Description qconf -sp Show the configuration for the specified parallel environment. qconf -spl Show a list of all currently configured parallel environments. Basic Parallel Example If your job requires the default 5GB of memory per slot, you can do the following: #!/bin/bash # # == Set SGE options: # # -- ensure BASH is used # -- run the job in the current working directory (where qsub is called) #$ -cwd # -- run with the environment variables from the User's environment

73

Determining Thermal Conductivity of Simulated Feed for High Level ...  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

74

Sludge digester  

SciTech Connect

A ballasted, gas-holding, liquid sludge digester is described comprising: a main liquid sludge tank having a bottom wall and upwardly projecting sidewall; a cover having a top and depending side skirt structure which telescopes with respect to the upwardly projecting sidewall of the main tank; ballast supported near the lower edge of said side skirt; a ballast-engaging, liquid-containing well joined to said sidewall of said main tank such that said cover provides a gas-tight seal when said ballast interacts with liquid in said well so as to be partially emerged or fully submerged in the liquid; liquid fill means interacting with said well to maintain a predetermined liquid level in the well when said ballast is at least partially emerged from the liquid in said well; and overflow means interacting with said well to maintain a predetermined liquid level in the well when said ballast is submerged in the liquid in the well.

Wight, J.L.; Cook, L.W.

1993-08-24T23:59:59.000Z

75

PDSF Batch Statistics  

NLE Websites -- All DOE Office Websites (Extended Search)

Summaries PDSF Group Batch Summary Year Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2013 SGE62 SGE62 SGE62 SGE62 SGE62 SGE62 SGE62 SGE62 SGE62 Partial SGE62 2012 SGE62 SGE62...

76

Submitting Batch Jobs on Franklin  

NLE Websites -- All DOE Office Websites (Extended Search)

Submitting Batch Jobs Submitting Batch Jobs Debug Jobs Short jobs requesting less than 30 minutes and requiring 512 nodes (2,048 cores) or fewer can run in the debug queue. From...

77

Sludge Batch 7 (SB7) Washing and Settling Demonstration  

Generate test slurry Wash per SB7 plan Quantify settling vs wash cycle and time Sampling and analysis. SB7 Washing and Settling Demonstration 5 ...

78

Monitoring Uranium Transformations Determined by the Evolution of Biogeochemical Processes: Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory  

SciTech Connect

With funds provided by the US DOE, Argonne National Laboratory subcontracted the design of batch and column studies to a Stanford University team with field experience at the ORNL IFRC, Oak Ridge, TN. The contribution of the Stanford group ended in 2011 due to budget reduction in ANL. Over the funded research period, the Stanford research team characterized ORNL IFRC groundwater and sediments and set up microcosm reactors and columns at ANL to ensure that experiments were relevant to field conditions at Oak Ridge. The results of microcosm testing demonstrated that U(VI) in sediments was reduced to U(IV) with the addition of ethanol. The reduced products were not uraninite but were instead U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. The Stanford team communicated with the ANL team members through email and conference calls and face to face at the annual ERSP PI meeting and national meetings.

Criddle, Craig S.; Wu, Weimin

2013-04-17T23:59:59.000Z

79

Biogas Generation from a 2-Phase Sludge Treatment System  

Science Conference Proceedings (OSTI)

The degradation of sewage sludge in single stage and 2 phase anaerobic systems was investigated in bench-scale batch reactors. Average COD reduction efficiency in 2 phase system in this initial phase of the study was 4.5% (30 days HRT) and 3.3% (20 days ... Keywords: dge digestion, 2-phase, single stage, qPCR, microbial communities

Taranveer Singh Mann, Terence Goh, William Phay

2013-04-01T23:59:59.000Z

80

Submitting Batch Jobs on Franklin  

NLE Websites -- All DOE Office Websites (Extended Search)

Submitting Batch Jobs Submitting Batch Jobs Submitting Batch Jobs Debug Jobs Short jobs requesting less than 30 minutes and requiring 512 nodes (2,048 cores) or fewer can run in the debug queue. From 5am-6pm Pacific Time, 256 nodes are reserved for debugging and interactive use. See also, running Interactive Jobs. Sample Batch Scripts The following batch script requests 8 cores on 2 nodes with a 10 minute wall clock limit in the debug queue. Torque directive lines tell the batch system how to run a job and begin with #PBS. #PBS -q debug #PBS -l mppwidth=8 #PBS -l walltime=00:10:00 #PBS -j eo #PBS -V cd $PBS_O_WORKDIR aprun -n 8 ./a.out Here is another example requesting 8 processors using 4 nodes with only 2 cores per node: #PBS -q debug #PBS -l mppwidth=8 #PBS -l mppnppn=2 #PBS -l walltime=00:10:00

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

NDA BATCH 2009-7  

Science Conference Proceedings (OSTI)

The testing facility is LLNL plutonium facility segmented gamma scanner. 100% of the radioassay data in the batch data report is reviewed.

Lawrence Livermore National Laboratory

2009-10-30T23:59:59.000Z

82

Progressing batch hydrolysis process  

DOE Patents (OSTI)

A progressive batch hydrolysis process for producing sugar from a lignocellulosic feedstock, comprising passing a stream of dilute acid serially through a plurality of percolation hydrolysis reactors charged with said feedstock, at a flow rate, temperature and pressure sufficient to substantially convert all the cellulose component of the feedstock to glucose; cooling said dilute acid stream containing glucose, after exiting the last percolation hydrolysis reactor, then feeding said dilute acid stream serially through a plurality of prehydrolysis percolation reactors, charged with said feedstock, at a flow rate, temperature and pressure sufficient to substantially convert all the hemicellulose component of said feedstock to glucose; and cooling the dilute acid stream containing glucose after it exits the last prehydrolysis reactor.

Wright, John D. (Denver, CO)

1986-01-01T23:59:59.000Z

83

Progressing batch hydrolysis process  

DOE Patents (OSTI)

A progressive batch hydrolysis process is disclosed for producing sugar from a lignocellulosic feedstock. It comprises passing a stream of dilute acid serially through a plurality of percolation hydrolysis reactors charged with feed stock, at a flow rate, temperature and pressure sufficient to substantially convert all the cellulose component of the feed stock to glucose. The cooled dilute acid stream containing glucose, after exiting the last percolation hydrolysis reactor, serially fed through a plurality of pre-hydrolysis percolation reactors, charged with said feedstock, at a flow rate, temperature and pressure sufficient to substantially convert all the hemicellulose component of said feedstock to glucose. The dilute acid stream containing glucose is cooled after it exits the last prehydrolysis reactor.

Wright, J.D.

1985-01-10T23:59:59.000Z

84

CX-009118: Categorical Exclusion Determination  

Energy.gov (U.S. Department of Energy (DOE))

Sludge Batch 8 Qualification: Washing and Defense Waste Processing Facility Simulations (Rad) CX(s) Applied: B3.6 Date: 08/14/2012 Location(s): South Carolina Offices(s): Savannah River Operations Office

85

CX-010491: Categorical Exclusion Determination  

Energy.gov (U.S. Department of Energy (DOE))

Sludge Batch 8 (SB8) Waste Acceptance Product Specifications (WAPS) CX(s) Applied: B3.6 Date: 05/21/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office

86

ELECTROCHEMICAL CORROSION STUDY FOR TANK 241-AY-102 SLUDGE  

SciTech Connect

The report describes the analyses performed on core samples from the sludge region of the waste in Tank 241-AY-102 to determine the electrochemical corrosion potential.

DUNCAN JB

2002-09-24T23:59:59.000Z

87

An evaluation of predictive environmental test procedures for sewage sludge.  

E-Print Network (OSTI)

??This research project aimed at evaluating four internationally accepted leachate extraction tests to determine their applicability on sewage sludge samples. Furthermore, the present analytical method… (more)

Kasselman, Graeme

2005-01-01T23:59:59.000Z

88

Pretreatment of microbial sludges  

DOE Patents (OSTI)

Methods are described for pretreating microbial sludges to break cells and disrupt organic matter. One method involves the use of sonication, and another method involves the use of shear forces. The pretreatment of sludge enhances bioconversion of the organic fraction. This allows for efficient dewatering of the sludge and reduces the cost for final disposal of the waste.

Rivard, Christopher J. (Lakewood, CO); Nagle, Nicholas J. (Louisville, CO)

1995-01-01T23:59:59.000Z

89

Pretreatment of microbial sludges  

DOE Patents (OSTI)

Methods are described for pretreating microbial sludges to break cells and disrupt organic matter. One method involves the use of sonication, and another method involves the use of shear forces. The pretreatment of sludge enhances bioconversion of the organic fraction. This allows for efficient dewatering of the sludge and reduces the cost for final disposal of the waste.

Rivard, C.J.; Nagle, N.J.

1995-01-10T23:59:59.000Z

90

EFFECT OF GLASS-BATCH MAKEUP ON THE MELTING PROCESS  

SciTech Connect

The response of a glass batch to heating is determined by the batch makeup and in turn determines the rate of melting. Batches formulated for a high-alumina nuclear waste to be vitrified in an all-electric melter were heated at a constant temperature-increase rate to determine changes in melting behavior in response to the selection of batch chemicals and silica grain-size as well as the addition of heat-generating reactants. The type of batch materials and the size of silica grains determine how much, if any, primary foam occurs during melting. Small quartz grains, 5 {micro}m in size, caused extensive foaming because their major portion dissolved at temperatures <800 C, contributing to the formation of viscous glass forming melt that trapped evolving batch gases. Primary foam did not occur in batches with larger quartz grains, {+-}75 {micro}m in size, because their major portion dissolved at temperatures >800 C when batch gases no longer evolved. The exothermal reaction of nitrates with sucrose was ignited at a temperature as low as 160 C and caused a temporary jump in temperature of several hundred degrees. Secondary foam, the source of which is oxygen from redox reactions, occurred in all batches of a limited composition variation involving five oxides, B{sub 2}O{sub 3}, CaO, Li{sub 2}O, MgO, and Na{sub 2}O. The foam volume at the maximum volume-increase rate was a weak function of temperature and melt basicity. Neither the batch makeup nor the change in glass composition had a significant impact on the dissolution of silica grains. The impacts of primary foam generation on glass homogeneity and the rate of melting in large-scale continuous furnaces have yet to be established via mathematical modeling and melter experiments.

KRUGER AA; HRMA P

2010-12-07T23:59:59.000Z

91

Solidification Tests for LLW Sludges  

Science Conference Proceedings (OSTI)

Oak Ridge National laboratory has about 350,000 gallons of remote-handled (RH) sludge in ten liquid low-level waste (LLLW) tanks that must be solidified and stabilized for disposal at the Nevada Test Site. Samples of the waste sludge were collected from four tanks, and a total of 36 small-scale grouting tests were performed. The presence of free water during curing was evaluated, and the cured grouts were analyzed using the Toxicity Characteristic Leaching Procedure (TCLP) to determine if any of the hazardous metals in the sludge (Cd, Cr, Hg, Pb, etc.) would leach above the Resource Conservation and Recovery Act (RCRA) limits/ The grouting formulation used for these tests, with ratios of grout-forming additives weight to waste slurry weight ranging from 0.75:1 to 1.2:1, produced wet grout mixtures that were easy to stir and were self leveling. The grout mixtures cured with no free water visible at any time. The cured grout matrix was very effective at retaining the hazardous metals in the sludge, with TCLP leachate concentrations well below the RCRA limits. The addition of ferrous sulfide (FeS) to some of the sludge samples resulted in, at most, a minimal reduction in the amount of mercury that leached from the grout samples, and had no detectable impact on the other heavy metals present in the sludge (Cd, Cr, and Pb). The TCLP extraction was performed on three samples after 1 day and 7 days of curing, compared to the >28 days for the remaining samples. The metal concentrations for the short cure time samples were similar to the remaining samples, and were all well below the RCRA limits.

Taylor, Paul Allen [ORNL

2009-01-01T23:59:59.000Z

92

ALARA ASSESSMENT OF SETTLER SLUDGE SAMPLING METHODS  

SciTech Connect

The purpose of this assessment is to compare underwater and above water settler sludge sampling methods to determine if the added cost for underwater sampling for the sole purpose of worker dose reductions is justified. Initial planning for sludge sampling included container, settler and knock-out-pot (KOP) sampling. Due to the significantly higher dose consequence of KOP sludge, a decision was made to sample KOP underwater to achieve worker dose reductions. Additionally, initial plans were to utilize the underwater sampling apparatus for settler sludge. Since there are no longer plans to sample KOP sludge, the decision for underwater sampling for settler sludge needs to be revisited. The present sampling plan calls for spending an estimated $2,500,000 to design and construct a new underwater sampling system (per A21 C-PL-001 RevOE). This evaluation will compare and contrast the present method of above water sampling to the underwater method that is planned by the Sludge Treatment Project (STP) and determine if settler samples can be taken using the existing sampling cart (with potentially minor modifications) while maintaining doses to workers As Low As Reasonably Achievable (ALARA) and eliminate the need for costly redesigns, testing and personnel retraining.

NELSEN LA

2009-01-30T23:59:59.000Z

93

Using the PDSF Batch System  

NLE Websites -- All DOE Office Websites (Extended Search)

System System Using the PDSF Batch System Submitting PDSF Jobs UGE (Univa Grid Engine) is the batch system used at PDSF. Read More » Scratch Space Use on Compute Nodes Use $TMPDIR and not /scratch or /tmp directly. Read More » I/O Resources I/O resources are in important tool at PDSF and this page describes how to use them. Read More » Running Interactive Batch Jobs This page describes when you should consider working in an interactive batch session and how to do it. Read More » Monitoring and Managing Jobs This page is about what you can do with your jobs after you have submitted them. Read More » Getting Info about Completed Jobs UGE accounting information about all jobs is available and this page describes how to access it. Read More » PDSF Batch Job Example

94

REMOVING SLUDGE HEELS FROM SAVANNAH RIVER SITE WASTE TANKS BY OXALIC ACID DISSOLUTION  

SciTech Connect

The Savannah River Site (SRS) will remove sludge as part of waste tank closure operations. Typically the bulk sludge is removed by mixing it with supernate to produce a slurry, and transporting the slurry to a downstream tank for processing. Experience shows that a residual heel may remain in the tank that cannot be removed by this conventional technique. In the past, SRS used oxalic acid solutions to disperse or dissolve the sludge heel to complete the waste removal. To better understand the actual conditions of oxalic acid cleaning of waste from carbon steel tanks, the authors developed and conducted an experimental program to determine its effectiveness in dissolving sludge, the hydrogen generation rate, the generation rate of other gases, the carbon steel corrosion rate, the impact of mixing on chemical cleaning, the impact of temperature, and the types of precipitates formed during the neutralization process. The test samples included actual SRS sludge and simulated SRS sludge. The authors performed the simulated waste tests at 25, 50, and 75 C by adding 8 wt % oxalic acid to the sludge over seven days. They conducted the actual waste tests at 50 and 75 C by adding 8 wt % oxalic acid to the sludge as a single batch. Following the testing, SRS conducted chemical cleaning with oxalic acid in two waste tanks. In Tank 5F, the oxalic acid (8 wt %) addition occurred over seven days, followed by inhibited water to ensure the tank contained enough liquid to operate the mixer pumps. The tank temperature during oxalic acid addition and dissolution was approximately 45 C. The authors analyzed samples from the chemical cleaning process and compared it with test data. The conclusions from the work are: (1) Oxalic acid addition proved effective in dissolving sludge heels in the simulant demonstration, the actual waste demonstration, and in SRS Tank 5F. (2) The oxalic acid dissolved {approx} 100% of the uranium, {approx} 100% of the iron, and {approx} 40% of the manganese during a single contact in the simulant demonstration. (The iron dissolution may be high due to corrosion of carbon steel coupons.) (3) The oxalic acid dissolved {approx} 80% of the uranium, {approx} 70% of the iron, {approx} 50% of the manganese, and {approx} 90% of the aluminum in the actual waste demonstration for a single contact. (4) The oxalic acid dissolved {approx} 100% of the uranium, {approx} 15% of the iron, {approx} 40% of the manganese, and {approx} 80% of the aluminum in Tank 5F during the first contact cycle. Except for the iron, these results agree well with the demonstrations. The data suggest that a much larger fraction of the iron in the sludge dissolved, but it re-precipitated with the oxalate added to Tank 5F. (5) The demonstrations produced large volumes (i.e., 2-14 gallons of gas/gallon of oxalic acid) of gas (primarily carbon dioxide) by the reaction of oxalic acid with sludge and carbon steel. (6) The reaction of oxalic acid with carbon steel produced hydrogen in the simulant and actual waste demonstrations. The volume produced varied from 0.00002-0.00100 ft{sup 3} hydrogen/ft{sup 2} carbon steel. The hydrogen production proved higher in unmixed tanks than in mixed tanks.

Poirier, M; David Herman, D; Fernando Fondeur, F; John Pareizs, J; Michael Hay, M; Bruce Wiersma, B; Kim Crapse, K; Thomas Peters, T; Samuel Fink, S; Donald Thaxton, D

2009-03-01T23:59:59.000Z

95

CX-010653: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3: Categorical Exclusion Determination 3: Categorical Exclusion Determination CX-010653: Categorical Exclusion Determination Sludge Batch 8 Processability Study CX(s) Applied: B3.6 Date: 06/25/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office Savannah River National Laboratory will perform a study of how parameters influenced by Defense Waste Processing Facility Chemical Process Cell (CPC) operation influence slurry properties such as rheology, gas retention, and foaming. The program will utilize actual waste sludge material. The resulting information will be used to aid in the understanding of recent DWPF processing issues. CX-010653.pdf More Documents & Publications CX-009118: Categorical Exclusion Determination CX-009101: Categorical Exclusion Determination CX-010491

96

Simulated Annealing For The Optimization Of Chemical Batch Production Processes  

E-Print Network (OSTI)

Batch distillation processes are widely used in chemical industry. In this work, we consider the optimization of such processes by simulated annealing. Although this method is stochastically in nature, it has two evitable advantages: it can be readily connected to highly sophisticated simulation codes and it converges towards a global optimum. According to the characteristics of batch distillation operation we propose to use a two-step computation approach. A feasible strategy (admissible control) will be searched for in the first step and it will be optimized in the second step. The approach has been applied to three models of batch distillation ranging from a simple test example to a real production system. These results show the potential of the method for developing optimal operation strategies for batch chemical processes. Keywords: batch distillation, simulated annealing, dynamic optimization. 1 Introduction The determination of optimal control strategies for chemical processe...

Michael Hanke; Pu Li

1998-01-01T23:59:59.000Z

97

Evaluation of nitrogen availability in irradiated sewage sludge, sludge compost and manure compost  

Science Conference Proceedings (OSTI)

A field experiment was conducted during 2 yr to determine plant availability of organic N from organic wastes, and effects of gamma irradiation on organic N availability in sewage sludge. The wastes investigated were: digested, dewatered sewage sludge (DSS), irradiated sewage sludge (DISS), irradiated, composted sewage sludge (DICSS), and composted livestock manure (CLM). The annual application rates were: 10, 20, 30, and 40 Mg solids ha{sup {minus}1}. Fertilizer N was added to the control, to which no waste was applied, as well as to the waste applications to ensure approximately equal amounts of available N (110 kg N ha{sup {minus}1}) for all treatments. Lettuce, petunias, and beans were grown in 1990 and two cuts of lettuce were harvested in 1991. Crop yields and plant N concentrations were measured. Assuming that crop N harvested/available N applied would be approximately equal for the control and the waste treatments, the N from organic fraction of the wastes, which is as available as that in fertilizer, was estimated. With petunia in 1990 and the combination of first and second cut of lettuce in 1991, the percentage ranged from 11.2 to 29.7 in nonirradiated sludge, 10.1 to 14.0 in irradiated sludge, 10.5 to 32.1 in sludge compost and 10.0 to 19.7 in manure compost. Most often, the highest values were obtained with the lowest application rates. Yields of petunia and N concentrations in second cut lettuce in 1991 were lower with irradiated sludge than with nonirradiated sludge suggest that the availability of organic N in digested sludge may have been reduced after irradiation. Irradiation of sludge appears to have released NH{sub 4}{sup +}-N. The availability of organic N, however, appears to have been reduced by irradiation by greater amount than the increase in NH{sub 4}{sup +}-N. 41 refs., 2 figs., 6 tabs.

Wen, Guang; Bates, T.E.; Voroney, R.P. [Univ. of Guelph, Ontario (Canada)

1995-05-01T23:59:59.000Z

98

Edison batch system is up and running  

NLE Websites -- All DOE Office Websites (Extended Search)

batch system is up and running Edison batch system is up and running July 25, 2013 (0 Comments) Edison batch system is up and running. Cray benchmark team and NERSC staff have...

99

Early-warning process/control for anaerobic digestion and biological nitrogen transformation processes: Batch, semi-continuous, and/or chemostat experiments. Final report  

DOE Green Energy (OSTI)

The objective of this project was to develop and test an early-warning/process control model for anaerobic sludge digestion (AD). The approach was to use batch and semi-continuously fed systems and to assemble system parameter data on a real-time basis. Specific goals were to produce a real-time early warning control model and computer code, tested for internal and external validity; to determine the minimum rate of data collection for maximum lag time to predict failure with a prescribed accuracy and confidence in the prediction; and to determine and characterize any trends in the real-time data collected in response to particular perturbations to feedstock quality. Trends in the response of trace gases carbon monoxide and hydrogen in batch experiments, were found to depend on toxicant type. For example, these trace gases respond differently for organic substances vs. heavy metals. In both batch and semi-continuously feed experiments, increased organic loading lead to proportionate increases in gas production rates as well as increases in CO and H{sub 2} concentration. An analysis of variance of gas parameters confirmed that CO was the most sensitive indicator variable by virtue of its relatively larger variance compared to the others. The other parameters evaluated including gas production, methane production, hydrogen, carbon monoxide, carbon dioxide and methane concentration. In addition, a relationship was hypothesized between gaseous CO concentration and acetate concentrations in the digester. The data from semicontinuous feed experiments were supportive.

Hickey, R. [Science Applications International Corp., McLean, VA (United States)

1992-09-01T23:59:59.000Z

100

Data-driven batch schuduling  

SciTech Connect

In this paper, we develop data-driven strategies for batch computing schedulers. Current CPU-centric batch schedulers ignore the data needs within workloads and execute them by linking them transparently and directly to their needed data. When scheduled on remote computational resources, this elegant solution of direct data access can incur an order of magnitude performance penalty for data-intensive workloads. Adding data-awareness to batch schedulers allows a careful coordination of data and CPU allocation thereby reducing the cost of remote execution. We offer here new techniques by which batch schedulers can become data-driven. Such systems can use our analytical predictive models to select one of the four data-driven scheduling policies that we have created. Through simulation, we demonstrate the accuracy of our predictive models and show how they can reduce time to completion for some workloads by as much as 80%.

Bent, John [Los Alamos National Laboratory; Denehy, Tim [GOOGLE; Arpaci - Dusseau, Remzi [UNIV OF WISCONSIN; Livny, Miron [UNIV OF WISCONSIN; Arpaci - Dusseau, Andrea C [NON LANL

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Analysis of sludge from K East basin floor and weasel pit  

Science Conference Proceedings (OSTI)

Sludge samples from the floor of the Hanford K East Basin fuel storage pool have been retrieved and analyzed. Both chemical and physical properties have been determined. The results are to be used to determine the disposition of the bulk of the sludge and possibly assess the impact of residual sludge on dry storage of the associated intact metallic uranium fuel elements.

Makenas, B.J., Westinghouse Hanford

1996-05-04T23:59:59.000Z

102

Continuous Sludge Leaching  

NLE Websites -- All DOE Office Websites (Extended Search)

Continuous Sludge Leaching Reid Peterson and Renee Russell - Battelle Pacific Northwest Division Terry Sams and Bill Brasel - Parsons 2 What is CSL? * Process diagram * Full scale...

103

Disposal of Lead Sludge - TMS  

Science Conference Proceedings (OSTI)

Aug 1, 2000 ... Problems with this sludge were investigated and methods were tested with the aim of stabilizing the sludge so that is passes the EPD TCLP test ...

104

HYDROGEN GENERATION FROM SLUDGE SAMPLE BOTTLES CAUSED BY RADIOLYSIS AND CHEMISTRY WITH CONCETNRATION DETERMINATION IN A STANDARD WASTE BOX (SWB) OR DRUM FOR TRANSPORT  

DOE Green Energy (OSTI)

A volume of 600 mL of sludge, in 4.1 L sample bottles (Appendix 7.6), will be placed in either a Super Pig (Ref. 1) or Piglet (Ref. 2, 3) based on shielding requirements (Ref. 4). Two Super Pigs will be placed in a Standard Waste Box (SWB, Ref. 5), as their weight exceeds the capacity of a drum; two Piglets will be placed in a 55-gallon drum (shown in Appendix 7.2). The generation of hydrogen gas through oxidation/corrosion of uranium metal by its reaction with water will be determined and combined with the hydrogen produced by radiolysis. The hydrogen concentration in the 55-gallon drum and SWB will be calculated to show that the lower flammability limit of 5% hydrogen is not reached. The inner layers (i.e., sample bottle, bag and shielded pig) in the SWB and drum will be evaluated to assure no pressurization occurs as the hydrogen vents from the inner containers (e.g., shielded pigs, etc.). The reaction of uranium metal with anoxic liquid water is highly exothermic; the heat of reaction will be combined with the source term decay heat, calculated from Radcalc, to show that the drum and SWB package heat load limits are satisfied. This analysis does five things: (1) Estimates the H{sub 2} generation from the reaction of uranium metal with water; (2) Estimates the H{sub 2} generation from radiolysis (using Radcalc 4.1); (3) Combines both H{sub 2} generation amounts, from Items 1 and 2, and determines the percent concentration of H{sub 2} in the interior of an SWB with two Super Pigs, and the interior of a 55-gallon drum with two Piglets; (4) From the combined gas generation rate, shows that the pressure at internal layers is minimal; and (5) Calculates the maximum thermal load of the package, both from radioactive decay of the source and daughter products as calculated/reported by Radcalc 4.1, and from the exothermic reaction of uranium metal with water.

RILEY DL; BRIDGES AE; EDWARDS WS

2010-03-30T23:59:59.000Z

105

INHIBITION OF WASHED SLUDGE WITH SODIUM NITRITE  

SciTech Connect

This report describes the results of electrochemical tests used to determine the relationship between the concentration of the aggressive anions in washed sludge and the minimum effective inhibitor concentration. Sodium nitrate was added as the inhibitor because of its compatibility with the DWPF process. A minimum of 0.05M nitrite is required to inhibit the washed sludge simulant solution used in this study. When the worst case compositions and safety margins are considered, it is expected that a minimum operating limit of nearly 0.1M nitrite will be specified. The validity of this limit is dependent on the accuracy of the concentrations and solubility splits previously reported. Sodium nitrite additions to obtain 0.1M nitrite concentrations in washed sludge will necessitate the additional washing of washed precipitate in order to decrease its sodium nitrite inhibitor requirements sufficiently to remain below the sodium limits in the feed to the DWPF. Nitrite will be the controlling anion in "fresh" washed sludge unless the soluble chloride concentration is about ten times higher than predicted by the solubility splits. Inhibition of "aged" washed sludge will not be a problem unless significant chloride dissolution occurs during storage. It will be very important tomonitor the composition of washed sludge during processing and storage.

Congdon, J.; Lozier, J.

2012-09-25T23:59:59.000Z

106

SLUDGE TREATMENT PROJECT ENGINEERED CONTAINER RETRIEVAL AND TRANSFER SYSTEM PRELMINARY DESIGN HAZARD AND OPERABILITY STUDY  

Science Conference Proceedings (OSTI)

This Hazard and Operability (HAZOP) study addresses the Sludge Treatment Project (STP) Engineered Container Retrieval and Transfer System (ECRTS) preliminary design for retrieving sludge from underwater engineered containers located in the 105-K West (KW) Basin, transferring the sludge as a sludge-water slurry (hereafter referred to as 'slurry') to a Sludge Transport and Storage Container (STSC) located in a Modified KW Basin Annex, and preparing the STSC for transport to T Plant using the Sludge Transport System (STS). There are six, underwater engineered containers located in the KW Basin that, at the time of sludge retrieval, will contain an estimated volume of 5.2 m{sup 3} of KW Basin floor and pit sludge, 18.4 m{sup 3} of 105-K East (KE) Basin floor, pit, and canister sludge, and 3.5 m{sup 3} of settler tank sludge. The KE and KW Basin sludge consists of fuel corrosion products (including metallic uranium, and fission and activation products), small fuel fragments, iron and aluminum oxide, sand, dirt, operational debris, and biological debris. The settler tank sludge consists of sludge generated by the washing of KE and KW Basin fuel in the Primary Clean Machine. A detailed description of the origin of sludge and its chemical and physical characteristics can be found in HNF-41051, Preliminary STP Container and Settler Sludge Process System Description and Material Balance. In summary, the ECRTS retrieves sludge from the engineered containers and hydraulically transfers it as a slurry into an STSC positioned within a trailer-mounted STS cask located in a Modified KW Basin Annex. The slurry is allowed to settle within the STSC to concentrate the solids and clarify the supernate. After a prescribed settling period the supernate is decanted. The decanted supernate is filtered through a sand filter and returned to the basin. Subsequent batches of slurry are added to the STSC, settled, and excess supernate removed until the prescribed quantity of sludge is collected. The sand filter is then backwashed into the STSC. The STSC and STS cask are then inerted and transported to T Plant.

CARRO CA

2011-07-15T23:59:59.000Z

107

Sludge Mass Reduction Update  

NLE Websites -- All DOE Office Websites (Extended Search)

in the tank Designed to handle obstructions in the tank - Steel Tapes - Thermowells - Sludge mounds 11 Mechanical Cleaning of SRS Tanks 18 and 19 Hose-in-hose System Overview...

108

Composting Manure and Sludge  

E-Print Network (OSTI)

Composted manure and sludge can be a valuable fertilizer, but special equipment is required. Composting can be done with windrow operations, aerated windrow operations or aerated bins. Factors that affect composting rates are included.

Sweeten, John M.

2008-07-08T23:59:59.000Z

109

DOWNSTREAM IMPACTS OF SLUDGE MASS REDUCTION VIA ALUMINUM DISSOLUTION ON DWPF PROCESSING OF SAVANNAH RIVER SITE HIGH LEVEL WASTE - 9382  

Science Conference Proceedings (OSTI)

The SRS sludge that was to become a major fraction of Sludge Batch 5 (SB5) for the Defense Waste Processing Facility (DWPF) contained a large fraction of H-Modified PUREX (HM) sludge, containing a large fraction of aluminum compounds that could adversely impact the processing and increase the vitrified waste volume. It is beneficial to reduce the non-radioactive fraction of the sludge to minimize the number of glass waste canisters that must be sent to a Federal Repository. Removal of aluminum compounds, such as boehmite and gibbsite, from sludge can be performed with the addition of NaOH solution and heating the sludge for several days. Preparation of SB5 involved adding sodium hydroxide directly to the waste tank and heating the contents to a moderate temperature through slurry pump operation to remove a fraction of this aluminum. The Savannah River National Laboratory (SRNL) was tasked with demonstrating this process on actual tank waste sludge in our Shielded Cells Facility. This paper evaluates some of the impacts of aluminum dissolution on sludge washing and DWPF processing by comparing sludge processing with and without aluminum dissolution. It was necessary to demonstrate these steps to ensure that the aluminum removal process would not adversely impact the chemical and physical properties of the sludge which could result in slower processing or process upsets in the DWPF.

Pareizs, J; Cj Bannochie, C; Michael Hay, M; Daniel McCabe, D

2009-01-14T23:59:59.000Z

110

Properties and potential uses of water treatment sludge from the Neches River of southeast Texas  

E-Print Network (OSTI)

Land application of water treatment plant (WTP) sludge has been an unsolved problem. The objectives of this study were (1) to investigate characteristics of organic polymer sludge, and (2) to determine the effects of the sludge on soil properties that influence utilization of the sludge as a soil amendment. Water treatment sludges were obtained from water utilities along the Neches Rivet-near Beaumont, Texas. They were mostly coagulated with organic polymers. Mineralogical composition, cation exchange capacity (CEC), scanning and transmission electron microscopy (SEM and TEM), aggregate stability, Atterberg limits, hydraulic conductivity, dispersion, crust strength, adsorption characteristics, nitrogen content and mineralization potential of the sludge or sludge-amended soil were determined in this study. Mineralogical composition of organic polymer sludge was similar to local Beaumont clay soil. The major fraction of the sludge, the coarse clay, was estimated to be 40% kaolinite, 32% smectite, 20% quartz and 8% mica. However, XRD patterns of the sludge indicated that expansion of the smectite was inhibited by organic polymer coagulant added during water clarification, which also was confirmed by aggregate stability of the sludge. Cation exchange capacity of the bulk sludge samples ranged from 8 to 28 cmol kg-1. Quantitative mineralogical analyses showed that CEC of the sludge was reduced by blockage of cation exchange sites with organic polymers. SEM and TEM results indicated that the sludge was mostly fine aggregates of clay particles. Dried sludge aggregates were not prone to swell, due to their resistance to rewetting. The aggregate stability of dried sludge was above 90% after a 24 hours soaking period in water, compared to 7% aggregate stability of local Beaumont clay soil. Addition of 0 to 10% sludge to Boonville sandy loam soil increased the aggregate stability of the soil from 4 to 13%. Atterberg limit showed that wet sludge had wide ranges of moisture contents in semi-solid and plastic states, and shrunk greatly during drying. Shrinkage limit of the sludges ranged from 16 to 66%; plastic limit from 111 to 138%; and liquid limit from 208 to 320%, which suggested that the sludge was highly plastic and compressible. Addition of 0 to 10% sludge into Boonville sandy loam soil increased the infiltration rate of the soil two orders of magnitudes from 1.4 x 10-4 to 1. I X 10-2 CM / S, and reduced the dispersion of the soil significantly. Moreover, addition of from 0 to 10% sludge into Boonville sandy loam soil greatly reduced the crusting produced by rainfall, and the penetration resistance of the crust decreased from 53.1 to 14.4 kg / cm. Metal adsorbing ability of the Boonville sandy loam soil was reduced by addition of the sludge. Adsorption of Zn+2 decreased from 19.7 to 17.7 ug / g when the sludge was amended from 0 to 10%. Total nitrogen and exchangeable ammonium nitrogen (NH4+) contents of the sludge were four times and twenty times as high, respectively, as those of local Beaumont clay and Lake Charles clay soils. Organic polymer coagulants added during water treatment apparently increased nitrogen content of the sludge. Although the sludge contained considerable total nitrogen, incubation experiment of sludge-amended Beaumont clay or Lake Charles clay soil showed that nitrogen mineralization rate was not affected by the sludge addition. This study indicated that the sludge can improve soil physical properties significantly, e.g. soil aggregation, infiltration, dispersion and crusting. The low nitrogen mineralization rate of the sludge showed that the sludge had little fertility and would not produce a groundwater contamination problem.

Kan, Weiqun

1995-01-01T23:59:59.000Z

111

Batch-oriented software appliances  

E-Print Network (OSTI)

This paper presents AppPot, a system for creating Linux software appliances. AppPot can be run as a regular batch or grid job and executed in user space, and requires no special virtualization support in the infrastructure. The main design goal of AppPot is to bring the benefits of a virtualization-based IaaS cloud to existing batch-oriented computing infrastructures. In particular, AppPot addresses the application deployment and configuration on large heterogeneous computing infrastructures: users are enabled to prepare their own customized virtual appliance for providing a safe execution environment for their applications. These appliances can then be executed on virtually any computing infrastructure being in a private or public cloud as well as any batch-controlled computing clusters the user may have access to. We give an overview of AppPot and its features, the technology that makes it possible, and report on experiences running it in production use within the Swiss National Grid infrastructure SMSCG.

Murri, Riccardo

2012-01-01T23:59:59.000Z

112

Standard Seawater Comparison of Some Recent Batches  

Science Conference Proceedings (OSTI)

The comparison experiment results of the standard seawater (SSW) were presented for batches P90, P100, P104, P106, P108 P111, and P112. This work shows that the SSW batch-to-batch agreement was recently improved. The adjusted mean differences ...

Yasushi Takatsuki; Michio Aoyama; Toshiya Nakano; Haruo Miyagi; Toshihiro Ishihara; Toshiya Tsutsumida

1991-12-01T23:59:59.000Z

113

Laboratory development of sludge washing and alkaline leaching processes: Test plan for FY 1994  

Science Conference Proceedings (OSTI)

The US Department of Energy plans to vitrify (as borosilicate glass) the large volumes of high-level radioactive wastes at the Hanford site. To reduce costs, pretreatment processes will be used to reduce the volume of borosilicate glass required for disposal. Several options are being considered for the pretreatment processes: (1) sludge washing with water or dilute hydroxide: designed to remove most of the Na from the sludge, thus significantly reducing the volume of waste to be vitrified; (2) sludge washing plus caustic leaching and/or metathesis (alkaline sludge leaching): designed to dissolve large quantities of certain nonradioactive elements, such as Al, Cr and P, thus reducing the volume of waste even more; (3) sludge washing, sludge dissolution, and separation of radionuclides from the dissolved sludge solutions (advanced processing): designed to remove all radionuclides for concentration into a minimum waste volume. This report describes a test plan for work that will be performed in FY 1994 under the Sludge Washing and Caustic Leaching Studies Task (WBS 0402) of the Tank Waste Remediation System (TWRS) Pretreatment Project. The objectives of the work described here are to determine the effects of sludge washing and alkaline leaching on sludge composition and the physical properties of the washed sludge and to evaluate alkaline leaching methods for their impact on the volume of borosilicate glass required to dispose of certain Hanford tank sludges.

Rapko, B.M.; Lumetta, G.J.

1994-07-01T23:59:59.000Z

114

Viscous sludge sample collector  

DOE Patents (OSTI)

A vertical core sample collection system for viscous sludge. A sample tube's upper end has a flange and is attached to a piston. The tube and piston are located in the upper end of a bore in a housing. The bore's lower end leads outside the housing and has an inwardly extending rim. Compressed gas, from a storage cylinder, is quickly introduced into the bore's upper end to rapidly accelerate the piston and tube down the bore. The lower end of the tube has a high sludge entering velocity to obtain a full-length sludge sample without disturbing strata detail. The tube's downward motion is stopped when its upper end flange impacts against the bore's lower end inwardly extending rim.

Beitel, George A. (Richland, WA)

1983-01-01T23:59:59.000Z

115

Categorical Exclusion Determinations: Savannah River Operations Office |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

May 21, 2013 May 21, 2013 CX-010489: Categorical Exclusion Determination Salt Batch 7 Qualification CX(s) Applied: B3.6 Date: 05/21/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office May 14, 2013 CX-010497: Categorical Exclusion Determination Electrical Operations to Perform Yard Maintenance in Electrical Substations CX(s) Applied: B1.3 Date: 05/14/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office May 14, 2013 CX-010496: Categorical Exclusion Determination Corrosion Tests on Carbon Steel Exposed to Oxalic Acid and a Sludge Simulant CX(s) Applied: B3.6 Date: 05/14/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office May 14, 2013 CX-010495: Categorical Exclusion Determination Advanced Fuel Cycle Initiative (AFCI) Am/Cm Separations

116

KE Basin Sludge Flocculant Testing  

SciTech Connect

In the revised path forward and schedule for the K Basins Sludge Retrieval and Disposal Project, the sludge in K East (KE) Basin will be moved from the floor and pits and transferred to large, free-standing containers located in the pits (so as to isolate the sludge from the basin). When the sludge is pumped into the containers, it must settle fast enough and clarify sufficiently that the overflow water returned to the basin pool will not cloud the water or significantly increase the radiological dose rate to the operations staff as a result of increased suspended radioactive material. The approach being evaluated to enhance sludge settling and speed the rate of clarification is to add a flocculant to the sludge while it is being transferred to the containers. In February 2004, seven commercial flocculants were tested with a specific K Basin sludge simulant to identify those agents that demonstrated good performance over a broad range of slurry solids concentrations. From this testing, a cationic polymer flocculant, Nalco Optimer 7194 Plus (7194+), was shown to exhibit superior performance. Related prior testing with K Basin sludge and simulant in 1994/1996 had also identified this agent as promising. In March 2004, four series of jar tests were conducted with 7194+ and actual KE Basin sludge (prepared by combining selected archived KE sludge samples). The results from these jar tests show that 7194+ greatly improves settling of the sludge slurries and clarification of the supernatant.

Schmidt, Andrew J.; Hallen, Richard T.; Muzatko, Danielle S.; Gano, Sue

2004-06-23T23:59:59.000Z

117

Construction and Changes in the Sludge Receipt and Adjustment Tank(Glass Apparatus Development Laboratory)  

SciTech Connect

The Defense Waste Processing Facility (DWPF), at the Savannah River Site is processing and immobilizing the radioactive high level waste sludge slurry at SRS into a durable borosilicate glass for final geological disposal. Each time a new batch of radioactive sludge is to be processed by the DWPF, the process flow sheet is to be tested and demonstrated to ensure an acceptable melter feed and glass can be made. These demonstrations are completed in the Shielded Cells Facility in the Savannah River National Laboratory at SRS.

DOBOS, JAMES

2004-06-02T23:59:59.000Z

118

Nitric acid requirement for treating sludge  

DOE Green Energy (OSTI)

The hydroxylamine nitrate (HAN) precipitate hydrolysis process produces sufficient oxidant (nitrate) such that the resulting blend of formic acid treated sludge and the aqueous product from hydrolysis (PHA) produces a melter feed of acceptable redox (i.e. Fe+2/Total Fe <0.33). With implementation of Late Washing (to reduce the nitrite content of the tetraphenyborate slurry produced during In-Tank Precipitation to 0.01M or less), HAN is no longer required during hydrolysis. As a result, the nitrate content of the melter feed will be reduced greater than an order-of-magnitude and the resulting melter feed produced will be too reducing. If formic acid treatment of the sludge is retained, it will be necessary to trim the melter feed with an oxidant to attain a proper redox. Rather than trimming the melter feed with an oxidant subsequent to the SRAT cycle in which formic acid is used to acidify the sludge, the Savannah River Technology Center (SRTC) has recommended this be accomplished by conversion to nitric acid addition to the Sludge Receipt and Adjustment Tank (SRAT) in place of formic acid (1). This memorandum specifies the stoichiometric bases for determining the nitric acid requirement for the SRAT.

Hsu, C.W.

1992-09-04T23:59:59.000Z

119

Effects of Time, Heat, and Oxygen on K Basin Sludge Agglomeration, Strength, and Solids Volume  

SciTech Connect

Sludge disposition will be managed in two phases under the K Basin Sludge Treatment Project. The first phase is to retrieve the sludge that currently resides in engineered containers in the K West (KW) Basin pool at ~10 to 18°C. The second phase is to retrieve the sludge from interim storage in the sludge transport and storage containers (STSCs) and treat and package it in preparation for eventual shipment to the Waste Isolation Pilot Plant. The work described in this report was conducted to gain insight into how sludge may change during long-term containerized storage in the STSCs. To accelerate potential physical and chemical changes, the tests were performed at temperatures and oxygen partial pressures significantly greater than those expected in the T Plant canyon cells where the STSCs will be stored. Tests were conducted to determine the effects of 50°C oxygenated water exposure on settled quiescent uraninite (UO2) slurry and a full simulant of KW containerized sludge to determine the effects of oxygen and heat on the composition and mechanical properties of sludge. Shear-strength measurements by vane rheometry also were conducted for UO2 slurry, mixtures of UO2 and metaschoepite (UO3•2H2O), and for simulated KW containerized sludge. The results from these tests and related previous tests are compared to determine whether the settled solids in the K Basin sludge materials change in volume because of oxidation of UO2 by dissolved atmospheric oxygen to form metaschoepite. The test results also are compared to determine if heating or other factors alter sludge volumes and to determine the effects of sludge composition and settling times on sludge shear strength. It has been estimated that the sludge volume will increase with time because of a uranium metal ? uraninite ? metaschoepite oxidation sequence. This increase could increase the number of containers required for storage and increase overall costs of sludge management activities. However, the volume might decrease because of decreases in the water-volume fraction caused by sludge solid reactions, compaction, or intergrowth and recrystallization of metaschoepite. In that case, fewer STSCs may be needed, but the shear strength would increase, and this could challenge recovery by water jet erosion and require more aggressive retrieval methods. Overall, the tests described herein indicate that the settled solids volume remains the same or decreases with time. The only case for which the sludge solids volumes increase with time is for the expansion factor attendant upon the anoxic corrosion of uranium metal to produce UO2 and subsequent reaction with oxygen to form equimolar UO2.25 and UO3•2H2O.

Delegard, Calvin H.; Sinkov, Sergey I.; Schmidt, Andrew J.; Daniel, Richard C.; Burns, Carolyn A.

2011-01-04T23:59:59.000Z

120

Pulping lignocellulose in continuous pressurized batch digesters  

Science Conference Proceedings (OSTI)

A batch process to produce kraft pulp is described, in which a combination of black and white liquor is used for cooking of wood chips. In the process, the steam consumption to produce 357 tons/day pulp at 50% yield was approximately 1600 lb/ton pulp, compared with 4000 lb/ton for a batch digester of conventional type.

Green, F.B.

1980-12-02T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Scheduling a capacitated batch-processing machine to minimize makespan  

Science Conference Proceedings (OSTI)

This paper aims at improving the utilization of a single batch-processing machine. The batch-processing machine can process a batch of jobs, as long as the number of jobs and the total size of all the jobs in a batch do not violate the machine's capacity. ... Keywords: Batch processing, Mathematical modeling, Scheduling, Simulated annealing

Purushothaman Damodaran; Krishnaswami Srihari; Sarah S. Lam

2007-04-01T23:59:59.000Z

122

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

SciTech Connect

Samples of sludge were collected from the K East fuel storage basin (KE Basin) floor, contiguous pits (Weasel Pit, North Load Out Pit, Dummy Elevator Pit, and Tech View Pit), and fuel storage canisters between 1995 and 2003 for chemical and radionuclide concentration analysis, physical property determination, and chemical process testing work. Because of the value of the sludge in this testing and because of the cost of obtaining additional fresh samples, an ongoing program of sludge preservation has taken place with the goals to track the sludge identities and preserve, as well as possible, the sludge composition by keeping the sludge in sealed jars and maintaining water coverage on the sludge consistent with the controlling Fluor Hanford (FH) Sampling and Analysis plans and FH contracts with the Pacific Northwest National Laboratory (PNNL). This work was originally initiated to provide material for planned hydrothermal treatment testing in accordance with the test plan for the Sludge Treatment Project (STP) corrosion process chemistry follow on testing (Delegard et al. 2007). Although most of the planned hydrothermal testing was canceled in July 2007 (as described in the forward of Delegard et al. 2007), sample consolidation and characterization was continued to identify a set of well-characterized sludge samples that are suited to support evolving STP initiatives. The work described in the letter was performed by the PNNL under the direction of the Sludge Treatment Project, managed by Fluor Hanford.

Delegard, Calvin H.; Schmidt, Andrew J.; Chenault, Jeffrey W.

2011-11-22T23:59:59.000Z

123

Strength Measurements of Archive K Basin Sludge Using a Soil Penetrometer  

SciTech Connect

Spent fuel radioactive sludge present in the K East and K West spent nuclear fuel storage basins now resides in the KW Basin in six large underwater engineered containers. The sludge will be dispositioned in two phases under the Sludge Treatment Project: (1) hydraulic retrieval into sludge transport and storage containers (STSCs) and transport to interim storage in Central Plateau and (2) retrieval from the STSCs, treatment, and packaging for shipment to the Waste Isolation Pilot Plant. In the years the STSCs are stored, sludge strength is expected to increase through chemical reaction, intergrowth of sludge crystals, and compaction and dewatering by settling. Increased sludge strength can impact the type and operation of the retrieval equipment needed prior to final sludge treatment and packaging. It is important to determine whether water jetting, planned for sludge retrieval from STSCs, will be effective. Shear strength is a property known to correlate with the effectiveness of water jetting. Accordingly, the unconfined compressive strengths (UCS) of archive K Basin sludge samples and sludge blends were measured using a pocket penetrometer modified for hot cell use. Based on known correlations, UCS values can be converted to shear strengths. Twenty-six sludge samples, stored in hot cells for a number of years since last being disturbed, were identified as potential candidates for UCS measurement and valid UCS measurements were made for twelve, each of which was found as moist or water-immersed solids at least 1/2-inch deep. Ten of the twelve samples were relatively weak, having consistencies described as 'very soft' to 'soft'. Two of the twelve samples, KE Pit and KC-4 P250, were strong with 'very stiff' and 'stiff' consistencies described, respectively, as 'can be indented by a thumb nail' or 'can be indented by thumb'. Both of these sludge samples are composites collected from KE Basin floor and Weasel Pit locations. Despite both strong sludges having relatively high iron concentrations, attribution of their high strengths to this factor could not be made with confidence as other measured sludge samples, also from the KE Basin floor and of high iron concentration, were relatively weak. The observed UCS and shear strengths for the two strong sludges were greater than observed in any prior testing of K Basin sludge except for sludge processed at 185 C under hydrothermal conditions.

Delegard, Calvin H.; Schmidt, Andrew J.; Chenault, Jeffrey W.

2011-12-06T23:59:59.000Z

124

Melting of foaming batches: Nuclear waste glass  

Science Conference Proceedings (OSTI)

A simple model is presented for the rate of melting of a batch blanket in an electric glassmelting furnace. The melting process is assumed to be jointly controlled by the heat transfer from the pool of molten glass and the batch-to-glass conversion kinetics. Factors affecting the melting rate in the conversion-controlled regime are discussed. Attention is paid to gas evolution from redox reactions in waste glass batches and component accumulation within the blanket. It is suggested that the high rate of the blanket-free melting in a mechanically agitated furnace is made possible by increasing the rate of melt surface renewal. 27 refs.

Hrma, P.

1990-10-01T23:59:59.000Z

125

Hydrogen Generation Rate During Melter Feed Preparation of Tank 42 Sludge and CST in the Defense Waste Processing Facility  

DOE Green Energy (OSTI)

This document details the testing performed to determine the maximum hydrogen generation expected with a coupled flowsheet of sludge, CST, and frit.

Lambert, D.P.; Monson, P.R.

2001-05-02T23:59:59.000Z

126

Batch Upload | Scientific and Technical Information Program  

Office of Scientific and Technical Information (OSTI)

Notices » Automated Protocols Notices » Automated Protocols Batch Upload Print page Print page Email page Email page One option for electronically submitting AN 241.1 data is Batch Upload (Site-to-OSTI). This method allows sites to upload metadata in a batch XML file at any time. The uploaded XML file is formatted according to the requirements of OSTI's XML. The Batch Upload process allows sites to export data from existing databases and upload it to OSTI. The process is customized for the submitting site. Full text documents can also be uploaded. Sites choose how often and how many records each file will contain. Sites also choose whether to include in the metadata a URL to the site-hosted full text or an uploaded full text. Unclassified documents with CUI access limitations MUST be input to E-Link via the Web Announcement Notice 241.1.

127

Nitrogen Removal in Aerobic Granular Sludge SBR: Real?time Control Strategies  

Science Conference Proceedings (OSTI)

A sequencing batch reactor (SBR) with aerobic granules was operated to determine the effect of different DO concentration on biological nitrogen removal for synthetic sewage treatment

Xiangjuan Yuan; Dawen Gao

2010-01-01T23:59:59.000Z

128

Categorical Exclusion Determinations: B3.6 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

June 26, 2013 June 26, 2013 CX-010901: Categorical Exclusion Determination Fuel-Flexible Combustion System for Refinery and Chemical Plant Process Heaters CX(s) Applied: B3.6 Date: 06/26/2013 Location(s): Texas Offices(s): National Energy Technology Laboratory June 25, 2013 CX-010906: Categorical Exclusion Determination Research and Development (R&D) to Prepare and Characterize Coal/Biomass Mixtures for Direct Co-Feeding into Gasification Systems CX(s) Applied: B3.6 Date: 09/25/2013 Location(s): Alabama Offices(s): National Energy Technology Laboratory June 25, 2013 CX-010653: Categorical Exclusion Determination Sludge Batch 8 Processability Study CX(s) Applied: B3.6 Date: 06/25/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office June 24, 2013 CX-010514: Categorical Exclusion Determination

129

Categorical Exclusion Determinations: B3.6 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

May 22, 2013 May 22, 2013 CX-010487: Categorical Exclusion Determination Defense Waste Processing Facility Precipitate Reactor Feed Tank (PRFT) Sample Analysis CX(s) Applied: B3.6 Date: 05/22/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office May 22, 2013 CX-010274: Categorical Exclusion Determination Analytical Sample Preparation Laboratory CX(s) Applied: B3.6 Date: 05/22/2013 Location(s): Oregon Offices(s): National Energy Technology Laboratory May 22, 2013 CX-010273: Categorical Exclusion Determination High Temperature Laboratory CX(s) Applied: B3.6 Date: 05/22/2013 Location(s): Oregon Offices(s): National Energy Technology Laboratory May 21, 2013 CX-010491: Categorical Exclusion Determination Sludge Batch 8 (SB8) Waste Acceptance Product Specifications (WAPS)

130

Categorical Exclusion Determinations: South Carolina | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

August 14, 2012 August 14, 2012 CX-009121: Categorical Exclusion Determination Roof Repair at 105-C Disassembly CX(s) Applied: B1.3 Date: 08/14/2012 Location(s): South Carolina Offices(s): Savannah River Operations Office August 14, 2012 CX-009120: Categorical Exclusion Determination Analytical Support for Alternate Feed Stock-2 (AFS-2) CX(s) Applied: B3.6 Date: 08/14/2012 Location(s): South Carolina Offices(s): Savannah River Operations Office August 14, 2012 CX-009119: Categorical Exclusion Determination Well Abandonment and Replacement Well Installation in N-Area CX(s) Applied: B3.1 Date: 08/14/2012 Location(s): South Carolina Offices(s): Savannah River Operations Office August 14, 2012 CX-009118: Categorical Exclusion Determination Sludge Batch 8 Qualification: Washing and Defense Waste Processing Facility

131

Original papers EFFECT OF GLASS-BATCH MAKEUP ON THE MELTING PROCESS  

E-Print Network (OSTI)

The response of a glass batch to heating is determined by the batch makeup and in turn determines the rate of melting. Batches formulated for a high-alumina nuclear waste to be vitrified in an all-electric melter were heated at a constant temperature-increase rate to determine changes in melting behavior in response to the selection of batch chemicals and silica grain-size as well as the addition of heat-generating reactants. The type of batch materials and the size of silica grains determine how much, if any, primary foam occurs during melting. Small quartz grains, 5 µm in size, caused extensive foaming because their major portion dissolved at temperatures 800°C when batch gases no longer evolved. The exothermal reaction of nitrates with sucrose was ignited at a temperature as low as 160°C and caused a temporary jump in temperature of several hundred degrees. Secondary foam, the source of which is oxygen from redox reactions, occurred in all batches of a limited composition variation involving five oxides, B 2O 3, CaO, Li 2O, MgO, and Na 2O. The foam volume at the maximum volume-increase rate was a weak function of temperature and melt basicity. Neither the batch makeup nor the change in glass composition had a significant impact on the dissolution of silica grains. The impacts of primary foam generation on glass homogeneity and the rate of melting in large-scale continuous furnaces have yet to be established via mathematical modeling and melter experiments.

Pavel Hrma; Michael J. Schweiger; Carissa J. Humrickhouse; J. Adam Moody; Rachel M. Tate; Timothy T. Rainsdon; Nathan E. Tegrotenhuis; Benjamin M. Arrigoni; José Marcial; Carmen P. Rodriguez; Benjamin H. Tincher

2010-01-01T23:59:59.000Z

132

Federal involvement in: municipal wastewater treatment plant sludge energy recovery and conservation  

DOE Green Energy (OSTI)

The results are presented of a study concerning federal involvement in municipal wastewater treatment plant (MWWTP) sludge energy recovery and conservation. The objectives of the study were to: determine and report the major agency programs and related MWWTP sludge energy recovery and conservation projects; determine and summarize the coordination efforts between federal agencies involved in MWWTP sludge; and recommend future U.S. Energy Research and Development Administration (ERDA) involvement in MWWTP sludge energy recovery and conservation projects. Specific federal agencies designated for surveying include ERDA, EPA, USDA, Bureau of Mines, National Science Foundation, and National Commission on Water Quality. Past (post-1966), present, and planned federal involvement in MWWTP sludge energy recovery and conservation, research and development, demonstration, and study projects were considered.

None

1977-06-01T23:59:59.000Z

133

Pretreatment of high solid microbial sludges  

DOE Patents (OSTI)

A process and apparatus for pretreating microbial sludges in order to enhance secondary anaerobic digestion. The pretreatment process involves disrupting the cellular integrity of municipal sewage sludge through a combination of thermal, explosive decompression and shear forces. The sludge is pressurized and pumped to a pretreatment reactor where it is mixed with steam to heat and soften the sludge. The pressure of the sludge is suddenly reduced and explosive decompression forces are imparted which partially disrupt the cellular integrity of the sludge. Shear forces are then applied to the sludge to further disrupt the cellular integrity of the sludge. Disrupting cellular integrity releases both soluble and insoluble organic constituents and thereby renders municipal sewage sludge more amenable to secondary anaerobic digestion.

Rivard, Christopher J. (Lakewood, CO); Nagle, Nicholas J. (Broomfield, CO)

1998-01-01T23:59:59.000Z

134

Pretreatment of high solid microbial sludges  

DOE Patents (OSTI)

A process and apparatus are disclosed for pretreating microbial sludges in order to enhance secondary anaerobic digestion. The pretreatment process involves disrupting the cellular integrity of municipal sewage sludge through a combination of thermal, explosive decompression and shear forces. The sludge is pressurized and pumped to a pretreatment reactor where it is mixed with steam to heat and soften the sludge. The pressure of the sludge is suddenly reduced and explosive decompression forces are imparted which partially disrupt the cellular integrity of the sludge. Shear forces are then applied to the sludge to further disrupt the cellular integrity of the sludge. Disrupting cellular integrity releases both soluble and insoluble organic constituents and thereby renders municipal sewage sludge more amenable to secondary anaerobic digestion. 1 fig.

Rivard, C.J.; Nagle, N.J.

1998-07-28T23:59:59.000Z

135

Running Jobs with the UGE Batch System  

NLE Websites -- All DOE Office Websites (Extended Search)

Jobs Jobs Running Jobs Submitting Jobs How to submit your job to the UGE. Read More » Running with Java Solutions to some of the common problems users have with running on Genepool when the JVM is part of their workflow. Read More » Batch Script Examples Sample batch scripts for Genepool/Phoebe highlighting queue selection, setting the run time and requesting large amounts of memory. Read More » Interactive Jobs How to run your workflow on the interactive nodes. Read More » Job Arrays Job arrays are a way to efficiently submit large numbers of jobs. Read More » Parallel Batch Scripts This page has examples of how to run parallel jobs on Genepool. Read More » Best Practices - and Practices to Avoid Things users should do to run jobs efficiently using UGE. Read More »

136

Biological Sludge Reduction and Analysis  

Science Conference Proceedings (OSTI)

This document describes research sponsored by EPRI and Advanced Biological Services (ABS). A series of experiments focused on the reduction and analysis of biological sludge in pulp mill wastewater. The first experiment involved optimization of the milling process through the alteration of the grinding gap and the number of times sludge was passed through the colloid mill in order to affect fractionation, dispersion, and lysis. For the second experiment, tests were conducted to evaluate the effect of ble...

2001-11-07T23:59:59.000Z

137

Mitigation of Hydrogen Gas Generation from the Reaction of Uranium Metal with Water in K Basin Sludge and Sludge Waste Forms  

DOE Green Energy (OSTI)

Prior laboratory testing identified sodium nitrate and nitrite to be the most promising agents to minimize hydrogen generation from uranium metal aqueous corrosion in Hanford Site K Basin sludge. Of the two, nitrate was determined to be better because of higher chemical capacity, lower toxicity, more reliable efficacy, and fewer side reactions than nitrite. The present lab tests were run to determine if nitrate’s beneficial effects to lower H2 generation in simulated and genuine sludge continued for simulated sludge mixed with agents to immobilize water to help meet the Waste Isolation Pilot Plant (WIPP) waste acceptance drainable liquid criterion. Tests were run at ~60°C, 80°C, and 95°C using near spherical high-purity uranium metal beads and simulated sludge to emulate uranium-rich KW containerized sludge currently residing in engineered containers KW-210 and KW-220. Immobilization agents tested were Portland cement (PC), a commercial blend of PC with sepiolite clay (Aquaset II H), granulated sepiolite clay (Aquaset II G), and sepiolite clay powder (Aquaset II). In all cases except tests with Aquaset II G, the simulated sludge was mixed intimately with the immobilization agent before testing commenced. For the granulated Aquaset II G clay was added to the top of the settled sludge/solution mixture according to manufacturer application directions. The gas volumes and compositions, uranium metal corrosion mass losses, and nitrite, ammonia, and hydroxide concentrations in the interstitial solutions were measured. Uranium metal corrosion rates were compared with rates forecast from the known uranium metal anoxic water corrosion rate law. The ratios of the forecast to the observed rates were calculated to find the corrosion rate attenuation factors. Hydrogen quantities also were measured and compared with quantities expected based on non-attenuated H2 generation at the full forecast anoxic corrosion rate to arrive at H2 attenuation factors. The uranium metal corrosion rates in water alone and in simulated sludge were near or slightly below the metal-in-water rate while nitrate-free sludge/Aquaset II decreased rates by about a factor of 3. Addition of 1 M nitrate to simulated sludge decreased the corrosion rate by a factor of ~5 while 1 M nitrate in sludge/Aquaset II mixtures decreased the corrosion rate by ~2.5 compared with the nitrate-free analogues. Mixtures of simulated sludge with Aquaset II treated with 1 M nitrate had uranium corrosion rates about a factor of 8 to 10 lower than the water-only rate law. Nitrate was found to provide substantial hydrogen mitigation for immobilized simulant sludge waste forms containing Aquaset II or Aquaset II G clay. Hydrogen attenuation factors of 1000 or greater were determined at 60°C for sludge-clay mixtures at 1 M nitrate. Hydrogen mitigation for tests with PC and Aquaset II H (which contains PC) were inconclusive because of suspected failure to overcome induction times and fully enter into anoxic corrosion. Lessening of hydrogen attenuation at ~80°C and ~95°C for simulated sludge and Aquaset II was observed with attenuation factors around 100 to 200 at 1 M nitrate. Valuable additional information has been obtained on the ability of nitrate to attenuate hydrogen gas generation from solution, simulant K Basin sludge, and simulant sludge with immobilization agents. Details on characteristics of the associated reactions were also obtained. The present testing confirms prior work which indicates that nitrate is an effective agent to attenuate hydrogen from uranium metal corrosion in water and simulated K Basin sludge to show that it is also effective in potential candidate solidified K Basin waste forms for WIPP disposal. The hydrogen mitigation afforded by nitrate appears to be sufficient to meet the hydrogen generation limits for shipping various sludge waste streams based on uranium metal concentrations and assumed waste form loadings.

Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.

2011-06-08T23:59:59.000Z

138

Ferrocyanide safety program: An assessment of the possibility of ferrocyanide sludge dryout  

Science Conference Proceedings (OSTI)

Much attention has been focused on the Hanford Site radioactive waste storage tanks as a results of problems that have been envisioned for them. One problem is the potential chemical reaction between ferrocyanide precipitate particles and nitrates in the absence of water. This report addresses the question of whether dryout of a portion of ferrocyanide sludge would render it potentially reactive. Various sludge dryout mechanisms were examined to determine if any of them could occur. The mechanisms are: (1) bulk heating of the entire sludge inventory to its boiling point; (2) loss of liquid to the atmosphere via sludge surface evaporation; (3) local drying by boiling in a hot spot region; (4) sludge drainage through a leak in the tank wall; and (5) local drying by evaporation from a warm segment of surface sludge. From the simple analyses presented in this report and more detailed published analyses, it is evident that global loss of water from bulk heating of the sludge to its boiling point or from surface evaporation and vapor transport to the outside air is not credible. Also, from the analyses presented in this report and experimental and analytical work presented elsewhere, it is evident that formation of a dry local or global region of sludge as a result of tank leakage (draining of interstitial liquid) is not possible. Finally, and most importantly, it is concluded that formation of dry local regions in the ferrocyanide sludge by local hot spots or warm surface regions is not possible. The conclusion that local or global dryout is incredible is consistent with four decades of waste storage history, during which sludge temperature have gradually decreased or remained constant and the sludge moisture content has been retained. 54 refs.

Epstein, M.; Fauske, H.K. [Fauske and Associates, Inc., Burr Ridge, IL (United States); Dickinson, D.R.; Crippen, M.D.; McCormack, J.D.; Cash, R.J.; Meacham, J.E. [Westinghouse Hanford Co., Richland, WA (United States); Simmons, C.S. [Pacific Northwest Lab., Richland, WA (United States)

1994-09-01T23:59:59.000Z

139

Computer modeling of ORNL storage tank sludge mobilization and mixing  

SciTech Connect

This report presents and analyzes the results of the computer modeling of mixing and mobilization of sludge in horizontal, cylindrical storage tanks using submerged liquid jets. The computer modeling uses the TEMPEST computational fluid dynamics computer program. The horizontal, cylindrical storage tank configuration is similar to the Melton Valley Storage Tanks (MVST) at Oak Ridge National (ORNL). The MVST tank contents exhibit non-homogeneous, non-Newtonian rheology characteristics. The eventual goals of the simulations are to determine under what conditions sludge mobilization using submerged liquid jets is feasible in tanks of this configuration, and to estimate mixing times required to approach homogeneity of the contents of the tanks.

Terrones, G.; Eyler, L.L.

1993-09-01T23:59:59.000Z

140

IMPACT OF IRRADIATION AND THERMAL AGING ON DWPF SIMULATED SLUDGE PROPERTIES  

Science Conference Proceedings (OSTI)

The research and development programs in support of the Defense Waste Processing Facility (DWPF) and other high-level waste vitrification processes require the use of both nonradioactive waste simulants and actual waste samples. While actual waste samples are the ideal materials to study, acquiring large quantities of actual waste is difficult and expensive. Tests utilizing actual high-level waste require the use of expensive shielded cells facilities to provide sufficient shielding for the researchers. Nonradioactive waste simulants have been used for laboratory testing, pilot-scale testing and full-scale integrated facility testing. These waste simulants were designed to reproduce the chemical and, if possible, the physical properties of the actual high-level waste. This technical report documents a study on the impact of irradiating a Sludge Batch 3 (SB3) simulant and of additional tests on aging a SB3 simulant by additional thermal processing. Prior simulant development studies examined methods of producing sludge and supernate simulants and processes that could be used to alter the physical properties of the simulant to more accurately mimic the properties of actual waste. Development of a precipitated sludge simulant for the River Protection Project (RPP) demonstrated that the application of heat for a period of time could significantly alter the rheology of the sludge simulant. The RPP precipitated simulant used distillation to concentrate the sludge solids and produced a reduction in sludge yield stress of up to 80% compared to the initial sludge properties. Observations at that time suggested that a substantial fraction of the iron hydroxide had converted to the oxide during the distillation. DWPF sludge simulant studies showed a much smaller reduction in yield stress ({approx}10%), demonstrated the impact of shear on particle size, and showed that smaller particle sizes yielded higher yield stress products. The current study documented in this report focuses on the SB3 sludge composition and recipe developed during the previous year as part of the simulant development program. The study examines the impact of a rapid dose of radiation on the physical properties of the SB3 simulant, the effect of temperature and time on the application of heat as a simulant aging mechanism, and the application of crossflow filtration to the production of an all-metals-precipitated SB3 sludge simulant.

Eibling, R; Michael Stone, M

2006-10-16T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Batch Preheat for glass and related furnace processing operations  

SciTech Connect

The objectives that our development work addressed are: (1) Establish through lab tests a salt eutectic with a melting point of about 250 F and a working range of 250 to 1800 F. (2) Establish the most economical material of construction for the screened salt eutectics identified in the first objective. (3) Establish the material of construction for the salt heater liner. Objectives 2 and 3 were determined through corrosion tests using selected metallurgical samples. Successful completion of the above-stated goals will be incorporated in a heat recovery design that can be used in high temperature processes and furnaces, typical of which is the glass melting process. The process design incorporates the following unit operations: a vertical batch heater (whereby the batch flows down through tubes in a shell and tube exchanger; a molten salt eutectic is circulated on the shell side); a molten salt heater utilizing furnace flue gas in a radiation type heater (molten salt is circulated in the annular space between the inner and outer shells of the vertical heater, and flue gas passes from the furnace exhaust through the inner shell of the heater); a cantilever type molten salt circulating pump; and a jacketed mixer/conveyor to drive off moisture from the batch prior to feeding the batch to the vertical batch heater. Historically, radiation heaters, when applied to glass or fiberglass furnace recuperation, have experienced failures due to uneven heat flux rates, which increases internal stresses and spot overheating conditions. Low heat transfer coefficients result in requirements for large heat transfer surface areas in gas to gas or gas to air exchangers. Fouling is another factor that results in lower unit availability and reduced performance. These factors are accommodated in this process by the incorporation of several design features. The salt heater will be a vertical double wall radiation design, similar to radiation air heaters used in high temperature heat recovery. The unit utilizes an inner shell that the furnace exhaust gas passes through: this provides essentially a self-cleaning surface. Utilization of radiation air heaters in fiberglass furnaces has demonstrated that the inner shell provides a surface from which molten ash can drain down. The molten salt eutectic will be pumped through the annulus between this inner wall and the outer wall of the unit. The annular space tempering via the molten salt will promote more uniform expansion for the unit, and thereby promote more uniform heat flux rates. Heat transfer would be via radiation mainly, with a minor convective contributor.

Energy & Environmental Resources, Inc

2002-08-12T23:59:59.000Z

142

Wastewater sludge management options for Honduras  

E-Print Network (OSTI)

Sludge management is a fundamental area of concern across wastewater treatment systems in Honduras. The lack of timely sludge removal has led to declining plant performance in many facilities throughout the country. In ...

Bhattacharya, Mahua, M. Eng. Massachusetts Institute of Technology.

2009-01-01T23:59:59.000Z

143

Laser removal of sludge from steam generators  

SciTech Connect

A method of removing unwanted chemical deposits known as sludge from the metal surfaces of steam generators with laser energy is provided. Laser energy of a certain power density, of a critical wavelength and frequency, is intermittently focused on the sludge deposits to vaporize them so that the surfaces are cleaned without affecting the metal surface (sludge substrate). Fiberoptic tubes are utilized for laser beam transmission and beam direction. Fiberoptics are also utilized to monitor laser operation and sludge removal.

Nachbar, Henry D. (Ballston Lake, NY)

1990-01-01T23:59:59.000Z

144

HIGH LEVEL WASTE MECHANCIAL SLUDGE REMOVAL AT THE SAVANNAH RIVER SITE F TANK FARM CLOSURE PROJECT  

SciTech Connect

The Savannah River Site F-Tank Farm Closure project has successfully performed Mechanical Sludge Removal (MSR) using the Waste on Wheels (WOW) system for the first time within one of its storage tanks. The WOW system is designed to be relatively mobile with the ability for many components to be redeployed to multiple waste tanks. It is primarily comprised of Submersible Mixer Pumps (SMPs), Submersible Transfer Pumps (STPs), and a mobile control room with a control panel and variable speed drives. In addition, the project is currently preparing another waste tank for MSR utilizing lessons learned from this previous operational activity. These tanks, designated as Tank 6 and Tank 5 respectively, are Type I waste tanks located in F-Tank Farm (FTF) with a capacity of 2,840 cubic meters (750,000 gallons) each. The construction of these tanks was completed in 1953, and they were placed into waste storage service in 1959. The tank's primary shell is 23 meters (75 feet) in diameter, and 7.5 meters (24.5 feet) in height. Type I tanks have 34 vertically oriented cooling coils and two horizontal cooling coil circuits along the tank floor. Both Tank 5 and Tank 6 received and stored F-PUREX waste during their operating service time before sludge removal was performed. DOE intends to remove from service and operationally close (fill with grout) Tank 5 and Tank 6 and other HLW tanks that do not meet current containment standards. Mechanical Sludge Removal, the first step in the tank closure process, will be followed by chemical cleaning. After obtaining regulatory approval, the tanks will be isolated and filled with grout for long-term stabilization. Mechanical Sludge Removal operations within Tank 6 removed approximately 75% of the original 95,000 liters (25,000 gallons). This sludge material was transferred in batches to an interim storage tank to prepare for vitrification. This operation consisted of eleven (11) Submersible Mixer Pump(s) mixing campaigns and multiple intraarea transfers utilizing STPs from July 2006 to August 2007. This operation and successful removal of sludge material meets requirement of approximately 19,000 to 28,000 liters (5,000 to 7,500 gallons) remaining prior to the Chemical Cleaning process. Removal of the last 35% of sludge was exponentially more difficult, as less and less sludge was available to mobilize and the lighter sludge particles were likely removed during the early mixing campaigns. The removal of the 72,000 liters (19,000 gallons) of sludge was challenging due to a number factors. One primary factor was the complex internal cooling coil array within Tank 6 that obstructed mixer discharge jets and impacted the Effective Cleaning Radius (ECR) of the Submersible Mixer Pumps. Minimal access locations into the tank through tank openings (risers) presented a challenge because the available options for equipment locations were very limited. Mechanical Sludge Removal activities using SMPs caused the sludge to migrate to areas of the tank that were outside of the SMP ECR. Various SMP operational strategies were used to address the challenge of moving sludge from remote areas of the tank to the transfer pump. This paper describes in detail the Mechanical Sludge Removal activities and mitigative solutions to cooling coil obstructions and other challenges. The performance of the WOW system and SMP operational strategies were evaluated and the resulting lessons learned are described for application to future Mechanical Sludge Removal operations.

Jolly, R; Bruce Martin, B

2008-01-15T23:59:59.000Z

145

Please use "gres" settings in your batch scripts  

NLE Websites -- All DOE Office Websites (Extended Search)

Please use "gres" settings in your batch scripts Please use "gres" settings in your batch scripts September 4, 2012 by Helen He (0 Comments) We would like to encourage you to use...

146

Anaerobic digestion of industrial activated aerobic sludge  

Science Conference Proceedings (OSTI)

The Tennessee Eastman Company manufactures a variety of organic chemicals, plastics and fibers at their Kingsport Tennessee Facility. The wastewater generated during the manufacture of these compounds is currently treated using an activated sludge process. The objective of the project is to evaluate the economic potential of an anaerobic digestion process to convert industrial sludge at the Tennessee Eastman Company into biogas. The evaluation will require collection and analysis of experimental data on the anaerobic digestion of industrial sludge obtained from Kingsport. Although the experiments will be conducted using Tennessee Eastman sludge, these results should be also generally applicable to similar industrial sludge.

Goodloe, J.G.; Roberts, R.S.

1990-04-01T23:59:59.000Z

147

Sewage Sludge (Maryland) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sewage Sludge (Maryland) Sewage Sludge (Maryland) Sewage Sludge (Maryland) < Back Eligibility Agricultural Commercial Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Systems Integrator Tribal Government Utility Program Info State Maryland Program Type Siting and Permitting Provider Maryland Department of the Environment Sewage sludge utilization permits are required prior to the use, processing, and disposal of sewage sludge in Maryland. Sewage sludge (also known as biosolids) is not sewage, but rather is one of the final products of treated sewage at a sewage (wastewater) treatment plant. Sewage sludge is the fine particulate matter remaining after treatment which breaks down organic matter and destroys disease organisms in sewage. A SSU Permit is required for any person who collects,

148

Selenite Reduction by a Denitrifying Culture: Batch- and Packed-Bed- Reactor Studies  

SciTech Connect

Selenite reduction by a bacterial consortium enriched from an oil refinery waste sludge was studied under denitrifying conditions using acetate as the electron donor. Fed-batch studies with nitrate as the primary electron acceptor showed that accumulation of nitrite led to a decrease in the extent of selenite reduction. Also, when nitrite was added as the primary electron acceptor, rapid selenite reduction was observed only after nitrite was significantly depleted from the medium. These results indicate that selenite reduction was inhibited at high nitrite concentrations. In addition to batch experiments, continuous flow selenite reduction experiments were performed in packed-bed columns using immobilized enrichment cultures. These experiments were carried out in three phases: In phase-I, a continuous nitrate feed with different inlet selenite concentration was applied; in phase-II, nitrate was fed in a pulsed fashion; and in phase-III, nitrate was fed in a continuous mode but at much lower concentrations than the other two phases. During the phase-I experiments, little selenite was removed from the influent. However, when the column was operated in the pulse feed strategy (phase II), or in the continuous mode with low nitrate levels (phase-III), significant quantities of selenium was removed from solution and retained in the immobilization matrix in the column. Thus, immobilized denitrifying cultures can be effective in removing selenium from waste streams, but nitrate-limited operating conditions might be required.

William A. Apel; Sridhar Viamajala; Yared Bereded-Samuel; James N. Petersen

2006-08-01T23:59:59.000Z

149

Thermal sludge dryer demonstration: Bird Island Wastewater Treatment Plant, Buffalo, NY. Final report  

DOE Green Energy (OSTI)

The Buffalo Sewer Authority (BSA), in cooperation with the New York State Energy Research and Development Authority (Energy Authority), commissioned a demonstration of a full scale indirect disk-type sludge dryer at the Bird Island Wastewater Treatment Plant (BIWWTP). The purpose of the project was to determine the effects of the sludge dryer on the sludge incineration process at the facility. Sludge incineration is traditionally the most expensive, energy-intensive unit process involving solids handling at wastewater treatment plants; costs for incineration at the BIWWTP have averaged $2.4 million per year. In the conventional method of processing solids, a series of volume reduction measures, which usually includes thickening, digestion, and mechanical dewatering, is employed prior to incineration. Usually, a high level of moisture is still present within sewage sludge following mechanical dewatering. The sludge dryer system thermally dewaters wastewater sludge to approximately 26%, (and as high as 38%) dry solids content prior to incineration. The thermal dewatering system at the BIWWTP has demonstrated that it meets its design requirements. It has the potential to provide significant energy and other cost savings by allowing the BSA to change from an operation employing two incinerators to a single incinerator mode. While the long-term reliability of the thermal dewatering system has yet to be established, this project has demonstrated that installation of such a system in an existing treatment plant can provide the owner with significant operating cost savings.

NONE

1995-01-01T23:59:59.000Z

150

Clay-sewage sludge co-pyrolysis. A TG-MS and Py-GC study on potential advantages afforded by the presence of clay in the pyrolysis of wastewater sewage sludge  

Science Conference Proceedings (OSTI)

Wastewater sewage sludge was co-pyrolyzed with a well characterized clay sample, in order to evaluate possible advantages in the thermal disposal process of solid waste. Characterization of the co-pyrolysis process was carried out both by thermogravimetric-mass spectrometric (TG-MS) analysis, and by reactor tests, using a lab-scale batch reactor equipped with a gas chromatograph for analysis of the evolved gas phase (Py-GC). Due to the presence of clay, two main effects were observed in the instrumental characterization of the process. Firstly, the clay surface catalyzed the pyrolysis reaction of the sludge, and secondly, the release of water from the clay, at temperatures of approx. 450-500 deg. C, enhanced gasification of part of carbon residue of the organic component of sludge following pyrolysis. Moreover, the solid residue remaining after pyrolysis process, composed of the inorganic component of sludge blended with clay, is characterized by good features for possible disposal by vitrification, yielding a vitreous matrix that immobilizes the hazardous heavy metals present in the sludge.

Ischia, Marco, E-mail: marco.ischia@ing.unitn.it [Department of Materials Engineering and Industrial Technologies, University of Trento, via Mesiano 77, 38100 Trento (Italy); Maschio, Roberto Dal [Department of Materials Engineering and Industrial Technologies, University of Trento, via Mesiano 77, 38100 Trento (Italy); Grigiante, Maurizio [Department of Civil and Environmental Engineering, University of Trento, via Mesiano 77, 38100 Trento (Italy); Baratieri, Marco [Faculty of Science and Technology, Free University of Bolzano, Piazza Universita 5, 39100 Bolzano (Italy)

2011-01-15T23:59:59.000Z

151

Criticality safety evaluation of disposing of K Basin sludge in double-shell tank AW-105  

SciTech Connect

A criticality safety evaluation is made of the disposal of K Basin sludge in double-shell tank (DST) AW-105 located in the 200 east area of Hanford Site. The technical basis is provided for limits and controls to be used in the development of a criticality prevention specification (CPS). A model of K Basin sludge is developed to account for fuel burnup. The iron/uranium mass ration required to ensure an acceptable magrin of subcriticality is determined.

ROGERS, C.A.

1999-06-04T23:59:59.000Z

152

CX-009623: Categorical Exclusion Determination | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Categorical Exclusion Determination CX-009623: Categorical Exclusion Determination Technetium Precipitation Batch Testing CX(s) Applied: B3.6 Date: 10312012 Location(s): South...

153

Proceedings: Steam Generator Sludge Management Workshop  

Science Conference Proceedings (OSTI)

A total of 151 individuals attended the Steam Generator Sludge Management Workshop. They represented domestic and foreign utilities, vendors, individuals from government laboratories, university members, EPRI employees. Presentations from utilities and vendors focused on overall control and management of generator sludge which covered several topics. A poster session included presentations on minimizing and characterizing sludge as well as a demonstration of a thermal hydraulic and fouling analysis works...

1995-12-08T23:59:59.000Z

154

Separating lignite hydrogenation sludge by vacuum distillation  

SciTech Connect

Vacuum distillation was studied as a means to separate coal hydrogenation sludge. Additives containing mainly aromatic hydrocarbons intensified the process. 4 refs., 2 figs., 5 tabs.

Gorlov, E.G.; Grobanova, L.T.; Belyavtseva, N.V. [Rossiskaya Akademiya, Nauk (Russian Federation)

1994-12-31T23:59:59.000Z

155

Hanford Sludge Treatment Project, August 2011  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Safety and Emergency Management Evaluations Activity Report for the Sludge Treatment Project Dates of Activity : 08222011 - 08252011 Report Preparer: Jake...

156

Effect Of Batch Charging Equipment On Glass Furnace Efficiency  

Science Conference Proceedings (OSTI)

This paper investigates the effects of batch pattern in the melt space caused by charging equipment on the energy efficiency of the furnace focusing on the ...

157

Exploration of supercritical water gasification of biomass using batch reactor .  

E-Print Network (OSTI)

??The focus of this study is on gasification of a biomass in supercritical water. Vapor mass yield in a batch reactor after 20 minutes in… (more)

Venkitasamy, Chandrasekar

2011-01-01T23:59:59.000Z

158

Better Mini-Batch Algorithms via Accelerated Gradient Methods  

E-Print Network (OSTI)

Better Mini-Batch Algorithms via Accelerated Gradient Methods Andrew Cotter Toyota Technological Toyota Technological Institute at Chicago nati@ttic.edu Karthik Sridharan Toyota Technological Institute

159

Batch Queue Configuration and Policies on Franklin  

NLE Websites -- All DOE Office Websites (Extended Search)

Queues and Policies Queues and Policies Queues and Policies Queues and Job Scheduling Jobs must be submitted to a valid Submit Queue. Upon submission the job is routed to the appropriate Torque execution class. Users can not directly access the Torque execution classes. Submit Queue Execution Queue (Do not use in batch script) Nodes Available Processors Max Wallclock Relative Priority (1 being the highest) Run Limit Queued Limit (eligible to run limit) Queue Charge Factor xfer xfer 1 4 6 hrs 3 3 2 1 interactive interactive 1-128 1-512 30 mins 1 1 1 1 debug debug 1-512 1-2,048 30 mins 2 1 1 1 premium premium 1-4,096 1-16,384 24 hrs 4 2 2 2 regular reg_short 1-511 1-2,044 6 hrs 7 12 8 1 reg_small 1-255 1-1,020 48 hrs 7 7 3 1

160

Reducing variance in batch partitioning measurements  

SciTech Connect

The partitioning experiment is commonly performed with little or no attention to reducing measurement variance. Batch test procedures such as those used to measure K{sub d} values (e.g., ASTM D 4646 and EPA402 -R-99-004A) do not explain how to evaluate measurement uncertainty nor how to minimize measurement variance. In fact, ASTM D 4646 prescribes a sorbent:water ratio that prevents variance minimization. Consequently, the variance of a set of partitioning measurements can be extreme and even absurd. Such data sets, which are commonplace, hamper probabilistic modeling efforts. An error-savvy design requires adjustment of the solution:sorbent ratio so that approximately half of the sorbate partitions to the sorbent. Results of Monte Carlo simulations indicate that this simple step can markedly improve the precision and statistical characterization of partitioning uncertainty.

Mariner, Paul E.

2010-08-11T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Enhanced Ethanol Production from De-Ashed Paper Sludge by Simultaneous Saccharification and Fermentation and Simultaneous Saccharification and Co-Fermentation  

Science Conference Proceedings (OSTI)

A previous study demonstrated that paper sludges with high ash contents can be converted to ethanol by simultaneous saccharification and fermentation (SSF) or simultaneous saccharification and co-fermentation (SSCF). High ash content in the sludge, however, limited solid loading in the bioreactor, causing low product concentration. To overcome this problem, sludges were de-ashed before SSF and SSCF. Low ash content in sludges also increased the ethanol yield to the extent that the enzyme dosage required to achieve 70% yield in the fermentation process was reduced by 30%. High solid loading in SSF and SSCF decreased the ethanol yield. High agitation and de-ashing of the sludges were able to restore the part of the yield loss caused by high solid loading. Substitution of the laboratory fermentation medium (peptone and yeast extract) with corn steep liquor did not bring about any adverse effects in the fermentation. Fed-batch operation of the SSCF and SSF using low-ash content sludges was effective in raising the ethanol concentration, achieving 47.8 g/L and 60.0 g/L, respectively.

Kang, L.; Wang, W.; Pallapolu, V. R.; Lee, Y. Y.

2011-11-01T23:59:59.000Z

162

DESTRUCTION OF TETRAPHENYLBORATE IN TANK 48H USING WET AIR OXIDATION BATCH BENCH SCALE AUTOCLAVE TESTING WITH ACTUAL RADIOACTIVE TANK 48H WASTE  

DOE Green Energy (OSTI)

Wet Air Oxidation (WAO) is one of the two technologies being considered for the destruction of Tetraphenylborate (TPB) in Tank 48H. Batch bench-scale autoclave testing with radioactive (actual) Tank 48H waste is among the tests required in the WAO Technology Maturation Plan. The goal of the autoclave testing is to validate that the simulant being used for extensive WAO vendor testing adequately represents the Tank 48H waste. The test objective was to demonstrate comparable test results when running simulated waste and real waste under similar test conditions. Specifically: (1) Confirm the TPB destruction efficiency and rate (same reaction times) obtained from comparable simulant tests, (2) Determine the destruction efficiency of other organics including biphenyl, (3) Identify and quantify the reaction byproducts, and (4) Determine off-gas composition. Batch bench-scale stirred autoclave tests were conducted with simulated and actual Tank 48H wastes at SRNL. Experimental conditions were chosen based on continuous-flow pilot-scale simulant testing performed at Siemens Water Technologies Corporation (SWT) in Rothschild, Wisconsin. The following items were demonstrated as a result of this testing. (1) Tetraphenylborate was destroyed to below detection limits during the 1-hour reaction time at 280 C. Destruction efficiency of TPB was > 99.997%. (2) Other organics (TPB associated compounds), except biphenyl, were destroyed to below their respective detection limits. Biphenyl was partially destroyed in the process, mainly due to its propensity to reside in the vapor phase during the WAO reaction. Biphenyl is expected to be removed in the gas phase during the actual process, which is a continuous-flow system. (3) Reaction byproducts, remnants of MST, and the PUREX sludge, were characterized in this work. Radioactive species, such as Pu, Sr-90 and Cs-137 were quantified in the filtrate and slurry samples. Notably, Cs-137, boron and potassium were shown as soluble as a result of the WAO reaction. (4) Off-gas composition was measured in the resulting gas phase from the reaction. Benzene and hydrogen were formed during the reaction, but they were reasonably low in the off-gas at 0.096 and 0.0063 vol% respectively. Considering the consistency in replicating similar test results with simulated waste and Tank 48H waste under similar test conditions, the results confirm the validity of the simulant for other WAO test conditions.

Adu-Wusu, K; Paul Burket, P

2009-03-31T23:59:59.000Z

163

Co-digestion of sewage sludge with glycerol to boost biogas production  

Science Conference Proceedings (OSTI)

The feasibility of adding crude glycerol from the biodiesel industry to the anaerobic digesters treating sewage sludge in wastewater treatment plants was studied in both batch and continuous experiments at 35 {sup o}C. Glycerol addition can boost biogas yields, if it does not exceed a limiting 1% (v/v) concentration in the feed. Any further increase of glycerol causes a high imbalance in the anaerobic digestion process. The reactor treating the sewage sludge produced 1106 {+-} 36 ml CH{sub 4}/d before the addition of glycerol and 2353 {+-} 94 ml CH{sub 4}/d after the addition of glycerol (1% v/v in the feed). The extra glycerol-COD added to the feed did not have a negative effect on reactor performance, but seemed to increase the active biomass (volatile solids) concentration in the system. Batch kinetic experiments showed that the maximum specific utilization rate ({mu}{sub max}) and the saturation constant (K{sub S}) of glycerol were 0.149 {+-} 0.015 h{sup -1} and 0.276 {+-} 0.095 g/l, respectively. Comparing the estimated values with the kinetics constants for propionate reported in the literature, it can be concluded that glycerol uptake is not the rate-limiting step during the process.

Fountoulakis, M.S., E-mail: mfountoul@steg.teiher.g [School of Agricultural Technology, Technological Educational Institute of Crete, Heraklion (Greece); Petousi, I.; Manios, T. [School of Agricultural Technology, Technological Educational Institute of Crete, Heraklion (Greece)

2010-10-15T23:59:59.000Z

164

Sewage sludge dewatering using flowing liquid metals  

DOE Patents (OSTI)

This invention relates generally to the dewatering of sludge, and more particularly to the dewatering of a sewage sludge having a moisture content of about 50 to 80% in the form of small cellular micro-organism bodies having internally confined water.

Carlson, L.W.

1985-08-30T23:59:59.000Z

165

Disposable sludge dewatering container and method  

DOE Patents (OSTI)

This invention is comprised of a device and method for preparing sludge for disposal comprising a box with a thin layer of gravel on the bottom and a thin layer of sand on the gravel layer, an array of perforated piping deployed throughout the gravel layer, and a sump in the gravel layer below the perforated piping array. Standpipes connect the array and sump to an external ion exchanger/fine particulate filter and a pump. Sludge is deposited on the sand layer and dewatered using a pump connected to the piping array, topping up with more sludge as the aqueous component of the sludge is extracted. When the box is full and the free standing water content of the sludge is acceptable, the standpipes are cut and sealed and the lid secured to the box.

Cole, C.M.

1990-12-27T23:59:59.000Z

166

Washing and caustic leaching of Hanford Tank C-106 sludge  

Science Conference Proceedings (OSTI)

This report describes the results of a laboratory-scale washing and caustic leaching test performed on sludge from Hanford Tank C-106. The purpose of this test was to determine the behavior of important sludge components when subjected to washing with dilute or concentrated sodium hydroxide solutions. The results of this laboratory-scale test were used to support the design of a bench-scale washing and leaching process used to prepare several hundred grams of high-level waste solids for vitrification tests to be done by private contractors. The laboratory-scale test was conducted at Pacific Northwest Laboratory in FY 1996 as part of the Hanford privatization effort. The work was funded by the US Department of Energy through the Tank Waste Remediation System (TWRS; EM-30).

Lumetta, G.J.; Wagner, M.J.; Hoopes, F.V.; Steele, R.T.

1996-10-01T23:59:59.000Z

167

Explicit control a batch-aware distributed file system  

Science Conference Proceedings (OSTI)

We present the design, implementation, and evaluation of the Batch-Aware Distributed File System (BAD-FS), a system designed to orchestrate large, I/O-intensive batch workloads on remote computing clusters distributed across the wide area. BAD-FS consists ...

John Bent; Douglas Thain; Andrea C. Arpaci-Dusseau; Remzi H. Arpaci-Dusseau; Miron Livny

2004-03-01T23:59:59.000Z

168

Heuristic batching policies for video-on-demand services  

Science Conference Proceedings (OSTI)

A video-on-demand (VOD) service imposes extremely severe resource requirement in terms of bandwidth and storage. Batching policies that use a single channel to serve multiple active clients for the same video program can reduce system resource requirement ... Keywords: Batching policy, Channel allocation, Instantaneous MFQL, Maximum factored queue length, Rate-based, Regular-interval, Statistical MFQL

J.-K Chen; J. -L. C Wu

1999-08-01T23:59:59.000Z

169

SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING  

DOE Green Energy (OSTI)

This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be released. Installation requirements were also determined for a transfer pump which will remove tank contents, and which is also required to not disturb sludge. Testing techniques and test results for both types of pumps are presented.

Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

2011-01-12T23:59:59.000Z

170

Independent Oversight Activity Report, Hanford Sludge Treatment Project -  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sludge Treatment Sludge Treatment Project - September 2013 Independent Oversight Activity Report, Hanford Sludge Treatment Project - September 2013 November 2013 Hanford Sludge Treatment Project Engineered Container Retrieval and Transfer System Operational Awareness Review and Sludge Treatment Project Independent Project Review [HIAR-RL-2013-09-18] This Independent Oversight Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations on September 17-18, 2013, at the Hanford Sludge Treatment Project. The activity consisted of HSS staff performing an operational awareness review of the Sludge Treatment Project (STP) Engineered Container Retrieval and Transfer System. An HSS

171

Tabu search heuristic for two-machine flowshop with batch processing machines  

Science Conference Proceedings (OSTI)

Batch processing machines are frequently encountered in many industrial environments. A batch processing machine is one which can process several jobs simultaneously as a batch. The processing time of a batch is equal to the largest processing time of ... Keywords: Batch processing machines, Flowshop, MILP model, Tabu search

Li-Man Liao; Ching-Jen Huang

2011-04-01T23:59:59.000Z

172

Batch leaching tests: Colloid release and PAH leachability  

Science Conference Proceedings (OSTI)

The Toxicity Characteristic Leaching Procedure (TCLP) was developed by the U.S. Environmental Protection Agency to assess leaching potential of contaminants from waste, and to provide a test to classify, hazardous waste. It is a batch leaching test where a waste (such as contaminated soil) and an extraction fluid are agitated for a predetermined time. Since TCLP employs an aggressive mixing technique, it is possible that hydrophobic contaminant-laden colloidal fractions may appear as 'dissolved' constituents. In this study, TCLP was employed to determine the leachability of PAH contamination from a coal tar contaminated site. Generated colloids and the apparent aqueous concentrations of naphthalene and phenanthrene were measured at various mixing times in the extraction fluid. A mathematical model was developed that predicted the apparent aqueous contaminant concentration in the filtrate. This model accounted for the presence of colloids in the filtrate, and quantified contaminant desorption from colloids. The fraction of colloid-bound contaminant was predicted to be negligible for naphthalene. However, phenanthrene was predicted to have a significant fraction of the total contaminant in the colloidal phase, while naphthalene was primarily dissolved. The desorption model and PAH desorption data are presented here to determine the extent of colloid-facilitated desorption during leaching tests.

Bergendahl, J. [Worcester Polytechnique Institute, Worcester, MA (United States). Dept. of Civil & Environmental Engineering

2005-07-01T23:59:59.000Z

173

In-Situ Characterization of Underwater Radioactive Sludge  

Science Conference Proceedings (OSTI)

A fundamental requirement underpinning safe clean-up technologies for legacy spent nuclear fuel (SNF) ponds, pools and wet silos is the ability to characterize the radioactive waste form prior to retrieval. The corrosion products resulting from the long term underwater storage of spent nuclear fuel, reactor components and reprocessing debris present a major hazard to facility decontamination and decommissioning in terms of their radioactive content and physical / chemical reactivity. The ability to perform in-situ underwater non-destructive characterization of sludge and debris in a safe and cost-effective manner offers significant benefits over traditional destructive sampling methods. Several techniques are available for underwater measurements including (i) Gross gamma counting, (ii) Low-, Medium- and High- Resolution Gamma Spectroscopy, (iii) Passive neutron counting and (iv) Active Neutron Interrogation. The optimum technique depends on (i) the radioactive inventory (ii) mechanical access restrictions for deployment of the detection equipment, interrogation sources etc. (iii) the integrity of plant records and (iv) the extent to which Acceptable Knowledge which may be used for 'fingerprinting' the radioactive contents to a marker nuclide. Prior deployments of underwater SNF characterization equipment around the world have been reviewed with respect to recent developments in gamma and neutron detection technologies, digital electronics advancements, data transfer techniques, remote operation capabilities and improved field ruggedization. Modeling and experimental work has been performed to determine the capabilities, performance envelope and operational limitations of the future generation of non-destructive underwater sludge characterization techniques. Recommendations are given on the optimal design of systems and procedures to provide an acceptable level of confidence in the characterization of residual sludge content of legacy wet storage facilities such that retrieval and repackaging of SNF sludges may proceed safely and efficiently with support of the regulators and the public. (author)

Simpson, A.P.; Clapham, M.J.; Swinson, B. [Pajarito Scientific Corp., Santa Fe, NM (United States)

2008-07-01T23:59:59.000Z

174

Updated Volumetric Expansion Factors for K Basin Sludge During Storage  

SciTech Connect

Sludge has accumulated in the K East (KE) and K West (KW) Basins at the Hanford Site. This sludge contains metallic uranium and uranium oxides that will corrode, hydrate, and generate and consume gases during containerized storage. From these corrosion reactions, two sludge expansion mechanisms can be expected: 1) expansion of the volume of the sludge solids from the generation of corrosion oxidation products that occupy more space than the starting-state sludge; and 2) expansion of the bulk sludge volume from the retention of hydrogen gas bubbles. This report provides a review and updated projections of the volumetric expansion occurring due to corrosion and gas retention during the containerized storage of K Basin sludge. New design and safety basis volume expansion values are provided for the following sludge streams: KW Floor, KW North Loadout Pit, KW canister, and fuel piece sludge.

Schmidt, Andrew J. (BATTELLE (PACIFIC NW LAB)); Delegard, Calvin H. (BATTELLE (PACIFIC NW LAB))

2003-03-14T23:59:59.000Z

175

Thermal Conductivity and Shear Strength of K Basin Sludge  

DOE Green Energy (OSTI)

Hanford K Basin sludge contains metallic uranium and uranium oxides that will corrode, hydrate, and, consequently, generate heat and hydrogen gas during storage. Heat is generated within the K Basin sludge by radiolytic decay and the reaction of uranium metal with water. To maintain thermal stability, the sludge must be retrieved, staged, transported, and stored in systems designed to provide a rate of heat removal that prevents the temperature in the sludge from increasing beyond acceptable limits. To support the dispositioning of the sludge to T Plant, modeling and testing and analyses are being performed to predict the behavior of sludge when placed into the storage containers. Two physical properties of the sludge that are critical to the modeling and analyses efforts are thermal conductivity and the sludge shear strength (yield stress). This report provides the results of thermal conductivity and shear strength measurements performed on representative sludge samples from the K East Basin.

Poloski, Adam P. (BATTELLE (PACIFIC NW LAB)); Bredt, Paul R. (BATTELLE (PACIFIC NW LAB)); Schmidt, Andrew J. (BATTELLE (PACIFIC NW LAB)); Swoboda, Robert G. (BATTELLE (PACIFIC NW LAB)); Chenault, Jeffrey W. (BATTELLE (PACIFIC NW LAB)); Gano, Sue (BATTELLE (PACIFIC NW LAB))

2002-05-17T23:59:59.000Z

176

SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY  

Science Conference Proceedings (OSTI)

The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is dependent on the confidence that DOE has in the long term mission for T Plant, is proposed: (1) If the confidence level in a durable, extended T Plant mission independent of sludge storage is high, then the Sludge Treatment Project (STP) would continue to implement the path forward previously described in the Alternatives Report (HNF-39744). Risks to the sludge project can be minimized through the establishment of an Interface Control Document (ICD) defining agreed upon responsibilities for both the STP and T Plant Operations regarding the transfer and storage of sludge and ensuring that the T Plant upgrade and operational schedule is well integrated with the sludge storage activities. (2) If the confidence level in a durable, extended T Plant mission independent of sludge storage is uncertain, then the ASF conceptual design should be pursued on a parallel path with preparation of T Plant for sludge storage until those uncertainties are resolved. (3) Finally, if the confidence level in a durable, extended T Plant mission independent of sludge storage is low, then the ASF design should be selected to provide independence from the T Plant mission risk.

RUTHERFORD WW; GEUTHER WJ; STRANKMAN MR; CONRAD EA; RHOADARMER DD; BLACK DM; POTTMEYER JA

2009-04-29T23:59:59.000Z

177

K Basins Sludge Treatment Project Phase 1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

K Basins Sludge Treatment Project Phase 1 K Basins Sludge Treatment Project Phase 1 Technology Readiness Assessment Report Herb G. Sutter Michael Poirier Art W. Etchells Gary Smith Kris Thomas Jim J. Davis Paul Macbeth November 16, 2009 Prepared by the U.S. Department of Energy Washington, D.C. K Basins Sludge Treatment Project Phase 1 Technology Readiness Assessment Report November 16, 2009 ii Herbert G. Sutter, Team Lead Date Michael Poirier, Team Member Date Arthur W. Etchells, Team Member Date Gary Smith, Team Member Date Kris Thomas, Team Member Date Jim J. Davis, Team Member Date Paul Macbeth, Team Member Date Signatures 11/09/2009 11/09/2009 11/09/2009 K Basins Sludge Treatment Project Phase 1 Technology Readiness Assessment Report November 16, 2009

178

Your Unanswered Questions.... Answered - Batch 2 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Your Unanswered Questions.... Answered - Batch 2 Your Unanswered Questions.... Answered - Batch 2 Your Unanswered Questions.... Answered - Batch 2 February 28, 2011 - 2:46pm Addthis Ginny Simmons Ginny Simmons Former Managing Editor for Energy.gov, Office of Public Affairs Last month, Secretary Chu hosted an online town hall to discuss President Obama's clean energy innovation agenda -- and while he was able to answer about 10 questions submitted online during the event, we received more than 200! For the next fews days, we're answering some of the ones Secretary Chu wasn't able to get to that day. Below is our second batch of questions and answers. From John Fahey over Facebook: How can we create a predictable investment environment for the renewable sector? President Obama's proposal to generate 80 percent of electricity from

179

Effect of Batch Initial Velocity on the Glass Furnace Efficiency  

Science Conference Proceedings (OSTI)

There is a direct coloration between the batch distribution techniques and the furnace ... A Review: Solar Thermal Reactors for Materials Production ... Cellulose Acetate Membranes for CO2 Separation from Water-gas-shift Reaction Products.

180

HANFORD K BASINS SLUDGE RETREIVAL & TREATMENT  

SciTech Connect

This paper shows how Fluor Hanford and BNG America have combined nuclear plant skills from the US and the UK to devise methods to retrieve and treat the sludge that has accumulated in K Basins at the Hanford site over many years. Retrieving the sludge is the final stage in removing fuel and sludge from the basins to allow them to be decontaminated and decommissioned, thus removing the threat of contamination of the Columbia River. A description is given of sludge retrieval using vacuum lances and specially developed nozzles and pumps into Consolidation Containers within the basins. The special attention that had to be paid to the heat generation and potential criticality issues with the irradiated uranium-containing sludge is described. The processes developed to re-mobilize the sludge from the Consolidation Containers and pump it through flexible and transportable hose-in-hose piping to the treatment facility are explained with particular note made of dealing with the abrasive nature of the sludge. The treatment facility, housed in an existing Hanford building is described, and the uranium-corrosion and grout encapsulation processes explained. The uranium corrosion process is a robust, tempered process very suitable for dealing with a range of differing sludge compositions. The grout process to produce the final waste form is backed by BNG America's 20 years experience of grouting radioactive waste at Sellafield and elsewhere. The use of transportable and re-usable equipment is emphasized and its role noted in avoiding new plant build that itself will require cleanup. The processes and techniques described in the paper are shown to have wide applicability to nuclear cleanup worldwide.

VASQUEZ, D.A.

2005-07-05T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Clean and Efficient Utilization of Sewage Sludge  

DOE Green Energy (OSTI)

This is the Final Report for the DOE SBIR Phase II project (Grant No. DE-FG03-98ER82573). This report summarizes accomplishments and results for the entire program. In this program an innovative technology has been devised for transforming sewage sludge into a high quality fuel and recovering its energy content. The technology being developed is generally applicable to nearly all municipal sewage sludge management facilities and coal-fired boilers. It will provide economic and environmental benefits.

Zamansky, Vladimir; Rizeq, George

2002-09-12T23:59:59.000Z

182

Land application systems for municipal sludge  

SciTech Connect

The production of treated municipal sludge requiring disposal or recycling has increased substantially in the last 10 years as a result of more stringent waste-water treatment requirements. In 1974, for example, there were 3.2 million dry tons of sludge requiring disposal. By 1982 that number had more than doubled to 6.5 million dry tons/year. Land application of municipal sludge is widely practiced in the United States as a method of handling these increasing tonnages. For wastewater treatment plants with less than 10 mgd capacity, 39 percent of the sludge produced is managed by land application. Currently, for all size treatment plants, about 25 percent of the nation's sludge is land applied. The experience with land application has shown it to be a safe and effective sludge management practice. In particular, research and studies of the practice over the past 10 years have produced new knowledge which allows the benefits of land application to be realized with minimal adverse impact. 11 references.

Crites, R.W.

1985-05-01T23:59:59.000Z

183

Sludge storage lagoon biogas recovery and use  

SciTech Connect

The City of Memphis has two wastewater treatment plants. The SWTP employs two large anaerobic digestion sludge lagoons as part of the overall sludge treatment system. Although these lagoons are effective in concentrating and digesting sludge, they can generate offensive odors. The SWTP uses aerobic digesters to partially stabilize the sludge and help reduce objectionable odors before it enters the lagoons. The anaerobic digestion of sludge in the lagoons results in the dispersion of a large quantity of biogas into the atmosphere. The City realized that if the lagoons could be covered, the odor problem could be resolved, and at the same, time, biogas could be recovered and utilized as a source of energy. In 1987, the City commissioned ADI International to conduct a feasibility study to evaluate alternative methods of covering the lagoons and recovering and utilizing the biogas. The study recommended that the project be developed in two phases: (1) recovery of the biogas and (2) utilization of the biogas. Phase 1 consists of covering the two lagoons with an insulated membrane to control odor and temperature and collect the biogas. Phase 1 was found to be economically feasible and offered a unique opportunity for the City to save substantial operating costs at the treatment facility. The Memphis biogas recovery project is the only application in the world where a membrane cover has been used on a municipal wastewater sludge lagoon. It is also the largest lagoon cover system in the world.

Muller, D.; Norville, C. (Memphis and Shelby County Div. of Planning and Development, TN (United States))

1991-07-01T23:59:59.000Z

184

Independent Activity Report, Hanford Sludge Treatment Project - February  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sludge Treatment Project - Sludge Treatment Project - February 2012 Independent Activity Report, Hanford Sludge Treatment Project - February 2012 February 2012 Hanford Sludge Treatment Project Operational Awareness Review [HIAR-RL-2012-02-27] The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), performed operational awareness reviews of the Sludge Treatment Project (STP), Engineered Container Retrieval and Transfer System (ECRTS) during site visits. Independent Activity Report, Hanford Sludge Treatment Project - February 2012 More Documents & Publications Independent Activity Report, Richland Operations Office - June 2011 Independent Activity Report, Richland Operations Office - April 2011 Independent Activity Report, Richland Operations Office - August 2011

185

Deep Sludge Gas Release Event Analytical Evaluation  

SciTech Connect

The purpose of the Deep Sludge Gas Release Event Analytical Evaluation (DSGRE-AE) is to evaluate the postulated hypothesis that a hydrogen GRE may occur in Hanford tanks containing waste sludges at levels greater than previously experienced. There is a need to understand gas retention and release hazards in sludge beds which are 200 -300 inches deep. These sludge beds are deeper than historical Hanford sludge waste beds, and are created when waste is retrieved from older single-shell tanks (SST) and transferred to newer double-shell tanks (DST).Retrieval of waste from SSTs reduces the risk to the environment from leakage or potential leakage of waste into the ground from these tanks. However, the possibility of an energetic event (flammable gas accident) in the retrieval receiver DST is worse than slow leakage. Lines of inquiry, therefore, are (1) can sludge waste be stored safely in deep beds; (2) can gas release events (GRE) be prevented by periodically degassing the sludge (e.g., mixer pump); or (3) does the retrieval strategy need to be altered to limit sludge bed height by retrieving into additional DSTs? The scope of this effort is to provide expert advice on whether or not to move forward with the generation of deep beds of sludge through retrieval of C-Farm tanks. Evaluation of possible mitigation methods (e.g., using mixer pumps to release gas, retrieving into an additional DST) are being evaluated by a second team and are not discussed in this report. While available data and engineering judgment indicate that increased gas retention (retained gas fraction) in DST sludge at depths resulting from the completion of SST 241-C Tank Farm retrievals is not expected and, even if gas releases were to occur, they would be small and local, a positive USQ was declared (Occurrence Report EM-RP--WRPS-TANKFARM-2012-0014, "Potential Exists for a Large Spontaneous Gas Release Event in Deep Settled Waste Sludge"). The purpose of this technical report is to (1) present and discuss current understandings of gas retention and release mechanisms for deep sludge in U.S. Department of Energy (DOE) complex waste storage tanks; and (2) to identify viable methods/criteria for demonstrating safety relative to deep sludge gas release events (DSGRE) in the near term to support the Hanford C-Farm retrieval mission. A secondary purpose is to identify viable methods/criteria for demonstrating safety relative to DSGREs in the longer term to support the mission to retrieve waste from the Hanford Tank Farms and deliver it to the Waste Treatment and Immobilization Plant (WTP). The potential DSGRE issue resulted in the declaration of a positive Unreviewed Safety Question (USQ). C-Farm retrievals are currently proceeding under a Justification for Continued Operation (JCO) that only allows tanks 241-AN-101 and 241-AN-106 sludge levels of 192 inches and 195 inches, respectively. C-Farm retrievals need deeper sludge levels (approximately 310 inches in 241-AN-101 and approximately 250 inches in 241-AN-106). This effort is to provide analytical data and justification to continue retrievals in a safe and efficient manner.

Sams, Terry L.

2013-08-15T23:59:59.000Z

186

Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)  

SciTech Connect

This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility.

WESTRA, A.G.

1999-06-24T23:59:59.000Z

187

An Assessment of Technologies to Provide Extended Sludge Retrieval from Underground Storage Tanks at the Hanford Site  

SciTech Connect

The purpose of this study was to identify sludge mobilization technologies that can be readily installed in double-shell tanks along with mixer pumps to augment mixer pump operation when mixer pumps do not adequately mobilize waste. The supplementary technologies will mobilize sludge that may accumulate in tank locations out-of-reach of the mixer-pump jet and move the sludge into the mixer-pump range of operation. The identified technologies will be evaluated to determine if their performances and configurations are adequate to meet requirements developed for enhanced sludge removal systems. The study proceeded in three parallel paths to identify technologies that: (1) have been previously deployed or demonstrated in radioactive waste tanks, (2) have been specifically evaluated for their ability to mobilize or dislodge waste simulants with physical and theological properties similar to those anticipated during waste retrieval, and (3) have been used in similar industrial conditions, bu t not specifically evaluated for radioactive waste retrieval.

JA Bamberger

2000-08-02T23:59:59.000Z

188

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

SciTech Connect

Packaged 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.

Wells, Beric E.; Enderlin, Carl W.; Gauglitz, Phillip A.; Peterson, Reid A.

2009-09-29T23:59:59.000Z

189

Devolatilization and ash comminution of two different sewage sludges under fluidized bed combustion conditions  

Science Conference Proceedings (OSTI)

Two different wet sewage sludges have been characterized under fluidized bed combustion conditions with reference to their devolatilization behavior and ash comminution with the aid of different and complementary experimental protocols. Analysis of the devolatilization process allowed to determine the size of fuel particle able to achieve effective lateral spreading of the volatile matter across the cross-section of medium-scale combustors. Primary fragmentation and primary ash particle characterization pointed out the formation of a significant amount of relatively large fragments. The mechanical properties of these fragments have been characterized by means of elutriation/abrasion tests using both quartz and sludge ash beds. (author)

Solimene, R.; Urciuolo, M.; Cammarota, A.; Chirone, R. [Istituto di Ricerche sulla Combustione (IRC) - CNR, Napoli (Italy); Salatino, P. [Istituto di Ricerche sulla Combustione (IRC) - CNR, Napoli (Italy); Dipartimento di Ingegneria Chimica Universita degli Studi di Napoli Federico II, Napoli (Italy); Damonte, G.; Donati, C.; Puglisi, G. [ECODECO Gruppo A2A, Giussago (PV) (Italy)

2010-04-15T23:59:59.000Z

190

Engineering evaluation of neutralization and precipitation processes applicable to sludge treatment project  

SciTech Connect

Engineering evaluations have been performed to determine likely unit operations and methods required to support the removal, storage, treatment and disposal of solids/sludges present in the K Basins at the Hanford Site. This evaluation was initiated to select a neutralization process for dissolver product solution resulting from nitric acid treatment of about 50 m{sup 3} of Hanford Site K Basins sludge. Neutralization is required to meet Tank Waste Remediation Waste System acceptance criteria for storage of the waste in the double shell tanks after neutralization, the supernate and precipitate will be transferred to the high level waste storage tanks in 200E Area. Non transuranic (TRU) solids residue will be transferred to the Environmental Restoration Disposal Facility (ERDF). This report presents an overview of neutralization and precipitation methods previously used and tested. This report also recommends a neutralization process to be used as part of the K Basins Sludge Treatment Project and identifies additional operations requiring further evaluation.

Klem, M.J.

1998-08-25T23:59:59.000Z

191

F/H seepage basin groundwater influent, effluent, precipitated sludge characterization task technical plan  

SciTech Connect

A treatability study to support the development of a remediation system which would reduce the contaminant levels in groundwater removed from the aquifers in the vicinity of the F/H seepage basins and southwest of the Mixed Waste Management Facility (MWMF) at the Savannah River facility was conducted. Proposed changes in the remediation system require an additional study to determine whether precipitated sludge generated from the proposed remediation system will be hazardous as defined by RCRA. Several contaminants, such as lead and mercury, are above the groundwater protection standards. The presence of radionuclides and other contaminants in the sludge does not present a problem provided that the sludge can pass the Toxicity Characteristic Leaching Procedure (TCLP) test. The study has been developed in such a manner as to cover the possible range of treatment options that may be used.

Siler, J.L.

1993-10-29T23:59:59.000Z

192

Gas Generation from K East Basin Sludges - Series II Testing  

Science Conference Proceedings (OSTI)

This report describes work to examine the gas generation behavior of actual K East (KE) Basin floor, pit and canister sludge. Mixed and unmixed and fractionated KE canister sludge were tested, along with floor and pit sludges from areas in the KE Basin not previously sampled. The first report in this series focused on gas generation from KE floor and canister sludge collected using a consolidated sampling technique. The third report will present results of gas generation testing of irradiated uranium fuel fragments with and without sludge addition. The path forward for management of the K Basin Sludge is to retrieve, ship, and store the sludge at T Plant until final processing at some future date. Gas generation will impact the designs and costs of systems associated with retrieval, transportation and storage of sludge.

Bryan, Samuel A.; Delegard, Calvin H.; Schmidt, Andrew J.; Sell, Rachel L.; Silvers, Kurt L.; Gano, Susan R.; Thornton, Brenda M.

2001-03-14T23:59:59.000Z

193

Hanford Sludge Treatment Project 105-KW Final Safety Analysis...  

NLE Websites -- All DOE Office Websites (Extended Search)

Analysis Report (HNF-SD-WM-SAR-062, Revision 14C) for the Sludge Treatment Project at the Hanford Site. 2.0 BACKGROUND The Sludge Treatment Project manages the removal of...

194

Microsoft Word - 2010 Hanford Sludge Treatment Project Visit...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the engineered containers presently containing the sludge in the K-West Basin, the underwater pump that will be used to move the sludge from the pool to the transport vessels,...

195

Hanford Sludge Treatment Project 105-KW Final Safety Analysis...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Report (HNF-SD-WM-SAR-062, Revision 14C) for the Sludge Treatment Project at the Hanford Site. 2.0 BACKGROUND The Sludge Treatment Project manages the removal of radioactive...

196

Scheduling a hybrid flowshop with batch production at the last stage  

Science Conference Proceedings (OSTI)

In this paper, we address the problem of scheduling n jobs in an s-stage hybrid flowshop with batch production at the last stage with the objective of minimizing a given criterion with respect to the completion time. The batch production at stage s is ... Keywords: Batch decoupling, Batch production, Hybrid flowshop scheduling, Improved dynamic programming, Lagrangian relaxation

Hua Xuan; Lixin Tang

2007-09-01T23:59:59.000Z

197

Evaluation of neural networks-based controllers in batch polymerisation of methyl methacrylate  

Science Conference Proceedings (OSTI)

The importance of batch reactors in today's process industries cannot be overstated. Thus said, it is important to optimise their operation in order to consistently achieve products of high quality while minimising the production of undesirables. In ... Keywords: Batch polymerisation, Batch reactor control, Batch reactor optimisation

E. E. Ekpo; I. M. Mujtaba

2008-03-01T23:59:59.000Z

198

Maintenance and Operations study for K basins sludge treatment  

SciTech Connect

This study evaluates maintenance and operating concepts for the chemical treatment of sludge from the 100 K Basins at Hanford. The sludge treatment equipment that will require remote operation or maintenance was identified. Then various maintenance and operating concepts used in the nuclear industry were evaluated for applicability to sludge treatment. A hot cell or cells is recommended as the best maintenance and operating concept for a sludge treatment facility.

WESTRA, A.G.

1998-11-30T23:59:59.000Z

199

Liquidization of dewatered organic sludge and anaerobic treatment  

SciTech Connect

Dewatered sewage sludge was thermochemically liquidized at 175 {degrees}C and the liquidized sludge was separated by centrifugation to 58% (w/w) supernatant and 42% precipitate. The amount of proteins in the liquidized sludge slightly decreased through the liquidization process, however, that of lipids increased. The supernatant separated from the sludge liquidized with dewatered sewage sludge was successfully anaerobically digested. Biogas yield from the supernatant from dewatered sewage sludge at organic loading concentrations of 1.9-2.2 g VS/l during 9 days incubation was 440 ml/g-added VS and digestion ratio was 66% (w/w). Biogas yield in the case of dewatered sewage sludge was 257 ml/g-added VS and digestion ratio was 45%. Similar results were obtained in the case of the anaerobically digested with sewage sludge and dewatered sludge. Anaerobic digestion of the supernatants from the liquidized sludges resulted in high biogas productivity and high digestion ratio compared with these of the original sludges. Moreover, the precipitates contained lower moisture, therefore, they can be incinerated easier than the respective original sludges.

Sawayama, Shigeki; Inoue, Seiichi; Ogi, Tomoko [National Institute for Resources and Environment, Tsukuba, Ibaraki (Japan)

1996-12-31T23:59:59.000Z

200

FINE PARTICAL AND TOXIC METAL EMISSIONS FROM THE COMBUSTION OF SEWAGE SLUDGE/COAL MIXTURES: A SYSTEMATIC ASSESSMENT  

DOE Green Energy (OSTI)

This research project focuses on pollutants from the combustion of mixtures of dried municipal sewage sludge (MSS) and pulverized coal. The objective was to determine potential tradeoffs between CO{sub 2} mitigation through using a CO{sub 2} neutral fuel, such as municipal sewage sludge, and the emergence of other potential problems such as the emission of toxic fly ash particles. The work led to new insight into mechanisms governing the partitioning of major and trace metals from the combustion of sewage sludge, and mixtures of coal and sewage sludge. The research also showed that the co-combustion of coal and sewage sludge emitted fine particulate matter that might potentially cause greater lung injury than that from the combustion of either coal alone or municipal sewage sludge alone. The reason appeared to be that the toxicity measured required the presence of large amounts of both zinc and sulfur in particles that were inhaled. MSS provided the zinc while coal provided the sulfur. Additional research showed that the toxic effects could most likely be engineered out of the process, through the introduction of kaolinite sorbent downstream of the combustion zone, or removing the sulfur from the fuel. These results are consequences of applying ''Health Effects Engineering'' to this issue. Health Effects Engineering is a new discipline arising out of this work, and is derived from using a collaboration of combustion engineers and toxicologists to mitigate the potentially bad health effects from combustion of this biomass fuel.

Jost O.L. Wendt; Wayne S. Seames; Art Fernandez

2003-09-21T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

ACTUAL-WASTE TESTING OF ULTRAVIOLET LIGHT TO AUGMENT THE ENHANCED CHEMICAL CLEANING OF SRS SLUDGE  

SciTech Connect

In support of Savannah River Site (SRS) tank closure efforts, the Savannah River National Laboratory (SRNL) conducted Real Waste Testing (RWT) to evaluate Enhanced Chemical Cleaning (ECC), an alternative to the baseline 8 wt% oxalic acid (OA) chemical cleaning technology for tank sludge heel removal. ECC utilizes a more dilute OA solution (2 wt%) and an oxalate destruction technology using ozonolysis with or without the application of ultraviolet (UV) light. SRNL conducted tests of the ECC process using actual SRS waste material from Tanks 5F and 12H. The previous phase of testing involved testing of all phases of the ECC process (sludge dissolution, OA decomposition, product evaporation, and deposition tank storage) but did not involve the use of UV light in OA decomposition. The new phase of testing documented in this report focused on the use of UV light to assist OA decomposition, but involved only the OA decomposition and deposition tank portions of the process. Compared with the previous testing at analogous conditions without UV light, OA decomposition with the use of UV light generally reduced time required to reach the target of <100 mg/L oxalate. This effect was the most pronounced during the initial part of the decomposition batches, when pH was <4. For the later stages of each OA decomposition batch, the increase in OA decomposition rate with use of the UV light appeared to be minimal. Testing of the deposition tank storage of the ECC product resulted in analogous soluble concentrations regardless of the use or non-use of UV light in the ECC reactor.

Martino, C.; King, W.; Ketusky, E.

2012-07-10T23:59:59.000Z

202

Fuzzy logic control of batch-feeding refuse incineration  

Science Conference Proceedings (OSTI)

The municipal solid waste (MSW) or refuse incineration plant is designated to reduce the volume of the refuse and recover energy from it. The steam generated from a boiler heated by burning refuse is sent to a turbine to generate the electricity. Batch-feeding ... Keywords: Singapore, Ulu Pandan refuse incineration plant, batch-feeding refuse incineration, boiler, boilers, combustion, complete combustion, electricity generation, energy recovery, flow control, fuzzy control, fuzzy logic control, grate rotating rates, incomplete combustion, municipal solid waste plant, rule-base fuzzy logic control algorithms, steam flow rate, steam power stations, uncertain fluctuation, waste disposal, waste-to-energy power plants

Desong Chen

1995-03-01T23:59:59.000Z

203

Sludge recycle and reuse in acid mine drainage treatment  

Science Conference Proceedings (OSTI)

Neutralization of acid mine drainage produces vast quantities of iron-rich sludge, and large quantities of unused lime remain in the sludge after treatment. In a study in which sludge was recycled to increase lime utilization, sludge was mixed with raw acid mine drainage and settled out in an intermediate clarifier. The clarifier supernatant was then treated by lime addition, aeration and sedimentation. The low-pH sludge was withdrawn from the intermediate clarifier. The iron was recovered by acidification and used as wastewater coagulant. The recycle scheme resulted in a 30% decrease in lime requirements, and the resultant coagulant performed well when compared with stock iron coagulant solutions.

Keefer, G.B.; Sack, W.A.

1983-03-01T23:59:59.000Z

204

Residuals, Sludge, and Composting (Maine) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Residuals, Sludge, and Composting (Maine) Residuals, Sludge, and Composting (Maine) Residuals, Sludge, and Composting (Maine) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Maine Program Type Siting and Permitting Provider Department of Environmental Protection The Maine Department of Environmental Protection's Residuals, Sludge, and Composting program regulates the land application and post-processing of organic wastes, including sewage sludge, septage, food waste, and wood

205

Preparation and Characterization of Uranium Oxides in Support of the K Basin Sludge Treatment Project  

Science Conference Proceedings (OSTI)

Uraninite (UO2) and metaschoepite (UO3·2H2O) are the uranium phases most frequently observed in K Basin sludge. Uraninite arises from the oxidation of uranium metal by anoxic water and metaschoepite arises from oxidation of uraninite by atmospheric or radiolytic oxygen. Studies of the oxidation of uraninite by oxygen to form metaschoepite were performed at 21°C and 50°C. A uranium oxide oxidation state characterization method based on spectrophotometry of the solution formed by dissolving aqueous slurries in phosphoric acid was developed to follow the extent of reaction. This method may be applied to determine uranium oxide oxidation state distribution in K Basin sludge. The uraninite produced by anoxic corrosion of uranium metal has exceedingly fine particle size (6 nm diameter), forms agglomerates, and has the formula UO2.004±0.007; i.e., is practically stoichiometric UO2. The metaschoepite particles are flatter and wider when prepared at 21°C than the particles prepared at 50°C. These particles are much smaller than the metaschoepite observed in prolonged exposure of actual K Basin sludge to warm moist oxidizing conditions. The uraninite produced by anoxic uranium metal corrosion and the metaschoepite produced by reaction of uraninite aqueous slurries with oxygen may be used in engineering and process development testing. A rapid alternative method to determine uranium metal concentrations in sludge also was identified.

Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.

2008-07-08T23:59:59.000Z

206

Evaluation of leaching and ecotoxicological properties of sewage sludge-fly ash mixtures  

Science Conference Proceedings (OSTI)

The objectives of this work were the evaluation of sewage sludge stabilization by mixing with fly ash, the examination of the physicochemical properties of the produced materials and their leachates and the assessment of their environmental impact by the evaluation of the ecotoxic characteristics. Different ratios of fly ash and sewage sludge (1:1, 1:2, 1:3, 1:6, and 1:9) were mixed for 48 and 72 h. After mixing, the liquid phase of the produced materials was analyzed for total coliforms and Escherichia coli, while the solid residue was dried and tested for the leaching characteristics by the application of TCLP and EN 12457-2 standard leaching methods. Furthermore, the produced leachates were analyzed for their content of specific metals, while their ecotoxicological characteristics were determined by the use of toxicity bioassays, using the marine photobacterium Vibrio fischeri and the crustacean Daphnia magna. The phytotoxicity of sewage sludge-fly ash mixtures was also determined by utilizing seeds of three higher plants (one monocotyl and two dicotyls). The mixtures exhibited low metal leaching in all cases, while the ecotoxic properties increased with the increase of fly ash/sewage sludge ratio. The phytotoxicity testing showed increased root length growth inhibition.

C.A. Papadimitriou; I. Haritou; P. Samaras; A.I. Zouboulis [Technological Educational Institute of West Macedonia, Kozani (Greece)

2008-03-15T23:59:59.000Z

207

Evaluation of Shear Strength Threshold of Concern for Retrieval of Interim-Stored K-Basin Sludge in the Hanford Site  

SciTech Connect

K-Basin sludge will be recovered into the Sludge Transport and Storage Containers (STSCs) and will be stored in the T Plant for interim storage (at least 10 years). Long-term sludge storage tests conducted by Pacific Northwest National Laboratory show that high uranium content K Basin sludge can self-cement and form a strong sludge with a bulk shear strength of up to 65 kPa. Some of this sludge has "paste" and "chunks" with shear strengths of approximately 3~5 kPa and 380 ~ 770 kPa, respectively. High uranium content sludge samples subjected to hydrothermal testing (e.g., 185°C, 10 h) have been observed to form agglomerates with a shear strength up to 170 kPa. After interim storage at T Plant, the sludge in the STSCs will be mobilized by water jets impinging the sludge. The objective of the evaluation was to determine the range of sludge shear strength for which there is high confidence that a water-jet retrieval system can mobilize stored K-Basin sludge from STSCs. The shear strength at which the sludge can be retrieved is defined as the "shear strength threshold of concern." If the sludge shear strength is greater than the value of the shear strength threshold of concern, a water-jet retrieval system will be unlikely to mobilize the sludge up to the container’s walls. The shear strength threshold of concern can be compared with the range of possible shear strengths of K-Basin stored sludge to determine if the current post interim-storage, water-jet retrieval method is adequate. Fourteen effective cleaning radius (ECR) models were reviewed, and their validity was examined by applying them to Hanford 241-SY-101 and 241-AZ-101 Tanks to reproduce the measured ECR produced by the mixer pumps. The validation test identified that the Powell-3 and Crowe-2 ECR models are more accurate than other ECR models reviewed. These ECR models were used to address a question as to whether the effective cleaning radius of a water jet is sufficient or if it can be readily expanded to cover the range of possible shear strengths. These results will assist CH2M HILL Plateau Remediation Company (CHPRC) to establish the technical basis of the feasibility of the sludge retrieval and storage plan and to develop an adequate water jet system to retrieve the stored K-Basin sludge in the STSCs. The STSCs are 2:1 elliptical-head vessels, 58 inches in diameter and 105 inches tall. Each STSC will contain 0.5 to 2.1 m3 of settled sludge with the specific loading dependent upon sludge type.

Onishi, Yasuo; Yokuda, Satoru T.; Schmidt, Andrew J.

2010-11-01T23:59:59.000Z

208

EM Employs Innovative Technology to Remove Radioactive Sludge | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Employs Innovative Technology to Remove Radioactive Sludge Employs Innovative Technology to Remove Radioactive Sludge EM Employs Innovative Technology to Remove Radioactive Sludge September 1, 2012 - 12:00pm Addthis Testing and equipment simulations ensure first-of-a-kind technological processes for sludge removal can be conducted safely and efficiently. Testing and equipment simulations ensure first-of-a-kind technological processes for sludge removal can be conducted safely and efficiently. RICHLAND, Wash. - The Richland Operations Office and contractor CH2M HILL Plateau Remediation Company successfully removed a portion of a highly radioactive sludge from underwater storage in a large basin adjacent to the K West reactor at the Hanford site this month. In that milestone, workers removed sludge originating from knock-out pots,

209

An Evaluation of Some Recent Batches of IAPSO Standard Seawater  

Science Conference Proceedings (OSTI)

The authors examine changes in the salinity of the International Association for the Physical Sciences of the Ocean standard seawater (SSW) as used in seven cruises between 1991 and 1997. Ten batches of SSW were used during this time—several more ...

Sheldon Bacon; Helen M. Snaith; Margaret J. Yelland

2000-06-01T23:59:59.000Z

210

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

DOE Green Energy (OSTI)

The Sludge Treatment Project (STP), managed for the U. S. DOE by Fluor Hanford (FH), was created to design and operate a process to eliminate uranium metal from K Basin sludge prior to packaging for Waste Isolation Pilot Plant (WIPP). The STP process uses high temperature liquid water to accelerate the reaction, produce uranium dioxide from the uranium metal, and safely discharge the hydrogen. Under nominal process conditions, the sludge will be heated in pressurized water at 185°C for as long as 72 hours to assure the complete reaction (corrosion) of up to 0.25-inch diameter uranium metal pieces. Under contract to FH, the Pacific Northwest National Laboratory (PNNL) conducted bench-scale testing of the STP hydrothermal process in November and December 2006. Five tests (~50 ml each) were conducted in sealed, un-agitated reaction vessels under the hydrothermal conditions (e.g., 7 to 72 h at 185°C) of the STP corrosion process using radioactive sludge samples collected from the K East Basin and particles/coupons of N Reactor fuel also taken from the K Basins. The tests were designed to evaluate and understand the chemical changes that may be occurring and the effects that any changes would have on sludge rheological properties. The 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 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.

Delegard, Calvin H.; Schmidt, Andrew J.; Thornton, Brenda M.

2007-03-30T23:59:59.000Z

211

Integrating BES in the wastewater and sludge  

E-Print Network (OSTI)

, denitrification, and anaerobic digester treatment systems, while chemical methods include phosphate removal, dye of WAS, including treatment of influent or the accumulated sludge with anaerobic digesters (Rulkens 2008 bacterial metabolism even at conditions outside the optimum range for anaerobic digestion (Angenent et al

Angenent, Lars T.

212

Asbestos in sludge- a significant risk  

SciTech Connect

The purpose of this study is to consider the issue of asbestos in sludge applied to land, and to provide some perspective on the health risk conclusions drawn from research on which these stories were based. While this review cannot conclude there is no health risk due to the presence of asbestos in sludge, it does suggest that such risk is not appreciably greater than from the presence of asbestos in other environmental samples. As analytical techniques continue to improve, increasing numbers of potentially toxic chemicals will be found in all types of environmental samples, including sludge. However, it is essential that the mere presence of a chemical in such samples not be equated with toxicity, or a hazard to the general public. Although some of the contaminants that will be detected in sludges or other environmental samples will be new and exotic, many have been present in the environment for years, and, in the case of the asbestos, for millenia. Scientists and engineers must work vigorously to minimize such health risks due to environmental contamination. However, scientists have the responsibility to discuss risks within a framework that is understandable by the general public. To do otherwise so as to incite fear and apprehension borders on scientific irresponsibility, and neither solves the problem, nor does justice to the scientific method.

Naylor, L.M.

1989-01-01T23:59:59.000Z

213

Fiscal year 1994 1/25-scale sludge mobilization testing  

Science Conference Proceedings (OSTI)

There are 28 one-million-gallon double-shell radioactive waste tanks on the Hanford Reservation in southeastern Washington State. The waste in these tanks was generated during processing of nuclear materials. Solids-laden slurries were placed into many of the tanks. Over time, the waste solids have settled to form a layer of sludge in the bottom of these tanks. The sludge layer thickness varies from tank to tank with some having only a few centimeters or no sludge up to some tanks which have about 4.5 m (15 ft) of sludge. It is planned that the waste will be removed from these tanks as part of the overall Hanford site cleanup efforts. Jet mixer pumps are to be placed into the tanks to stir up (mobilize) the sludge and form a uniform slurry suitable for pumping to downstream processing facilities. These mixer pumps use powerful jets of tank fluid directed horizontally out of two, diametrically opposed nozzles near the tank bottom. These fluid jets impinge upon the sludge and stir it up. The amount of sludge mobilized by the mixer pump jets depends not only on the jet properties, but also on the ability of the sludge to resist the jets. It is the goal of the work described in this document to develop the ability to predict how much sludge will be mobilized by the mixer pumps based on the size and velocity of the mixer pump jets and the physical and chemical properties of the tank sludge.

Powell, M.R.; Gates, C.M.; Hymas, C.R.; Sprecher, M.A. [Pacific Northwest Lab., Richland, WA (United States); Morter, N.J. [Associated Western Universities, Inc., Salt Lake City, UT (United States). Northwest Div.

1995-07-01T23:59:59.000Z

214

ESTIMATION OF THE TEMPERATURE RISE OF A MCU ACID STREAM PIPE IN NEAR PROXIMITY TO A SLUDGE STREAM PIPE  

SciTech Connect

Effluent streams from the Modular Caustic-Side Solvent Extraction Unit (MCU) will transfer to the tank farms and to the Defense Waste Processing Facility (DWPF). These streams will contain entrained solvent. A significant portion of the Strip Effluent (SE) pipeline (i.e., acid stream containing Isopar{reg_sign} L residues) length is within one inch of a sludge stream. Personnel envisioned the sludge stream temperature may reach 100 C during operation. The nearby SE stream may receive heat from the sludge stream and reach temperatures that may lead to flammability issues once the contents of the SE stream discharge into a larger reservoir. To this end, personnel used correlations from the literature to estimate the maximum temperature rise the SE stream may experience if the nearby sludge stream reaches boiling temperature. Several calculation methods were used to determine the temperature rise of the SE stream. One method considered a heat balance equation under steady state that employed correlation functions to estimate heat transfer rate. This method showed the maximum temperature of the acid stream (SE) may exceed 45 C when the nearby sludge stream is 80 C or higher. A second method used an effectiveness calculation used to predict the heat transfer rate in single pass heat exchanger. By envisioning the acid and sludge pipes as a parallel flow pipe-to-pipe heat exchanger, this method provides a conservative estimation of the maximum temperature rise. Assuming the contact area (i.e., the area over which the heat transfer occurs) is the whole pipe area, the results found by this method nearly matched the results found with the previous calculation method. It is recommended that the sludge stream be maintained below 80 C to minimize a flammable vapor hazard from occurring.

Fondeur, F; Michael Poirier, M; Samuel Fink, S

2007-07-12T23:59:59.000Z

215

CX-000500: Categorical Exclusion Determination | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Exclusion Determination CX-000500: Categorical Exclusion Determination Construct Rail Spur to Concrete Batch Plant, P-Area CX(s) Applied: B1.13 Date: 07082009 Location(s):...

216

Rapid Batch Characterization of Coal Utilization By-Products  

NLE Websites -- All DOE Office Websites (Extended Search)

Batch Characterization Batch Characterization of Coal Utilization By-Products Peter A. Hesbach 1 *, Alexander S. P. Abel 2 Ann G. Kim 3 , and Steven C. Lamey 4 1 U.S. Department of Energy, National Energy Technology Laboratory, 3610 Collins Ferry Road, P.O. Box 880, Morgantown, WV 26507-0880 USA; 2 NETL Site Support Contractor, Parsons, 3610 Collins Ferry Road, Morgantown, WV 26505 USA; 3 U.S. Department of Energy, National Energy Technology Laboratory Post-Doctoral Fellow, 626 Cochrans Mill Road, P.O. Box 10940, Pittsburgh, PA 15236-0940 USA; 4 retired, U.S. Department of Energy, National Energy Technology Laboratory, Morgantown, WV USA (* author for correspondence, phone: 304-285-4443, fax: 304-285-4487, e-mail: peter.hesbach@netl.doe.gov) KEYWORDS: leaching methods, ash characterization, coal utilization by-products

217

Dynamic scheduling II: look-ahead strategies for controlling batch operations in industry — an overview  

Science Conference Proceedings (OSTI)

Batching jobs in a manufacturing system is a very common policy in most industries. Main reasons for batching are avoidance of set ups and/or facilitation of material handling. Examples of batch-wise production systems are ovens found in aircraft industry ...

Durk-Jouke van der Zee

2003-12-01T23:59:59.000Z

218

Compilation and Integration of K Basin Sludge Particle Size Analysis Data  

SciTech Connect

This report consolidates and integrates all of the particle size analysis data generated during the Hanford K Basin sludge characterization campaigns. The provides the most representative particle size distribution curves for the various K Basin sludge types. Understanding the particle size distribution of the sludge is necessary to design sludge retrieval and processing systems and to address sludge transportation and storage safety issues due to the potential reactivity of sludge.

Bredt, Paul R. (BATTELLE (PACIFIC NW LAB)); Tingey, Joel M. (BATTELLE (PACIFIC NW LAB)); Schmidt, Andrew J. (BATTELLE (PACIFIC NW LAB))

2000-11-06T23:59:59.000Z

219

Test Plan for K Basin floor sludge consolidated sampling equipment  

SciTech Connect

The purpose of this document is to provide the test procedure for the function and acceptance testing of the K Basin Floor Sludge Consolidated Sampling Equipment. This equipment will be used to transfer K Basin floor sludge to a sludge sampling container for subsequent shipment to an analysis or testing facility. This equipment will provide sampling consistent with data quality objectives and sampling plans currently being developed.

OLIVER, J.W.

1998-10-30T23:59:59.000Z

220

Modelling and optimisation of batch distillation involving esterification and hydrolysis reaction systems. Modelling and optimisation of conventional and unconventional batch distillation process: Application to esterification of methanol and ethanol using acetic acid and hydrolysis of methyl lactate system.  

E-Print Network (OSTI)

??Batch distillation with chemical reaction when takes place in the same unit is referred to as batch reactive distillation process. The combination reduces the capital… (more)

Edreder, Elmahboub A.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Hanford Sludge Treatment Project Review, June 2011  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1-06-17 1-06-17 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Sludge Treatment Project Dates of Activity : 06/13/2011 - 06/17/2011 Report Preparer: Jake Wechselberger Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), performed operational awareness reviews of the Sludge Treatment Project (STP), Engineered Container Retrieval and Transfer System (ECRTS) during site visits. Result: During the period June 13-17, 2011, an HSS representative participated in tours of the STP test facility. The HSS representative was also briefed by the CHPRC STP Test Director and the DOE-Richland Operations Office principal support

222

Hanford Sludge Treatment Project, August 2011  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8-25 8-25 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Sludge Treatment Project Dates of Activity : 08/22/2011 - 08/25/2011 Report Preparer: Jake Wechselberger Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), performed operational awareness reviews of the Sludge Treatment Project (STP), Engineered Container Retrieval and Transfer System (ECRTS) during site visits. Result: During the period August 22-25, 2011, an HSS representative attended the STP ECRTS Design Review, Value Engineering. The design review was attended by virtually all STP designated personnel, including managers and experts, representing

223

Geothermal brines and sludges: a new resource  

DOE Green Energy (OSTI)

Development of cost efficient biochemical processes for the treatment of geothermal brines and sludges is the main thrust of a major R&D effort at Brookhaven National Laboratory (BNL). This effort has led to the design of an environmentally acceptable, technically and economically feasible new technology which converts geothermal wastes into products with significant commercial potential. These include valuable metals recovery with a metal extraction and recovery efficiency of better then 80% over short periods of time (5-25 hours). The new technology also yields valuable salts, such as potassium chloride and generates high quality pigment free silica. The basic technology is versatile and can, with slight modifications, be used in the treatment of hypersaline as well as low salinity brines and sludges. Concurrently traces of toxic metals, including radium are removed to levels which are within regulatory limits. The current status of the new biochemical technology will be discussed in this paper.

Premuzic, E.T.; Lin, M.S.; Lian, H.; Miltenberger, R.P.

1996-10-01T23:59:59.000Z

224

Ethanol production from paper sludge by simultaneous saccharification...  

NLE Websites -- All DOE Office Websites (Extended Search)

Ethanol Production From Paper Sludge by Simultaneous Saccharification and Co-Fermentation Using Recombinant Xylose-Fermenting Microorganisms Jiayi Zhang, 1 Lee R. Lynd 1,2 1...

225

Preparing T Plant to Store K-Basin Sludge  

SciTech Connect

This paper will explain the history and status of the modification of the Hanford T Plant facility for storage of K Basin sludge.

MCKENNEY, D.E.

2003-01-01T23:59:59.000Z

226

Operational Awareness Review of the Hanford Sludge Treatment...  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Safety and Emergency Management Evaluations Activity Report for the Sludge Treatment Project Dates of Activity : 11172010 - 04072011 Report Preparer: Jake...

227

Review of the Hanford Sludge Treatment Project, February 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Safety and Emergency Management Evaluations Activity Report for the Sludge Treatment Project Dates of Activity : 02272012 - 03012012 Report Preparer: Jake...

228

An Innovative Approach to Sludge Retrieval from Containers ...  

Objective of this work is to provide and demonstrate an alternate method of emptying the K- Basin Sludge from the ... Future work – Program plan

229

Dissolution of Uranium Metal from Hanford K Basin Sludge Simulant ...  

Dissolution of Uranium Metal from Hanford K Basin Sludge Simulant, Without Producing Hydrogen Stephanie Bruffey and Paul Taylor Background About 2100 metric tons of ...

230

Summary - K Basins Sludge Treatment Process  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

K Basin K Basin DOE is Proces the va at Han subsys oxidati objecti of-fact maturi Eleme Techn The as which seven * M * M * Pr * Pr * As The Ele Site: H roject: K P Report Date: A ited States Why DOE ns Sludge Treatme s constructing ss (STP) for re rious sludge st nford. The STP stems: sludge ion, assay, pac ive of the asse t" appraisal of t ty by first ident ents (CTEs) of t ology Readine What th ssessment team was further div CTEs and the Material Mobiliza Material Transfe rocess Chemis rocess Instrum ssay (TRL=2) To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin Hanford/ORP K Basins Slud Process/STP August 2007 Departmen K Bas E-EM Did This ent Process Flow D a K Basins Slu trieving, treatin treams stored i P is comprised containerizatio ckaging, and dr ssment was to the project's ov

231

U.S. Department of Energy Categorical Exclusion Determination Form  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Dissolution of Sludge Constituents in Glycolate-containing 2H Evaporator Rad Feed Solution Dissolution of Sludge Constituents in Glycolate-containing 2H Evaporator Rad Feed Solution Savannah River Site Aiken/Aiken/South Carolina Glycolic acid is being studied as an alternate reductant in the Defense Waste Processing Facility (DWPF) feed preparation process. It will either be a total or partial replacement for the formic acid that is currently used. The DWPF recycle stream serves as a portion of the feed to the 2H Evaporator. The DWPF recycle stream, in addition to containing sludge, also will contain glycolate. This testing seeks to determine the extent to which sludge constituents (Pu, U, Fe, etc.) dissolve (or the solubility of sludge constituents) in the glycolate-containing 2H Evaporator feed solution (Tank 43H). The testing also seeks to determine the interaction of the glycolate-containing evaporator feed solutions with 2H evaporator

232

Caustic Leaching of Hanford Tank S-110 Sludge  

SciTech Connect

This report describes the Hanford Tank S-110 sludge caustic leaching test conducted in FY 2001 at the Pacific Northwest National Laboratory. The data presented here can be used to develop the baseline and alternative flowsheets for pretreating Hanford tank sludge. The U.S. Department of Energy funded the work through the Efficient Separations and Processing Crosscutting Program (ESP; EM?50).

Lumetta, Gregg J.; Carson, Katharine J.; Darnell, Lori P.; Greenwood, Lawrence R.; Hoopes, Francis V.; Sell, Richard L.; Sinkov, Sergey I.; Soderquist, Chuck Z.; Urie, Michael W.; Wagner, John J.

2001-10-31T23:59:59.000Z

233

Gas Generation from K East Basin Sludges - Series II Testing  

SciTech Connect

This report describes work to examine the gas generation behavior of actual K East (KE) Basin floor, pit and canister sludge. Mixed and unmixed and fractionated KE canister sludge were tested, along with floor and pit sludges from areas in the KE Basin not previously sampled. The first report in this series focuses on gas generation from KE floor and canister sludge collected using a consolidated sampling technique. The third report presents results of gas generation testing of irradiated uranium fuel fragments with and without sludge addition. The path forward for management of the K Basin Sludge is to retrieve, ship, and store the sludge at T Plant until final processing at some future date. Gas generation will impact the designs and costs of systems associated with retrieval, transportation and storage of sludge. This report was originally published in March 2001. In January 2004, a transcription error was discovered in the value reported for the uranium metal content of KE North Loadout Pit sample FE-3. This revision of the report corrects the U metal content of FE-3 from 0.0013 wt% to 0.013 wt%.

Bryan, Samuel A.; Delegard, Calvin H.; Schmidt, Andrew J.; Sell, Rachel L.; Silvers, Kurt L.; Gano, Susan R.; Thornton, Brenda M.

2004-04-26T23:59:59.000Z

234

Hanford K-Basin Sludge Characterization Overview February 2005  

E-Print Network (OSTI)

Hanford K-Basin Sludge Characterization Overview February 2005 1 Hanford K-Basin Sludge Characterization Overview February 2005 1. Summary The Hanford K-East and K-West Basins were used to store of the irradiated fuel reprocessing facility at Hanford (the PUREX facility) the N-Reactor irradiated fuel remained

235

Test procedure forms for sludge retrieval and packaging  

SciTech Connect

This document provides test procedure forms for sludge retrieval and packaging tests in the 305 Cold Test Facility. The completed and approved forms provide all descriptions, criteria and analysis to safely perform sludge equipment tests in the 305 Cold Test Facility.

Feigenbutz, L.V.

1994-09-27T23:59:59.000Z

236

PRODUCTION OF CONSTRUCTION AGGREGATES FROM FLUE GAS DESULFURIZATION SLUDGE  

SciTech Connect

Through a cooperative agreement with DOE, the Research and Development Department of CONSOL Inc. (CONSOL R and D) is teaming with SynAggs, Inc. and Duquesne Light to design, construct, and operate a 500 lb/h continuous pilot plant to produce road construction aggregate from a mixture of wet flue gas desulfurization (FGD) sludge, fly ash, and other components. The proposed project is divided into six tasks: (1) Project Management; (2) Mix Design Evaluation; (3) Process Design; (4) Construction; (5) Start-Up and Operation; and (6) Reporting. In this quarter, Tasks 1 and 2 were completed. A project management plan (Task 1) was issued to DOE on October 22, 1998 . The mix design evaluation (Task 2) with Duquesne Light Elrama Station FGD sludge and Allegheny Power Hatfields Ferry Station fly ash was completed. Eight semi-continuous bench-scale tests were conducted to examine the effects of mix formulation on aggregate properties. A suitable mix formulation was identified to produce aggregates that meet specifications of the American Association of State High Transport Officials (AASHTO) as Class A aggregate for use in highway construction. The mix formulation was used in designing the flow sheet of the pilot plant. The process design (Task 3) is approximately 80% completed. Equipment was evaluated to comply with design requirements. The design for the curing vessel was completed by an outside engineering firm. All major equipment items for the pilot plant, except the curing vessel, were ordered. Pilot plant construction (Task 4) was begun in October. The Hazardous Substance Plan was issued to DOE. The Allegheny County (PA) Heat Department determined that an air emission permit is not required for operation of the pilot plant.

1998-12-01T23:59:59.000Z

237

CRAD, Emergency Management - Office of River Protection K Basin Sludge  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office of River Protection K Basin Office of River Protection K Basin Sludge Waste System CRAD, Emergency Management - Office of River Protection K Basin Sludge Waste System May 2004 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2004 assessment of the Emergency Management program at the Office of River Protection K Basin Sludge Waste System. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Emergency Management - Office of River Protection K Basin Sludge Waste System More Documents & Publications CRAD, Engineering - Office of River Protection K Basin Sludge Waste System

238

First of Hanford's Highly Radioactive Sludge Moved Away from River |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

First of Hanford's Highly Radioactive Sludge Moved Away from First of Hanford's Highly Radioactive Sludge Moved Away from River First of Hanford's Highly Radioactive Sludge Moved Away from River July 13, 2012 - 12:00pm Addthis Media Contacts Geoff Tyree, DOE Geoffrey.Tyree@rl.doe.gov 509-376-4171 Dee Millikin, CH2M HILL Dee_Millikin@rl.doe.gov 509-376-1297 RICHLAND, Wash. - Workers have started moving highly radioactive material, called sludge, away from the Columbia River, marking a significant milestone in the U. S. Department of Energy (DOE)'s cleanup of the Hanford Site in Washington State. Today, DOE contractor CH2M HILL Plateau Remediation Company (CH2M HILL) safely transferred the first large container of highly radioactive sludge from a basin next to a former plutonium production reactor to dry storage in the center of the site. Today's transfer is the first of six shipments

239

High Level Waste System Impacts from Acid Dissolution of Sludge  

DOE Green Energy (OSTI)

This research evaluates the ability of OLI{copyright} equilibrium based software to forecast Savannah River Site High Level Waste system impacts from oxalic acid dissolution of Tank 1-15 sludge heels. Without further laboratory and field testing, only the use of oxalic acid can be considered plausible to support sludge heel dissolution on multiple tanks. Using OLI{copyright} and available test results, a dissolution model is constructed and validated. Material and energy balances, coupled with the model, identify potential safety concerns. Overpressurization and overheating are shown to be unlikely. Corrosion induced hydrogen could, however, overwhelm the tank ventilation. While pH adjustment can restore the minimal hydrogen generation, resultant precipitates will notably increase the sludge volume. OLI{copyright} is used to develop a flowsheet such that additional sludge vitrification canisters and other negative system impacts are minimized. Sensitivity analyses are used to assess the processability impacts from variations in the sludge/quantities of acids.

KETUSKY, EDWARD

2006-04-20T23:59:59.000Z

240

Pretreatment of neutralized cladding removal waste sludge: Status Report  

SciTech Connect

This report describes the status of process development for pretreating Hanford neutralized cladding removal waste (NCRW) sludge, of which [approximately] 3.3 [times] 10[sup 6] L is stored in Tanks 103-AW and 105-AW at the Hanford Site. The initial baseline process chosen for pretreating NCRW sludge is to dissolve the sludge in nitric acid and extract the -transuranic (MU) elements from the dissolved sludge solution with octyl(phenyl)-N,N-diisobutylcarbamoyl methyl phosphine oxide (CNWO). This process converts the NCRW sludge into a relatively large volume of low-level waste (LLW) to be disposed of as grout, leaving only a small volume of high-level waste (HLW) requiring vitrification in the Hanford Waste Vitrification Plant (HWVP).

Lumetta, G J; Swanson, J L

1993-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Stabilization of Mercury in High pH Tank Sludges  

Science Conference Proceedings (OSTI)

DOE complex contains many tank sludges contaminated with mercury. The high pH of these tank sludges typically fails to stabilize the mercury, resulting in these radioactive wastes also being characteristically hazardous or mixed waste. The traditional treatment for soluble inorganic mercury species is precipitation as insoluble mercuric sulfide. Sulfide treatment and a commercial mercury-stabilizing product were tested on surrogate sludges at various alkaline pH values. Neither the sulfide nor the commercial product stabilized the mercury sufficiently at the high pH of the tank sludges to pass the Toxicity Characteristic Leach Procedure (TCLP) treatment standards of the Resource Conservation and Recovery Act (RCRA). The commercial product also failed to stabilize the mercury in samples of the actual tank sludges.

Spence, R.; Barton, J.

2003-02-24T23:59:59.000Z

242

Correlation between Organic Matter Degradation and the Rheological Performance of Waste Sludge During Anaerobic Digestion  

Science Conference Proceedings (OSTI)

Anaerobic digestion has demonstrated to be a good possibility to reduce the organic matter contents in waste activated sludge resulting in the effluents treatment. An anaerobic digestion was carried out in a 3.5 L reactor at 35?°C for a period of 20 days. An electronic thermostat controlled the temperature. The reactor was agitated at a rate of 200 rpm. The study of the rheological behavior of the waste activated sludge was done with an Anton Paar™ rheometer model MCR301 with a peltier plate for temperature control. Four?blade vane geometry was used with samples of 37 mL for determining rheological properties. Sampling (two samples) was taken every four days of anaerobic digestion through a peristaltic pump. The samples behavior was characterized by the Herschel?Bulkley model

Evangelina S. Morel; José A. Hernández?Hernándes; Juan M. Méndez?Contreras; Denis Cantú?Lozano

2008-01-01T23:59:59.000Z

243

Revised cost savings estimate with uncertainty for enhanced sludge washing of underground storage tank waste  

SciTech Connect

Enhanced Sludge Washing (ESW) has been selected to reduce the amount of sludge-based underground storage tank (UST) high-level waste at the Hanford site. During the past several years, studies have been conducted to determine the cost savings derived from the implementation of ESW. The tank waste inventory and ESW performance continues to be revised as characterization and development efforts advance. This study provides a new cost savings estimate based upon the most recent inventory and ESW performance revisions, and includes an estimate of the associated cost uncertainty. Whereas the author`s previous cost savings estimates for ESW were compared against no sludge washing, this study assumes the baseline to be simple water washing which more accurately reflects the retrieval activity along. The revised ESW cost savings estimate for all UST waste at Hanford is $6.1 B {+-} $1.3 B within 95% confidence. This is based upon capital and operating cost savings, but does not include development costs. The development costs are assumed negligible since they should be at least an order of magnitude less than the savings. The overall cost savings uncertainty was derived from process performance uncertainties and baseline remediation cost uncertainties, as determined by the author`s engineering judgment.

DeMuth, S.

1998-09-01T23:59:59.000Z

244

Limitations for heavy metal release during thermo-chemical treatment of sewage sludge ash  

Science Conference Proceedings (OSTI)

Phosphate recycling from sewage sludge can be achieved by heavy metal removal from sewage sludge ash (SSA) producing a fertilizer product: mixing SSA with chloride and treating this mixture (eventually after granulation) in a rotary kiln at 1000 {+-} 100 deg. C leads to the formation of volatile heavy metal compounds that evaporate and to P-phases with high bio-availability. Due to economical and ecological reasons, it is necessary to reduce the energy consumption of this technology. Generally, fluidized bed reactors are characterized by high heat and mass transfer and thus promise the saving of energy. Therefore, a rotary reactor and a fluidized bed reactor (both laboratory-scale and operated in batch mode) are used for the treatment of granulates containing SSA and CaCl{sub 2}. Treatment temperature, residence time and - in case of the fluidized bed reactor - superficial velocity are varied between 800 and 900 deg. C, 10 and 30 min and 3.4 and 4.6 m s{sup -1}. Cd and Pb can be removed well (>95 %) in all experiments. Cu removal ranges from 25% to 84%, for Zn 75-90% are realized. The amount of heavy metals removed increases with increasing temperature and residence time which is most pronounced for Cu. In the pellet, three major reactions occur: formation of HCl and Cl{sub 2} from CaCl{sub 2}; diffusion and reaction of these gases with heavy metal compounds; side reactions from heavy metal compounds with matrix material. Although, heat and mass transfer are higher in the fluidized bed reactor, Pb and Zn removal is slightly better in the rotary reactor. This is due the accelerated migration of formed HCl and Cl{sub 2} out of the pellets into the reactor atmosphere. Cu is apparently limited by the diffusion of its chloride thus the removal is higher in the fluidized bed unit.

Nowak, Benedikt, E-mail: benedikt.nowak@tuwien.ac.at [Institute of Chemical Engineering, Vienna University of Technology, Getreidemarkt 9/166, A-1060 Vienna (Austria); Perutka, Libor [Institute of Chemical Engineering, Vienna University of Technology, Getreidemarkt 9/166, A-1060 Vienna (Austria); Aschenbrenner, Philipp [Institute for Water Quality, Resource and Waste Management, Vienna University of Technology, Karlsplatz 13/226, A-1040 Vienna (Austria); Kraus, Petra [ASH DEC Umwelt AG, Donaufelderstrasse 101/4/5, A-1210 Vienna (Austria); Rechberger, Helmut [Institute for Water Quality, Resource and Waste Management, Vienna University of Technology, Karlsplatz 13/226, A-1040 Vienna (Austria); Winter, Franz, E-mail: franz.winter@tuwien.ac.at [Institute of Chemical Engineering, Vienna University of Technology, Getreidemarkt 9/166, A-1060 Vienna (Austria)

2011-06-15T23:59:59.000Z

245

U.S. Department of Energy Categorical Exclusion Determination Form  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Dissolution of Sludge Constituents in Glycolate-Containing 2H Evaporator Rad Feed Solution Dissolution of Sludge Constituents in Glycolate-Containing 2H Evaporator Rad Feed Solution Savannah River Site Aiken/Aiken/South Carolina Glycolic acid is being studied as an alternate reductant in the Defense Waste Processing Facility (DWPF) feed preparation process. It will either be a total or partial replacement for the formic acid that is currently used. The DWPF recycle stream serves as a portion of the feed to the 2H Evaporator. The DWPF recycle stream in addition to containing sludge will also contain glycolate. This testing seeks to determine the extent to which sludge constituents (Pu, U, Fe, etc.) dissolve (or the solubility of sludge constituents) in the glycolate-containing 2H Evaporator feed solution (Tank 43H). B3.6 - Small-scale research and development, laboratory operations, and pilot projects

246

Poland petroleum refinery sludge lagoon demonstration project  

SciTech Connect

The US Department of Energy and the Institute for Ecology of Industrial Area have been working together to develop mutually beneficial, cost-effective environmental remediation technologies such as the demonstration of bioremediation techniques for the clean up of acidic petroleum sludge impacted soils at an oil refinery in southern Poland. After an expedited site characterization, treatability study, and a risk assessment study, a remediation strategy was devised. The waste material was composed primarily of high molecular weight paraffinic and polynuclear aromatic hydrocarbons. A biopile design which employed a combination of passive and active aeration in conjunction with nutrient and surfactant application as used to increase the biodegradation of the contaminants of concern.

Altman, D.J.

2000-05-05T23:59:59.000Z

247

Tank 42 sludge-only process development for the Defense Waste Processing Facility (DWPF)  

SciTech Connect

Defense Waste Processing Facility (DWPF) requested the development of a sludge-only process for Tank 42 sludge since at the current processing rate, the Tank 51 sludge has been projected to be depleted as early as August 1998. Testing was completed using a non-radioactive Tank 42 sludge simulant. The testing was completed under a range of operating conditions, including worst case conditions, to develop the processing conditions for radioactive Tank 42 sludge. The existing Tank 51 sludge-only process is adequate with the exception that 10 percent additional acid is recommended during sludge receipt and adjustment tank (SRAT) processing to ensure adequate destruction of nitrite during the SRAT cycle.

Lambert, D.P.

2000-03-22T23:59:59.000Z

248

Hydrogen production during processing of radioactive sludge containing noble metals  

DOE Green Energy (OSTI)

Hydrogen was produced when radioactive sludge from Savannah River Site radioactive waste containing noble metals was reacted with formic acid. This will occur in a process tank in the Defense Waste Facility at SRS when waste is vitrified. Radioactive sludges from four tanks were tested in a lab-scale apparatus. Maximum hydrogen generation rates varied from 5 {times}10{sup {minus}7} g H{sub 2}/hr/g of sludge from the least reactive sludge (from Waste Tank 51) to 2 {times}10{sup {minus}4} g H{sub 2}/hr/g of sludge from the most reactive sludge (from Waste Tank 11). The time required for the hydrogen generation to reach a maximum varied from 4.1 to 25 hours. In addition to hydrogen, carbon dioxide and nitrous oxide were produced and the pH of the reaction slurry increased. In all cases, the carbon dioxide and nitrous oxide were generated before the hydrogen. The results are in agreement with large-scale studies using simulated sludges.

Ha, B.C.; Ferrara, D.M.; Bibler, N.E.

1992-01-01T23:59:59.000Z

249

Hydrogen production during processing of radioactive sludge containing noble metals  

DOE Green Energy (OSTI)

Hydrogen was produced when radioactive sludge from Savannah River Site radioactive waste containing noble metals was reacted with formic acid. This will occur in a process tank in the Defense Waste Facility at SRS when waste is vitrified. Radioactive sludges from four tanks were tested in a lab-scale apparatus. Maximum hydrogen generation rates varied from 5 {times}10{sup {minus}7} g H{sub 2}/hr/g of sludge from the least reactive sludge (from Waste Tank 51) to 2 {times}10{sup {minus}4} g H{sub 2}/hr/g of sludge from the most reactive sludge (from Waste Tank 11). The time required for the hydrogen generation to reach a maximum varied from 4.1 to 25 hours. In addition to hydrogen, carbon dioxide and nitrous oxide were produced and the pH of the reaction slurry increased. In all cases, the carbon dioxide and nitrous oxide were generated before the hydrogen. The results are in agreement with large-scale studies using simulated sludges.

Ha, B.C.; Ferrara, D.M.; Bibler, N.E.

1992-09-01T23:59:59.000Z

250

SLUDGE RETRIEVAL FROM HANFORD K WEST BASIN SETTLER TANKS  

SciTech Connect

In 2010, an innovative, remotely operated retrieval system was deployed to successfully retrieve over 99.7% of the radioactive sludge from ten submerged tanks in Hanford's K-West Basin. As part of K-West Basin cleanup, the accumulated sludge needed to be removed from the 0.5 meter diameter by 5 meter long settler tanks and transferred approximately 45 meters to an underwater container for sampling and waste treatment. The abrasive, dense, non-homogeneous sludge was the product of the washing process of corroded nuclear fuel. It consists of small (less than 600 micron) particles of uranium metal, uranium oxide, and various other constituents, potentially agglomerated or cohesive after 10 years of storage. The Settler Tank Retrieval System (STRS) was developed to access, mobilize and pump out the sludge from each tank using a standardized process of retrieval head insertion, periodic high pressure water spray, retraction, and continuous pumping of the sludge. Blind operations were guided by monitoring flow rate, radiation levels in the sludge stream, and solids concentration. The technology developed and employed in the STRS can potentially be adapted to similar problematic waste tanks or pipes that must be remotely accessed to achieve mobilization and retrieval of the sludge within.

ERPENBECK EG; LESHIKAR GA

2011-01-13T23:59:59.000Z

251

An Abstract Model of VHS Case Study 1 (Experimental Batch Plant)  

E-Print Network (OSTI)

In this work we describe the verification of safety properties for the experimental batch plant of case study 1 using the model checker SMV.

Ur Informatik; Und Praktische Mathematik; Lehrstuhl F; Ben Lukoschus; Ben Lukoschus

1999-01-01T23:59:59.000Z

252

Treatment of biomass gasification wastewater using a combined wet air oxidation/activated sludge process  

DOE Green Energy (OSTI)

A lab-scale treatability study for using thermal and biological oxidation to treat a biomass gasification wastewater (BGW) having a chemical oxygen demand (COD) of 46,000 mg/l is described. Wet air oxidation (WA0) at 300/sup 0/C and 13.8 MPa (2000 psi) was used to initially treat the BGW and resulted in a COD reduction of 74%. This was followed by conventional activated sludge treatment using operating conditions typical of municipal sewage treatment plants. This resulted in an additional 95% COD removal. Overall COD reduction for the combined process was 99%. A detailed chemical analysis of the raw BGW and thermal and biological effluents was performed using gas chromatography/mass spectrometry (GC/MS). These results showed a 97% decrease in total extractable organics with WA0 and a 99.6% decrease for combined WA0 and activated sludge treatment. Components of the treated waters tended to be fewer in number and more highly oxidized. An experiment was conducted to determine the amount of COD reduction caused by volatilization during biological treatment. Unfortunately, this did not yield conclusive results. Treatment of BGW using WA0 followed by activated sludge appears to be very effective and investigations at a larger scale are recommended.

English, C.J.; Petty, S.E.; Sklarew, D.S.

1983-02-01T23:59:59.000Z

253

EM-31 ALTERNATIVE AND ENHANCED CHEMICAL CLEANING PROGRAM FOR SLUDGE HEEL REMOVAL - 11220  

Science Conference Proceedings (OSTI)

Mixtures of oxalic acid with nitric acid have been shown to be superior to oxalic acid alone for the dissolution of iron-rich High Level Waste sludge heels. Optimized conditions resulting in minimal oxalate usage and stoichiometric iron dissolution (based on added oxalate ion) have been determined for hematite (a primary sludge iron phase) in oxalic/nitric acid mixtures. The acid mixtures performed better than expected based on the solubility of hematite in the individual acids through a synergistic effect in which the preferred 1:1 Fe:oxalate complex is formed. This allows for the minimization of oxalate additions to the waste stream. Carbon steel corrosion rates were measured in oxalic/nitric acid mixtures to evaluate the impacts of chemical cleaning with these solutions on waste tank integrity. Manageable corrosion rates were observed in the concentration ranges of interest for an acid contact timescale of 1 month. Kinetics tests involving hematite and gibbsite (a primary sludge aluminum phase) have confirmed that {ge}90% solids dissolution occurs within 3 weeks. Based on these results, the chemical cleaning conditions recommended to promote minimal oxalate usage and manageable corrosion include: 0.5 wt. % oxalic acid/0.175 M nitric acid mixture, 50 C, 2-3 week contact time with agitation.

King, W.; Hay, M.; Wiersma, B.; Pennebaker, F.

2010-12-10T23:59:59.000Z

254

K-Area and Par Pond Sewage Sludge Application Sites groundwater monitoring report: Second quarter 1993  

Science Conference Proceedings (OSTI)

During second quarter 1993, samples from the three monitoring wells at the K-Area site (KSS series) and the three monitoring wells at the Par Pond site (PSS series) were analyzed for constituents required by South Carolina Department of Health and Environmental Control Construction Permit 13,173 and for other constituents as part of the Savannah River Site (SRS) Groundwater Monitoring Program. This report describes monitoring results that exceeded the final Primary Drinking Water Standards (PDWS) or the SRS flagging criteria. During second quarter 1993, no constituents exceeded the final PDWS or any other flagging criteria at the K-Area and Par Pond Sewage Sludge Application Sites. During first quarter 1993, aluminum and iron exceeded the SRS Flag 2 criteria in one or more of the KSS and the PSS wells. These constituents were not analyzed second quarter 1993. In the KSS well series, the field measurement for alkalinity ranged as high as 35 mg/L in well KSS 1D. Alkalinity measurements were zero in the PSS wells, except for a single measurement of 1 mg/L in well PSS 1D. Historical and current water-level elevations at the K-Area Sewage Sludge Application Site indicate that the groundwater flow direction is south to southwest (SRS grid coordinates). The groundwater flow direction at the Par Pond Sewage Sludge Application Site could not be determined second quarter 1993.

Not Available

1993-10-01T23:59:59.000Z

255

Characterization Data Package for Containerized Sludge Samples Collected from Engineered Container SCS-CON-210  

SciTech Connect

This data package contains the K Basin sludge characterization results obtained by Pacific Northwest National Laboratory during processing and analysis of four sludge core samples collected from Engineered Container SCS-CON-210 in 2010 as requested by CH2M Hill Plateau Remediation Company. Sample processing requirements, analytes of interest, detection limits, and quality control sample requirements are defined in the KBC-33786, Rev. 2. The core processing scope included reconstitution of a sludge core sample distributed among four to six 4-L polypropylene bottles into a single container. The reconstituted core sample was then mixed and subsampled to support a variety of characterization activities. Additional core sludge subsamples were combined to prepare a container composite. The container composite was fractionated by wet sieving through a 2,000 micron mesh and a 500-micron mesh sieve. Each sieve fraction was sampled to support a suite of analyses. The core composite analysis scope included density determination, radioisotope analysis, and metals analysis, including the Waste Isolation Pilot Plant Hazardous Waste Facility Permit metals (with the exception of mercury). The container composite analysis included most of the core composite analysis scope plus particle size distribution, particle density, rheology, and crystalline phase identification. A summary of the received samples, core sample reconstitution and subsampling activities, container composite preparation and subsampling activities, physical properties, and analytical results are presented. Supporting data and documentation are provided in the appendices. There were no cases of sample or data loss and all of the available samples and data are reported as required by the Quality Assurance Project Plan/Sampling and Analysis Plan.

Fountain, Matthew S.; Fiskum, Sandra K.; Baldwin, David L.; Daniel, Richard C.; Bos, Stanley J.; Burns, Carolyn A.; Carlson, Clark D.; Coffey, Deborah S.; Delegard, Calvin H.; Edwards, Matthew K.; Greenwood, Lawrence R.; Neiner, Doinita; Oliver, Brian M.; Pool, Karl N.; Schmidt, Andrew J.; Shimskey, Rick W.; Sinkov, Sergey I.; Snow, Lanee A.; Soderquist, Chuck Z.; Thompson, Christopher J.; Trang-Le, Truc LT; Urie, Michael W.

2013-09-10T23:59:59.000Z

256

Sewage Sludge Management Rule (West Virginia) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sewage Sludge Management Rule (West Virginia) Sewage Sludge Management Rule (West Virginia) Sewage Sludge Management Rule (West Virginia) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State West Virginia Program Type Siting and Permitting This rule establishes requirements for the permitting siting, bonding, installation, establishment, construction, modification, and operation of any facility that generates, processes, recycles and/or disposes of sewage

257

Shear Strength Measurement Benchmarking Tests for K Basin Sludge Simulants  

SciTech Connect

Equipment development and demonstration testing for sludge retrieval is being conducted by the K Basin Sludge Treatment Project (STP) at the MASF (Maintenance and Storage Facility) using sludge simulants. In testing performed at the Pacific Northwest National Laboratory (under contract with the CH2M Hill Plateau Remediation Company), the performance of the Geovane instrument was successfully benchmarked against the M5 Haake rheometer using a series of simulants with shear strengths (?) ranging from about 700 to 22,000 Pa (shaft corrected). Operating steps for obtaining consistent shear strength measurements with the Geovane instrument during the benchmark testing were refined and documented.

Burns, Carolyn A.; Daniel, Richard C.; Enderlin, Carl W.; Luna, Maria; Schmidt, Andrew J.

2009-06-10T23:59:59.000Z

258

Sludge Heel Removal Analysis for Slurry Pumps of Tank 11  

SciTech Connect

Computational fluid dynamics methods were used to develop and recommend a slurry pump operational strategy for sludge heel removal in Tank 11. Flow patterns calculated by the model were used to evaluate the performance of various combinations of operating pumps and their orientation. The models focused on removal of the sludge heel located at the edge of Tank 11 using the four existing slurry pumps. The models and calculations were based on prototypic tank geometry and expected normal operating conditions as defined by Tank Closure Project (TCP) Engineering. Computational fluid dynamics models of Tank 11 with different operating conditions were developed using the FLUENT(tm) code. The modeling results were used to assess the efficiency of sludge suspension and removal operations in the 75-ft tank. The models employed a three-dimensional approach, a two-equation turbulence model, and an approximate representation of flow obstructions. The calculated local velocity was used as a measure of sludge removal and mixing capability. For the simulations, a series of the modeling calculations was performed with indexed pump orientations until an efficient flow pattern near the potential location of the sludge mound was established for sludge removal. The calculated results demonstrated that the existing slurry pumps running at 1600 rpm could remove the sludge mound from the tank with a 103 in. liquid level, based on a minimum sludge suspension velocity of 2.27 ft/sec. In this case, the only exception is the region within about 2 ft. from the tank wall. Further results showed that the capabilities of sludge removal were affected by the indexed pump orientation, the number of operating pumps, and the pump speed. A recommended operational strategy for an efficient flow pattern was developed to remove the sludge mound assuming that local fluid velocity can be used as a measure of sludge suspension and removal. Sensitivity results showed that for a given pump speed, a higher tank level and a lower pump nozzle elevation would result in better performance in suspending and removing the sludge. The results also showed that the presence of flow obstructions such as valve housing structure were advantageous for certain pump orientations.

Lee, S.Y.

2003-09-30T23:59:59.000Z

259

CX-006609: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9: Categorical Exclusion Determination 9: Categorical Exclusion Determination CX-006609: Categorical Exclusion Determination EM-31 Alternative Chemical Cleaning (ACC) Program CX(s) Applied: B3.6 Date: 05/24/2010 Location(s): Aiken, South Carolina Office(s): Savannah River Operations Office Two types of testing will be conducted. Dissolution testing of sludge materials and organic destruction scoping tests with spent acids containing dissolved sludge materials. (1) Dissolution Testing - Dissolution testing will involve treatment of sludge simulants and known mineral phases with inorganic acids, carboxylic acids, mixtures of acids, other complexants, and caustic. The solubilities of selected components and the fate of various species will be examined under a range of conditions. Testing will utilize sludge simulants and simple, known mineral phases, or mixtures of

260

CX-005861: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1: Categorical Exclusion Determination 1: Categorical Exclusion Determination CX-005861: Categorical Exclusion Determination Pretreatment Engineering Platform (PEP) Sludge Simulant Preparation CX(s) Applied: B3.6 Date: 03/17/2011 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office Sludge simulant is needed for rotary microfliter (RMF) testing. The Pretreatment Engineering Platform (PEP) sludge simulant is a blend of the following five major components: Iron-rich sludge simulant, specific supernate simulant, aluminum hydroxide solids, aluminum oxyhydroxide solids, and sodium oxalate solids. The specific supernate simulant has the following components: Sodium oxalate, aluminum nitrate, sodium phosphate, sodium sulfate, sodium nitrate, sodium hydroxide, sodium nitrite, and

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

CX-000803: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3: Categorical Exclusion Determination 3: Categorical Exclusion Determination CX-000803: Categorical Exclusion Determination Production of Hazardous Enhanced Chemical Cleaning Sludge Simulants CX(s) Applied: B3.6 Date: 01/05/2010 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office Engineering Development Laboratory (EDL) will produce sludge simulants that contain hazardous materials and are sufficiently resistant to acid dissolution to appropriately represent Savannah River Site sludges based on recipes provided for F and H area Tanks (Reference EEC No. TC-W-2009-070). EDL will produce about 50 gallons of each of the three sludges and ship some to AREVA in Lynchburg, Virginia for additional testing. An additional 50 gallons of the blend simulant will be produced by EDL for delivery to

262

Rules and Regulations for Sewage Sludge Management (Rhode Island)  

Energy.gov (U.S. Department of Energy (DOE))

The purpose of these rules and regulations is to ensure that sewage sludge that is treated, land applied, disposed, distributed, stockpiled or transported in the State of Rhode Island is done so in...

263

Package Safety Analysis Assessment for Sludge Transportation System  

SciTech Connect

This package safety analysis assessment demonstrates that the Sludge Transportation System meets the acceptance criteria for an equivalent package as specified in DOE/RL-2001-36, Hanford Sitewide Transportation Safety Document for onsite shipment.

ROMANO, T.

2003-03-19T23:59:59.000Z

264

Novel Nanoscale Materials Reduce Electricity Needed for Sludge  

E-Print Network (OSTI)

Sludge Digestion Dewatering (Centrifuge/ Belt Filter Press) Solids for Drying/Disposal Return Centrate. Finally, there will be a reduction of greenhouse gas emissions during shipment for disposal. Project

265

Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Reduces  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Reduces the Risk along the Columbia River Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Reduces the Risk along the Columbia River September 13, 2012 - 12:00pm Addthis Media Contacts Cameron Salony, DOE Cameron.Salony@rl.doe.gov 509-376-0402 Dee Millikin, CH2M HILL Plateau Remediation Company Dee_Millikin@rl.gov 509-376-1297 RICHLAND, WASH. - The U.S. Department of Energy (DOE) and contractor CH2M HILL Plateau Remediation Company (CH2M HILL) announced today the removal of the first phase of highly radioactive sludge from under water storage in the K West Basin about 400 yards away from the Columbia River. "This is a major step forward in protecting the river and a historic

266

Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Reduces  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Reduces the Risk along the Columbia River Highly Radioactive Sludge Removal Complete: Historic Cleanup Effort Reduces the Risk along the Columbia River September 13, 2012 - 12:00pm Addthis Media Contacts Cameron Salony, DOE Cameron.Salony@rl.doe.gov 509-376-0402 Dee Millikin, CH2M HILL Plateau Remediation Company Dee_Millikin@rl.gov 509-376-1297 RICHLAND, WASH. - The U.S. Department of Energy (DOE) and contractor CH2M HILL Plateau Remediation Company (CH2M HILL) announced today the removal of the first phase of highly radioactive sludge from under water storage in the K West Basin about 400 yards away from the Columbia River. "This is a major step forward in protecting the river and a historic

267

Marketing coal ash, slag, and sludge  

Science Conference Proceedings (OSTI)

The increase in coal-fired power plants and tighter environmental problems have put utilities in the position of marketing coal ash, slag, and sludge by turning waste products into a resource. Many utilities are looking beyond road and structural fill uses in their marketing efforts. Slag can be made into sandblasting grit, aggregate, and roofing granules, or used for soil stabilization or the chemical fixation of municipal wastes. Composition and collection variations discourage many utilities from marketing their by-products, while availability can be a problem for customers if the power plant should shut down. Other problems include storage and transportation, competition, and institutional barriers. Documentation of the fly ash, bottom ash, boiler slag, and scrubber waste markets by the Electric Power Research Institute considers these factors and develops a marketing method to help utilities evaluate and promote their product. (DCK)

Lihach, N.; Golden, D.; Komai, R.; Maulbetsch, J.

1982-12-01T23:59:59.000Z

268

A real-time warehouse operations planning system for small batch replenishment problems in production environment  

Science Conference Proceedings (OSTI)

A factory consists of numerous production workstations, multiple production lines and many production floors. Due to the characteristics of just-in-time and make-to-order mode manufacturing, small batches of production materials are required for production ... Keywords: Genetic algorithm (GA), Radio frequency identification (RFID) technology, Small batch replenishment problem

T. C. Poon; K. L. Choy; F. T. S. Chan; G. T. S. Ho; A. Gunasekaran; H. C. W. Lau; H. K. H. Chow

2011-07-01T23:59:59.000Z

269

Single-machine batch delivery scheduling with an assignable common due date and controllable processing times  

Science Conference Proceedings (OSTI)

We consider single-machine batch delivery scheduling with an assignable common due date and controllable processing times, which vary as a convex function of the amounts of a continuously divisible common resource allocated to individual jobs. Finished ... Keywords: Batch delivery, Common due date, Resource allocation, Scheduling

Yunqiang Yin, T. C. E. Cheng, Shuenn-Ren Cheng, Chin-Chia Wu

2013-08-01T23:59:59.000Z

270

Separation of organic ion exchange resins from sludge -- engineering study  

SciTech Connect

This engineering study evaluates the use of physical separation technologies to separate organic ion exchange resin from KE Basin sludge prior to nitric acid dissolution. This separation is necessitate to prevent nitration of the organics in the acid dissolver. The technologies under consideration are: screening, sedimentation, elutriation. The recommended approach is to first screen the Sludge and resin 300 microns then subject the 300 microns plus material to elutriation.

Duncan, J.B.

1998-08-25T23:59:59.000Z

271

Design, implementation, and operation of a class based batch queue scheduler for VAX/VMS  

SciTech Connect

Fermilab found that the standard VMS batch configuration options were inadequate for the job mix that exists on the Fermilab central computer facility VAX cluster. Accordingly, Fermilab designed and implemented a class based batch queue scheduler. This scheduler makes use of the standard VMS job controller and batch system. Users interact with the scheduler at job submission time by specification of CPU time limits and batch job characteristics. This scheduler allows Fermilab to make efficient use of our large heterogeneous VAX cluster which contains machines ranging from a VAX 780 to a VAX 8800. The scheduler was implemented using the VMS system services $GETQUI and $SNDJBC, without changes to the existing VMS job scheduler. As a result, the scheduler should remain compatible with future VMS versions. This session will discuss the design goals, implementation, and operational experience with Fermilab's class based batch queue scheduler.

Chadwick, K.

1988-05-20T23:59:59.000Z

272

Sludge storage lagoon biogas recovery and use. Volume 2  

Science Conference Proceedings (OSTI)

The City of Memphis has two wastewater treatment plants. The SWTP employs two large anaerobic digestion sludge lagoons as part of the overall sludge treatment system. Although these lagoons are effective in concentrating and digesting sludge, they can generate offensive odors. The SWTP uses aerobic digesters to partially stabilize the sludge and help reduce objectionable odors before it enters the lagoons. The anaerobic digestion of sludge in the lagoons results in the dispersion of a large quantity of biogas into the atmosphere. The City realized that if the lagoons could be covered, the odor problem could be resolved, and at the same, time, biogas could be recovered and utilized as a source of energy. In 1987, the City commissioned ADI International to conduct a feasibility study to evaluate alternative methods of covering the lagoons and recovering and utilizing the biogas. The study recommended that the project be developed in two phases: (1) recovery of the biogas and (2) utilization of the biogas. Phase 1 consists of covering the two lagoons with an insulated membrane to control odor and temperature and collect the biogas. Phase 1 was found to be economically feasible and offered a unique opportunity for the City to save substantial operating costs at the treatment facility. The Memphis biogas recovery project is the only application in the world where a membrane cover has been used on a municipal wastewater sludge lagoon. It is also the largest lagoon cover system in the world.

Muller, D.; Norville, C. [Memphis and Shelby County Div. of Planning and Development, TN (United States)

1991-07-01T23:59:59.000Z

273

Characterization of Settler Tank and KW Container Sludge Simulants  

SciTech Connect

The Sludge Treatment Project (STP), managed by CH2M Hill Plateau Remediation Company (CHPRC) has specified base formulations for non-radioactive sludge simulants for use in the development and testing of equipment for sludge sampling, retrieval, transport, and processing. In general, the simulant formulations are based on the average or design-basis physical and chemical properties obtained by characterizing sludge samples. The simulants include surrogates for uranium metal, uranium oxides (agglomerates and fine particulate), and the predominant chemical phases (iron and aluminum hydroxides, sand). Specific surrogate components were selected to match the nominal particle-size distribution and particle-density data obtained from sludge sample analysis. Under contract to CHPRC, Pacific Northwest National Laboratory (PNNL) has performed physical and rheological characterization of simulants, and the results are reported here. Two base simulant types (dry) were prepared by STP staff at the Maintenance and Storage Facility and received by PNNL on February 12, 2009: Settler Tank Simulant and KW Container Sludge Simulant. The objectives of this simulant characterization effort were to provide baseline characterization data on simulants being used by STP for process development and equipment testing and provide a high-level comparison of the simulant characteristics to the targets used to formulate the simulants.

Burns, Carolyn A.; Luna, Maria; Schmidt, Andrew J.

2009-05-12T23:59:59.000Z

274

SLUDGE TREATMENT PROJECT ALTERNATIVES ANALYSIS SUMMARY REPORT [VOLUME 1  

SciTech Connect

Highly radioactive sludge (containing up to 300,000 curies of actinides and fission products) resulting from the storage of degraded spent nuclear fuel is currently stored in temporary containers located in the 105-K West storage basin near the Columbia River. The background, history, and known characteristics of this sludge are discussed in Section 2 of this report. There are many compelling reasons to remove this sludge from the K-Basin. These reasons are discussed in detail in Section1, and they include the following: (1) Reduce the risk to the public (from a potential release of highly radioactive material as fine respirable particles by airborne or waterborn pathways); (2) Reduce the risk overall to the Hanford worker; and (3) Reduce the risk to the environment (the K-Basin is situated above a hazardous chemical contaminant plume and hinders remediation of the plume until the sludge is removed). The DOE-RL has stated that a key DOE objective is to remove the sludge from the K-West Basin and River Corridor as soon as possible, which will reduce risks to the environment, allow for remediation of contaminated areas underlying the basins, and support closure of the 100-KR-4 operable unit. The environmental and nuclear safety risks associated with this sludge have resulted in multiple legal and regulatory remedial action decisions, plans,and commitments that are summarized in Table ES-1 and discussed in more detail in Volume 2, Section 9.

FREDERICKSON JR; ROURK RJ; HONEYMAN JO; JOHNSON ME; RAYMOND RE

2009-01-19T23:59:59.000Z

275

Caustic Leaching of SRS Tank 12H Sludge With and Without Chelating Agents  

SciTech Connect

The primary objective of this study was to measure the effect of adding triethanolamine (TEA) to caustic leaching solutions to improve the solubility of aluminum in actual tank-waste sludge. High-level radioactive waste sludge that had a high aluminum assay was used for the tests. This waste, which originated with the processing of aluminum-clad/aluminum-alloy fuels, generates high levels of heat because of the high {sup 90}Sr concentration and contains hard-to-dissolve boehmite phases. In concept, a chelating agent, such as TEA, can both improve the dissolution rate and increase the concentration in the liquid phase. For this reason, TEA could also increase the solubility of other sludge components that are potentially problematic to downstream processing. Tests were conducted to determine if this were the case. Because of its relatively high vapor pressure, process design should include methods to minimize losses of the TEA. Sludge was retrieved from tank 12H at the Savannah River Site by on-site personnel, and then shipped to Oak Ridge National Laboratory for the study. The sludge contained a small quantity of rocky debris. One slate-like flat piece, which had approximate dimensions of 1 1/4 x 1/2 x 1/8 in., was recovered. Additional gravel-like fragments with approximate diameters ranging from 1/8 to 1/4 in. were also recovered by sieving the sludge slurry through a 1.4-mm square-pitch stainless steel mesh. These particles ranged from a yellow quartz-like material to grey-colored gravel. Of the 32.50 g of sludge received, the mass of the debris was only 0.89 g, and the finely divided sludge comprised {approx}97% of the mass. The sludge was successfully subdivided into uniform aliquots during hot-cell operations. Analytical measurements confirmed the uniformity of the samples. The smaller sludge samples were then used as needed for leaching experiments conducted in a glove box. Six tests were performed with leachate concentrations ranging from 0.1 to 3.0 m NaOH, 0 to 3.0 m TEA and 0 to 2.9 m NaNO{sub 3}. Figure ES.1 illustrates the leaching of aluminum in all six tests. One test was performed at an operating temperature of 80 C to obtain baseline data, and the remaining five tests were all performed at 60 C. A leaching solution of 3.0 m NaOH was used for the test performed at 80 C and for one of the tests performed at 60 C. These results indicated that more aluminum entered the solution at the higher temperature, though equilibrium was achieved at both temperatures within {approx}10 days. The addition of TEA significantly increased the concentration of aluminum in the leachate, and the concentration continued to increase even after 11 days of processing. The fraction of aluminum dissolved at 60EC increased from {approx}35% using 3.0 m NaOH alone to {approx}87% using a combination of 3.0 m NaOH and 3.0 m TEA. The high-nitrate, low-hydroxide solutions did not significantly dissolve the aluminum, because aluminate ion could not be produced. A small addition of TEA had no effect on this process. The use of TEA also increased the solubility of some other sludge components. The fractions of copper, nickel, and iron that were dissolved increased to 72, 13, and 52%, respectively. However, the original fractions of these metals were only 0.055, 0.72, and 3.1%, respectively, of the dry mass of the sludge and therefore represent minor constituents. The presence of nickel in the leachate did have a dramatic effect on its color, which changed from light yellow to deep green as the nickel concentration increased. By comparison, the baseline leaching with 3.0 m NaOH at 60 C removed {approx}14% of the copper; iron and nickel were below the detectable limit.

Spencer, B.B.

2003-04-30T23:59:59.000Z

276

SLURRY MIX EVAPORATOR BATCH ACCEPTABILITY AND TEST CASES OF THE PRODUCT COMPOSITION CONTROL SYSTEM WITH THORIUM AS A REPORTABLE ELEMENT  

SciTech Connect

The Defense Waste Processing Facility (DWPF), which is operated by Savannah River Remediation, LLC (SRR), has recently begun processing Sludge Batch 6 (SB6) by combining it with Frit 418 at a nominal waste loading (WL) of 36%. A unique feature of the SB6/Frit 418 glass system, as compared to the previous glass systems processed in DWPF, is that thorium will be a reportable element (i.e., concentrations of elemental thorium in the final glass product greater than 0.5 weight percent (wt%)) for the resulting wasteform. Several activities were initiated based upon this unique aspect of SB6. One of these was an investigation into the impact of thorium on the models utilized in DWPF's Product Composition and Control System (PCCS). While the PCCS is described in more detail below, for now note that it is utilized by Waste Solidification Engineering (WSE) to evaluate the acceptability of each batch of material in the Slurry Mix Evaporator (SME) before this material is passed on to the melter. The evaluation employs models that predict properties associated with processability and product quality from the composition of vitrified samples of the SME material. The investigation of the impact of thorium on these models was conducted by Peeler and Edwards [1] and led to a recommendation that DWPF can process the SB6/Frit 418 glass system with ThO{sub 2} concentrations up to 1.8 wt% in glass. Questions also arose regarding the handling of thorium in the SME batch acceptability process as documented by Brown, Postles, and Edwards [2]. Specifically, that document is the technical bases of PCCS, and while Peeler and Edwards confirmed the reliability of the models, there is a need to confirm that the current implementation of DWPF's PCCS appropriately handles thorium as a reportable element. Realization of this need led to a Technical Task Request (TTR) prepared by Bricker [3] that identified some specific SME-related activities that the Savannah River National Laboratory (SRNL) was requested to conduct. SRNL issued a Task Technical and Quality Assurance (TT&QA) plan [4] in response to the SRR request. The conclusions provided in this report are that no changes need to be made to the SME acceptability process (i.e., no modifications to WSRC-TR-95-00364, Revision 5, are needed) and no changes need to be made to the Product Composition Control System (PCCS) itself (i.e. the spreadsheet utilized by Waste Solidification Engineering (WSE) for acceptability decisions does not require modification) in response to thorium becoming a reportable element for DWPF operations. In addition, the inputs and results for the two test cases requested by WSE for use in confirming the successful activation of thorium as a reportable element for DWPF operations during the processing of SB6 are presented in this report.

Edwards, T.

2010-10-07T23:59:59.000Z

277

Comparison of different liquid anaerobic digestion effluents as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer Compared methane production of solid AD inoculated with different effluents. Black-Right-Pointing-Pointer Food waste effluent (FWE) had the largest population of acetoclastic methanogens. Black-Right-Pointing-Pointer Solid AD inoculated with FWE produced the highest methane yield at F/E ratio of 4. Black-Right-Pointing-Pointer Dairy waste effluent (DWE) was rich of cellulolytic and xylanolytic bacteria. Black-Right-Pointing-Pointer Solid AD inoculated with DWE produced the highest methane yield at F/E ratio of 2. - Abstract: Effluents from three liquid anaerobic digesters, fed with municipal sewage sludge, food waste, or dairy waste, were evaluated as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover in mesophilic reactors. Three feedstock-to-effluent (F/E) ratios (i.e., 2, 4, and 6) were tested for each effluent. At an F/E ratio of 2, the reactor inoculated by dairy waste effluent achieved the highest methane yield of 238.5 L/kgVS{sub feed}, while at an F/E ratio of 4, the reactor inoculated by food waste effluent achieved the highest methane yield of 199.6 L/kgVS{sub feed}. The microbial population and chemical composition of the three effluents were substantially different. Food waste effluent had the largest population of acetoclastic methanogens, while dairy waste effluent had the largest populations of cellulolytic and xylanolytic bacteria. Dairy waste also had the highest C/N ratio of 8.5 and the highest alkalinity of 19.3 g CaCO{sub 3}/kg. The performance of solid-state batch anaerobic digestion reactors was closely related to the microbial status in the liquid anaerobic digestion effluents.

Xu Fuqing; Shi Jian [Department of Food, Agricultural and Biological Engineering, Ohio State University, Ohio Agricultural Research and Development Center, 1680 Madison Ave., Wooster, OH 44691 (United States); Lv Wen; Yu Zhongtang [Department of Animal Sciences, Ohio State University, Columbus, OH 43210 (United States); Li Yebo, E-mail: li.851@osu.edu [Department of Food, Agricultural and Biological Engineering, Ohio State University, Ohio Agricultural Research and Development Center, 1680 Madison Ave., Wooster, OH 44691 (United States)

2013-01-15T23:59:59.000Z

278

Sludge application and monitoring program on the Oak Ridge Reservation, 1986--1993  

DOE Green Energy (OSTI)

Municipal sewage sludge has been applied to forests and pastures on the Oak Ridge Reservation since 1983 as a method of both disposal and beneficial reuse. Application was carried out under Tennessee permits issued to the city of Oak Ridge for land disposal of sewage sludge. In conjunction with these applications, information has been collected concerning sludge quantity and characteristics, soil parameters, soil water constituents, groundwater quality, surface runoff water quality, and various chemical constituents in vegetation on application sites. This information provides (1) a record of sludge application on the DOE reservations and (2) documentation of changes in soil parameters following sludge application. The information also provides a basis for evaluating the implications of the land application of municipal sewage sludge for soil and water quality and for evaluating the fate of sludge constituents when sludge is either sprayed or injected on pasture sites or surface applied in forested sites. This report covers in detail sludge applications conducted from 1986 through 1993, with some data from the period between 1983 and 1986. Anaerobically digested liquid sludge (2% to 4% solids) from the city of Oak Ridge had a relatively high nitrogen content (8% dry weight) and average to low concentrations of potentially problematic metals, compared with typical municipal sludges. Few potentially hazardous organic chemicals were detected in the sludge, and when found, these were at very low concentrations. Oak Ridge sludge is somewhat unique in that it contains radionuclides ({sup 137}Cs, {sup 60}Co, {sup 131}I, uranium isotopes, {sup 90}Sr, and occasionally {sup 99}Tc) at concentrations much higher than typical municipal sludges. Land application of sewage sludge can dilute or destroy problematic sludge constituents while improving soil fertility. Correct management has made these sludge applications a model of environmentally responsible waste management.

Gunderson, C.A.; Larsen, I.L.; Boston, H.L.; Bradburn, D.M. [Oak Ridge National Lab., TN (United States); Van Miegroet, H. [Utah State Univ., Logan, UT (United States). Dept. of Forest Resources; Morris, J.L. [Jaycor, Inc., Oak Ridge, TN (United States); Walzer, A.E. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States). Central Environmental Compliance; Adler, T.C. [Bechtel National, Inc., Oak Ridge, TN (United States); Huq, M. [Oak Ridge Associated Universities, TN (United States)

1995-09-01T23:59:59.000Z

279

Vibration mills in the manufacturing technology of slurry fuel from unbeneficiated coal sludge  

Science Conference Proceedings (OSTI)

Coal-water slurry fuel (CWSF) is economically viable provided that its ash content does not exceed 30% and the amount water in the fuel is at most 45%. Two impoundments were revealed that have considerable reserves of waste coal useful for commercial manufacture of CWSF without the beneficiation step. One of the CWSF manufacture steps is the comminution of coal sludge to have a particle size required by the combustion conditions. Vibration mills, which are more compact and energy-intensive that drum mills, can be used in the CWSG manufacture process. The rheological characteristics of CWSF obtained from unbeneficiated waste coal were determined.

E.G. Gorlov; A.I. Seregin; G.S. Khodakov [Institute for Fossil Fuels, Moscow (Russia)

2008-08-15T23:59:59.000Z

280

Gas Generation Testing of Uranium Metal in Simulated K Basins Sludge and Grouted Sludge Waste Forms  

DOE Green Energy (OSTI)

The evolving plan for most of the KE and KW Basin sludges is disposition to WIPP as remote handled (RH) TRU. Because the hydrogen gas concentration in the sealed transportation cask destined for WIPP is limited by flammability safety, the number of containers and shipments to WIPP likely will be driven by the rate of hydrogen generated by the contained uranium metals reaction with water. Therefore, gas generation testing with uranium metal particles of known surface area and immobilized in candidate (grout) solidification matrices was used to identify the effectiveness of various candidate solidification matrices to inhibit the rate of the uranium metal-water reaction.

Delegard, Calvin H.; Schmidt, Andrew J.; Sell, Rachel L.; Sinkov, Sergei I.; Bryan, Samuel A.

2004-05-21T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

K Basin sludge polychlorinated biphenyl removal technology assessment  

Science Conference Proceedings (OSTI)

The two Hanford K Basins are water-filled concrete pools that contain over 2,100 metric tons of N Reactor fuel elements stored in aluminum or stainless steel canisters. During the time the fuel has been stored, approximately 50 m3 of heterogeneous solid material have accumulated in the basins. This material, referred to as sludge, is a mixture of fuel corrosion products, metallic bits of spent fuel and zirconium clad iron and metal corrosion products and silica from migrating sands. Some of the sludges also contain PCBs. The congener group of PCBs was identified as Aroclor 1254. The maximum concentration of sludge PCBS was found to be 140 ppm (as settled wet basis). However, the distribution of the PCBs is non-uniform throughout the sludge (i.e., there are regions of high and low concentrations and places where no PCBs are present). Higher concentrations could be present at various locations. Aroclors 1016/1242, 1221, 1248, 1254, and 1260 were identified and quantified in K West (KW) Canister sludge. In some of these samples, the concentration of 1260 was higher than 1254. The sludge requires pre-treatment to meet tank farm waste acceptance criteria, Among the numerous requirements, the sludge should be retreated so that it does not contain regulated levels of Toxic Substances Control Act (TSCA) compounds. Because of their stable chemistry and relative insolubility in water, PCBs are difficult to treat. They also resist degradation from heat and electrical charges. This stability has resulted in environmental persistence which has prompted the development of a variety of new cleanup processes including supercritical processes, advanced oxidation, dehalogenation and others. Hopefully, most of the new processes are discussed herein. Information on new processes are being received and will be evaluated in a future revision.

Ashworth, S.C.

1998-08-25T23:59:59.000Z

282

INITIAL CHARACTERIZATIONS AND SRAT SIMULATIONS OF FOUR SLUDGE MATRIX STUDY SIMULANTS  

DOE Green Energy (OSTI)

The Savannah River National Laboratory (SRNL) initiated a sludge matrix study to evaluate the impact of changing insoluble solid composition on the processing characteristics of slurries in the Defense Waste Processing Facility (DWPF). Three compositional ranges were developed for three groups of elements in the waste. The first was high iron/low aluminum versus low iron/high aluminum. The second was high calcium-manganese/low nickel, chromium, and magnesium versus low calcium-manganese/high nickel, chromium, and magnesium. The third was high noble metals (Ag, Pd, Rh, Ru) versus low noble metals. These three options can be combined to form eight distinct sludge compositions. The sludge matrix study called for testing each of these eight simulants near the minimum acid required for nitrite destruction and at a second acid level that produced significant hydrogen by noble metal catalyzed decomposition of formic acid. Four simulants were prepared based on the four possible combinations of the Al/Fe and Mn-Ca/Mg-Ni-Cr options. Preliminary simulant preparation work has already been documented. The four simulants can be used for both high and low noble metal concentration testing and high and low acid testing. This report summarizes preliminary testing of each of the four simulants at low noble metals and low acid stoichiometry. The remaining matrix study tests are on hold. Chemically processed simulant was needed for U. S. Department of Energy-Office of Environmental Management and DWPF funded melt rate studies. Therefore, a preliminary assessment of the processing characteristics of the four sludge matrix simulants was completed using the low noble metal concentration option to meet this need. Sludge Receipt and Adjustment Tank (SRAT) testing was at low total acid stoichiometry (near the minimum acid end of the stoichiometric acid window). Composition and physical property measurements were made on the SRAT products. Updated values for formate loss and nitrite-to-nitrate conversion were found that can be used in the acid calculations for future sludge matrix process simulations. A reasonable determination of the minimum acid requirement for nitrite destruction was found to be slightly less than 105% of the Koopman minimum stoichiometric acid equation prediction for all four simulants at the low noble metal concentrations. The Koopman minimum stoichiometric acid equation is based on supernate carbonate, plus total Mg and Ca, in addition to the usual DWPF inputs such as base equivalents and Mn. This group of four tests extends the range of bulk insoluble solids concentrations over which the new Koopman minimum stoichiometric acid equation has been validated. The low iron-low manganese case appeared to have somewhat more excess acid than the other three combinations. Preliminary results of the initial testing indicate: (1) Hydrogen generation rate was not an issue in these tests. (2) Mercury stripping was less efficient than expected at about 1000 g steam/g mercury stripped. Only about 25% of the initial concentration of 1.5 wt% Hg in the total solids was removed in 13-14 hours of boiling, when 70% needed to be removed to meet the DWPF SRAT product specification of 0.45 wt% in the total solids. (3) Foaminess was not an issue using the nominal antifoam addition strategy in these tests. (4) Ammonia generation was not an issue based on off-gas condensate analyses. (5) One of the SRAT products (an HM-type simulant) was much more viscous than the other three SRAT products even though it had the lowest wt% insoluble solids. More comprehensive results concerning the impact of insoluble solids composition on processing, melt rate, etc. must await completion of the full sludge matrix study experimental scope.

Koopman,D.; Lambert, D.

2009-12-10T23:59:59.000Z

283

Tc-99 Adsorption on Selected Activated Carbons - Batch Testing Results  

Science Conference Proceedings (OSTI)

CH2M HILL Plateau Remediation Company (CHPRC) is currently developing a 200-West Area groundwater pump-and-treat system as the remedial action selected under the Comprehensive Environmental Response, Compensation, and Liability Act Record of Decision for Operable Unit (OU) 200-ZP-1. This report documents the results of treatability tests Pacific Northwest National Laboratory researchers conducted to quantify the ability of selected activated carbon products (or carbons) to adsorb technetium-99 (Tc-99) from 200-West Area groundwater. The Tc-99 adsorption performance of seven activated carbons (J177601 Calgon Fitrasorb 400, J177606 Siemens AC1230AWC, J177609 Carbon Resources CR-1240-AW, J177611 General Carbon GC20X50, J177612 Norit GAC830, J177613 Norit GAC830, and J177617 Nucon LW1230) were evaluated using water from well 299-W19-36. Four of the best performing carbons (J177606 Siemens AC1230AWC, J177609 Carbon Resources CR-1240-AW, J177611 General Carbon GC20X50, and J177613 Norit GAC830) were selected for batch isotherm testing. The batch isotherm tests on four of the selected carbons indicated that under lower nitrate concentration conditions (382 mg/L), Kd values ranged from 6,000 to 20,000 mL/g. In comparison. Under higher nitrate (750 mg/L) conditions, there was a measureable decrease in Tc-99 adsorption with Kd values ranging from 3,000 to 7,000 mL/g. The adsorption data fit both the Langmuir and the Freundlich equations. Supplemental tests were conducted using the two carbons that demonstrated the highest adsorption capacity to resolve the issue of the best fit isotherm. These tests indicated that Langmuir isotherms provided the best fit for Tc-99 adsorption under low nitrate concentration conditions. At the design basis concentration of Tc 0.865 µg/L(14,700 pCi/L), the predicted Kd values from using Langmuir isotherm constants were 5,980 mL/g and 6,870 mL/g for for the two carbons. These Kd values did not meet the target Kd value of 9,000 mL/g. Tests conducted to ascertain the effects of changing pH showed that at pH values of 6.5 and 7.5, no significant differences existed in Tc-adsorption performance for three of the carbons, but the fourth carbon performed better at pH 7.5. When the pH was increased to 8.5, a slight decline in performance was observed for all carbons. Tests conducted to ascertain the temperature effect on Tc-99 adsorption indicated that at 21 ºC, 27 ºC, and 32 ºC there were no significant differences in Tc-99 adsorption for three of the carbons. The fourth carbon showed a noticeable decline in Tc-99 adsorption performance with increasing temperature. The presence of volatile organic compounds (VOCs) in the source water did not significantly affect Tc-99 adsorption on either of two carbons tested. Technetium-99 adsorption differed by less than 15% with or without VOCs present in the test water, indicating that Tc-99 adsorption would not be significantly affected if VOCs were removed from the water prior to contact with carbon.

Mattigod, Shas V.; Wellman, Dawn M.; Golovich, Elizabeth C.; Cordova, Elsa A.; Smith, Ronald M.

2010-12-01T23:59:59.000Z

284

Research of sludge compost maturity degree modeling method based on wavelet neural network for sewage treatment  

Science Conference Proceedings (OSTI)

Because of the complicated interaction of the sludge compost components, it makes the compost maturity degree judging system appear the nonlinearity and uncertainty. According to the physical circumstances of sludge compost, a compost maturity degree ...

Meijuan Gao; Jingwen Tian; Wei Jiang; Kai Li

2007-09-01T23:59:59.000Z

285

Characterization and Leach Testing for PUREX Cladding Waste Sludge (Group 3) and REDOX Cladding Waste Sludge (Group 4) Actual Waste Sample Composites  

SciTech Connect

A testing program evaluating actual tank waste was developed in response to Task 4 from the M-12 External Flowsheet Review Team (EFRT) issue response plan.(a) The testing program was subdivided into logical increments. The bulk water-insoluble solid wastes that are anticipated to be delivered to the Waste Treatment and Immobilization Plant (WTP) were identified according to type such that the actual waste testing could be targeted to the relevant categories. Eight broad waste groupings were defined. Samples available from the 222S archive were identified and obtained for testing. The actual wastetesting program included homogenizing the samples by group, characterizing the solids and aqueous phases, and performing parametric leaching tests. Two of the eight defined groups—plutonium-uranium extraction (PUREX) cladding waste sludge (Group 3, or CWP) and reduction-oxidation (REDOX) cladding waste sludge (Group 4, or CWR)—are the subjects of this report. Both the Group 3 and 4 waste composites were anticipated to be high in gibbsite, requiring caustic leaching. Characterization of the composite Group 3 and Group 4 waste samples confirmed them to be high in gibbsite. The focus of the Group 3 and 4 testing was on determining the behavior of gibbsite during caustic leaching. The waste-type definition, archived sample conditions, homogenization activities, characterization (physical, chemical, radioisotope, and crystal habit), and caustic leaching behavior as functions of time, temperature, and hydroxide concentration are discussed in this report. Testing was conducted according to TP-RPP-WTP-467.

Snow, Lanee A.; Buck, Edgar C.; Casella, Amanda J.; Crum, Jarrod V.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Fiskum, Sandra K.; Jagoda, Lynette K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Swoboda, Robert G.

2009-02-13T23:59:59.000Z

286

Multi-batch slip stacking in the Main Injector at Fermilab  

SciTech Connect

The Main Injector (MI) at Fermilab is planning to use multi-batch slip stacking scheme in order to increase the proton intensity at the NuMI target by about a factor of 1.5.[1] [2] By using multi-batch slip stacking, a total of 11 Booster batches are merged into 6, 5 double ones and one single. We have successfully demonstrated the multibatch slip stacking in MI and accelerated a record intensity of 4.6E13 particle per cycle to 120 GeV. The technical issues and beam loss mechanisms for multibatch slip stacking scheme are discussed.

Seiya, K.; Berenc, T.; Chase, B.; Dey, J.; Joireman, P.; Kourbanis, I.; Reid, J.; /Fermilab

2007-06-01T23:59:59.000Z

287

Optimal production and rationing policies of a make-to-stock production system with batch demand and backordering  

Science Conference Proceedings (OSTI)

In this paper, we consider the stock rationing problem of a single-item make-to-stock production/inventory system with multiple demand classes. Demand arrives as a Poisson process with a randomly distributed batch size. It is assumed that the batch demand ... Keywords: Batch demand, Inventory, Markov decision process, Production, Rationing

Jianjun Xu; Shaoxiang Chen; Bing Lin; Rohit Bhatnagar

2010-05-01T23:59:59.000Z

288

Feasibility report on criticality issues associated with storage of K Basin sludge in tanks farms  

Science Conference Proceedings (OSTI)

This feasibility study provides the technical justification for conclusions about K Basin sludge storage options. The conclusions, solely based on criticality safety considerations, depend on the treatment of the sludge. The two primary conclusions are, (1) untreated sludge must be stored in a critically safe storage tank, and (2) treated sludge (dissolution, precipitation and added neutron absorbers) can be stored in a standard Double Contained Receiver Tank (DCRT) or 241-AW-105 without future restrictions on tank operations from a criticality safety perspective.

Vail, T.S.

1997-05-29T23:59:59.000Z

289

Sludge Treatment and Extraction Technology Development: Results of FY 1993 studies  

SciTech Connect

This report describes experimental results from work conducted in FY 1993 under the Sludge Treatment and Extraction Technology Development Task of the Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project at Pacific Northwest Laboratory (PNL). Experiments were conducted in the following six general areas: (1) sludge washing, (2) sludge leaching, (3) sludge dissolution, (4) actinide separation by solvent extraction and extraction chromatography, (5) Sr separation by solvent extraction, and (6) extraction of Cs from acidic solution.

Lumetta, G.J.; Wagner, M.J.; Barrington, R.J.; Rapko, B.M.; Carlson, C.D.

1994-03-01T23:59:59.000Z

290

Marketing coal ash, slag, and sludge  

SciTech Connect

Investigates the selling of by-products of coal-fired power generation--fly ash, bottom ash, boiler slag, and scrubber sludge--by utilities for use in highways, parking lots, cement, roofing, bricks, and blocks. Points out that the EPA has drafted tough new regulations for solid-waste storage, transportation, and disposal that may soon cost power plants $25-$40 a ton to dispose of wastes. Reports that the EPRI is studying high-volume by-product applications that have low technology requirements (e.g. fly ash for use in highways, parking lots, and utility construction) and medium-volume, medium-technology applications (e.g. by-products used for cement manufacture, asphalt, blocks, bricks, roofing granules, and wallboards). Reveals that EPRI plans to eventually identify a representative set of perhaps half a dozen basic fly ashes, characterize them, do proportion studies of existing concrete mixes (including those with fly ash in them), and then develop guidelines for fly ash proportions in concrete.

Lihach, N.; Golden, D.; Komai, R.; Maulbetsch, J.

1982-12-01T23:59:59.000Z

291

INTEC SBW Solid Sludge Surrogate Recipe and Validation  

SciTech Connect

A nonhazardous INTEC tank farm sludge surrogate that incorporated metathesis reactions to generate solids from solutions of known elements present in the radioactive INTEC tank farm sodium-bearing waste sludges was formulated. Elemental analyses, physical property analyses, and filtration testing were performed on waste surrogate and tank farm waste samples, and the results were compared. For testing physical systems associated with moving the tank farm solids, the surrogate described in this report is the best currently available choice. No other available surrogate exhibits the noted similarities in behavior to the sludges. The chemical morphology, particle size distribution, and settling and flow characteristics of the surrogate were similar to those exhibited by the waste sludges. Nonetheless, there is a difference in chemical makeup of the surrogate and the tank farm waste. If a chemical treatment process were to be evaluated for final treatment and disposition of the waste sludges, the surrogate synthesis process would likely require modification to yield a surrogate with a closer matching chemical composition.

Maio, Vince; Janikowski, Stuart; Johnson, Jim; Maio, Vince; Pao, Jenn-Hai

2004-06-01T23:59:59.000Z

292

Computational fluid dynamics modelling of sewage sludge mixing in an anaerobic digester  

Science Conference Proceedings (OSTI)

In this paper, the development of a computational fluid dynamics (CFD) model to simulate the mechanical mixing of sewage sludge at laboratory scale is reported. The paper recommends a strategy for modelling mechanically mixed sewage sludge at laboratory ... Keywords: Biogas, CFD, Digestion, Energy, Non-Newtonian fluid, Sewage sludge, Turbulence

J. Bridgeman

2012-02-01T23:59:59.000Z

293

The Reactive Light Yellow Dye Wastewater Treatment by Sewage Sludge-Based Activated Carbon  

Science Conference Proceedings (OSTI)

The paper is aim to discuss the dye wastewater treatment by sewage sludge-based adsorbent. The adsorbent derived from sewage sludge, which produced through phosphoric acid-microwave method, and commercia activated carbon (ACC) were tested in the process ... Keywords: Sewage Sludge-based Activated Carbon (ACSS), the Reactive Light Yellow, Dye Wastewater, Adsorption

Yang Lijun; Dai Qunwei

2011-02-01T23:59:59.000Z

294

Please use "gres" settings in your batch scripts  

NLE Websites -- All DOE Office Websites (Extended Search)

Please use "gres" settings in your batch scripts Please use "gres" settings in your batch scripts Please use "gres" settings in your batch scripts September 4, 2012 by Helen He (0 Comments) We would like to encourage you to use the generic resources ("gres") setting for various file systems that your batch jobs use. This feature is currently available on Hopper and Carver. The advantage of this setting is that your jobs won't start (thus won't fail) during a scheduled file system maintenance. The syntax for the "gres" setting is: #PBS -l gres=filesystem1[%filesystem2%filesystem3...] (new recommendation) or #PBS -l gres=filesystem1:1[%filesystem2:1%filesystem3:1...] (as announced before) Note that the "%" character means "and". Therefore, if multiple file

295

Analysis of batching strategies for multi-item production with yield uncertainty  

E-Print Network (OSTI)

In this thesis, we investigate the batch sizing problem for a custom-job production facility. More specifically, given a production system that has been assigned several different types of custom jobs, we try to derive ...

Siow, Christopher (Christopher Shun Yi)

2008-01-01T23:59:59.000Z

296

Site Selection for Concrete Batch Plant to Support Plutonium Disposition Facilities at the Savannah River Site  

Science Conference Proceedings (OSTI)

WSRC conducted a site selection study to identify, assess, and rank candidate sites for an onsite concrete batch plant at the Savannah River Site in the vicinity of F-Area.

Wike, L.D.

2001-06-15T23:59:59.000Z

297

Uranium Metal Reaction Behavior in Water, Sludge, and Grout Matrices  

SciTech Connect

This report summarizes information and data on the reaction behavior of uranium metal in water, in water-saturated simulated and genuine K Basin sludge, and in grout matrices. This information and data are used to establish the technical basis for metallic uranium reaction behavior for the K Basin Sludge Treatment Project (STP). The specific objective of this report is to consolidate the various sources of information into a concise document to serve as a high-level reference and road map for customers, regulators, and interested parties outside the STP (e.g., external reviewers, other DOE sites) to clearly understand the current basis for the corrosion of uranium metal in water, sludge, and grout.

Delegard, Calvin H.; Schmidt, Andrew J.

2008-09-25T23:59:59.000Z

298

Uranium Metal Reaction Behavior in Water, Sludge, and Grout Matrices  

SciTech Connect

This report summarizes information and data on the reaction behavior of uranium metal in water, in water-saturated simulated and genuine K Basin sludge, and in grout matrices. This information and data are used to establish the technical basis for metallic uranium reaction behavior for the K Basin Sludge Treatment Project (STP). The specific objective of this report is to consolidate the various sources of information into a concise document to serve as a high-level reference and road map for customers, regulators, and interested parties outside the STP (e.g., external reviewers, other DOE sites) to clearly understand the current basis for the corrosion of uranium metal in water, sludge, and grout.

Delegard, Calvin H.; Schmidt, Andrew J.

2009-05-27T23:59:59.000Z

299

Hanford Sludge Simulant Selection for Soil Mechanics Property Measurement  

Science Conference Proceedings (OSTI)

The current System Plan for the Hanford Tank Farms uses relaxed buoyant displacement gas release event (BDGRE) controls for deep sludge (i.e., high level waste [HLW]) tanks, which allows the tank farms to use more storage space, i.e., increase the sediment depth, in some of the double-shell tanks (DSTs). The relaxed BDGRE controls are based on preliminary analysis of a gas release model from van Kessel and van Kesteren. Application of the van Kessel and van Kesteren model requires parametric information for the sediment, including the lateral earth pressure at rest and shear modulus. No lateral earth pressure at rest and shear modulus in situ measurements for Hanford sludge are currently available. The two chemical sludge simulants will be used in follow-on work to experimentally measure the van Kessel and van Kesteren model parameters, lateral earth pressure at rest, and shear modulus.

Wells, Beric E.; Russell, Renee L.; Mahoney, Lenna A.; Brown, Garrett N.; Rinehart, Donald E.; Buchmiller, William C.; Golovich, Elizabeth C.; Crum, Jarrod V.

2010-03-23T23:59:59.000Z

300

Supercritical Fluid Extraction of Bacterial and Archaeal Lipid Biomarkers from Anaerobically Digested Sludge  

E-Print Network (OSTI)

Abstract: Supercritical fluid extraction (SFE) was used in the analysis of bacterial respiratory quinone (RQ), bacterial phospholipid fatty acid (PLFA), and archaeal phospholipid ether lipid (PLEL) from anaerobically digested sludge. Bacterial RQ were determined using ultra performance liquid chromatography (UPLC). Determination of bacterial PLFA and archaeal PLEL was simultaneously performed using gas chromatography-mass spectrometry (GC-MS). The effects of pressure, temperature, and modifier concentration on the total amounts of RQ, PLFA, and PLEL were investigated by 23 experiments with five settings chosen for each variable. The optimal extraction conditions that were obtained through a multiple-response optimization included a pressure of 23.6 MPa, temperature of 77.6 °C, and 10.6 % (v/v) of methanol as the modifier. Thirty nine components of microbial lipid biomarkers were identified in the anaerobically digested sludge. Overall, the SFE method proved to be more effective, rapid, and quantitative for simultaneously extracting bacterial and archaeal lipid biomarkers, compared to conventional organic solvent extraction. This work shows the potential application of SFE as a routine method for the comprehensive analysis of microbial community structures in environmental assessments using the lipid biomarkers profile. Int. J. Mol. Sci. 2012, 13 3023

Muhammad Hanif; Yoichi Atsuta; Koichi Fujie; Hiroyuki Daimon

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Mechanism of Phosphorus Removal from Hanford Tank Sludge by Caustic Leaching  

SciTech Connect

Two experiments were conducted to explore the mechanism by which phosphorus is removed from Hanford tank sludge by caustic leaching. In the first experiment, a series of phosphate salts were treated with 3 M NaOH under conditions prototypic of the actual leaching process to be performed in the Waste Treatment and Immobilization Plant (WTP). The phosphates used were aluminum phosphate, bismuth phosphate, chromium(III) phosphate, and ?-tri-calcium phosphate; all of these phases have previously been determined to exist in Hanford tank sludge. The leachate solution was sampled at selected time intervals and analyzed for the specific metal ion involved (Al, Bi, Ca, or Cr) and for P (total and as phosphate). The solids remaining after completion of the caustic leaching step were analyzed to determine the reaction product. In the second experiment, the dependence of P removal from bismuth phosphate was examined as a function of the hydroxide ion concentration. It was anticipated that a plot of log[phosphate] versus log[hydroxide] would provide insight into the phosphorus-removal mechanism. This report describes the test activities outlined in Section 6.3.2.1, Preliminary Investigation of Phosphate Dissolution, in Test Plan TP-RPP-WTP-467, Rev.1. The objectives, success criteria, and test conditions of Section 6.3.2.1 are summarized here.

Lumetta, Gregg J.

2008-03-05T23:59:59.000Z

302

K East basin sludge volume estimates for integrated water treatment system  

Science Conference Proceedings (OSTI)

This document provides estimates of the volume of sludge expected from Integrated Process Strategy (IPS) processing of the fuel elements and in the fuel storage canisters in K East Basin. The original estimates were based on visual observations of fuel element condition in the basin and laboratory measurements of canister sludge density. Revision 1 revised the volume estimates of sludge from processing of the fuel elements based on additional data from evaluations of material from the KE Basin fuel subsurface examinations. A nominal Working Estimate and an upper level Working Bound is developed for the canister sludge and the fuel wash sludge components in the KE Basin.

Pearce, K.L.

1998-08-19T23:59:59.000Z

303

USE OF AN EQUILIBRIUM MODEL TO FORECAST DISSOLUTION EFFECTIVENESS, SAFETY IMPACTS, AND DOWNSTREAM PROCESSABILITY FROM OXALIC ACID AIDED SLUDGE REMOVAL IN SAVANNAH RIVER SITE HIGH LEVEL WASTE TANKS 1-15  

DOE Green Energy (OSTI)

This thesis details a graduate research effort written to fulfill the Magister of Technologiae in Chemical Engineering requirements at the University of South Africa. The research evaluates the ability of equilibrium based software to forecast dissolution, evaluate safety impacts, and determine downstream processability changes associated with using oxalic acid solutions to dissolve sludge heels in Savannah River Site High Level Waste (HLW) Tanks 1-15. First, a dissolution model is constructed and validated. Coupled with a model, a material balance determines the fate of hypothetical worst-case sludge in the treatment and neutralization tanks during each chemical adjustment. Although sludge is dissolved, after neutralization more is created within HLW. An energy balance determines overpressurization and overheating to be unlikely. Corrosion induced hydrogen may overwhelm the purge ventilation. Limiting the heel volume treated/acid added and processing the solids through vitrification is preferred and should not significantly increase the number of glass canisters.

KETUSKY, EDWARD

2005-10-31T23:59:59.000Z

304

GLYCOLIC-FORMIC ACID FLOWSHEET SLUDGE MATRIX STUDY  

Science Conference Proceedings (OSTI)

Testing was completed to demonstrate the viability of the newly developed glycolic acid/formic acid flowsheet on processing in the Defense Waste Processing Facility's (DWPF) Chemical Process Cell (CPC). The Savannah River National Laboratory (SRNL) initiated a sludge matrix study to evaluate the impact of changing insoluble solid composition on the processing characteristics of slurries in DWPF. Four sludge simulants were prepared to cover two compositional ranges in the waste. The first was high iron/low aluminum versus low iron/high aluminum (referred to as HiFe or LoFe in this report). The second was high calcium-manganese/low nickel, chromium, and magnesium versus low calcium-manganese/high nickel, chromium, and magnesium (referred to as HiMn or LoMn in this report). These two options can be combined to form four distinct sludge compositions. The sludge matrix study called for testing each of these four simulants near the minimum acid required for nitrite destruction (100% acid stoichiometry) and at a second acid level that produced significant hydrogen by noble metal catalyzed decomposition of formic acid (150% acid stoichiometry). Four simulants were prepared based on the four possible combinations of the Al/Fe and Mn-Ca/Mg-Ni-Cr options. Preliminary simulant preparation work has already been documented. The four simulants were used for high and low acid testing. Eight planned experiments (GF26 to GF33) were completed to demonstrate the viability of the glycolic-formic flowsheet. Composition and physical property measurements were made on the SRAT product. Composition measurements were made on the condensate from the Mercury Water Wash Tank (MWWT), Formic Acid Vent Condenser (FAVC), ammonia scrubber and on SRAT samples pulled throughout the SRAT cycle. Updated values for formate loss and nitrite-tonitrate conversion were found that can be used in the acid calculations for future sludge matrix process simulations with the glycolic acid/formic acid flowsheet. Preliminary results of the initial testing indicate: (1) Hydrogen generation rate was very low throughout all SRAT cycles. (2) The mercury concentration of the SRAT product was below the 0.8 wt% limit in all runs. (3) Nitrite in the SRAT product was aluminum sludges (LoFe, HM type sludges) were much more viscous than the Hi Fe sludges. At 100% acid stoichiometry, the SRAT products from the high aluminum sludges were very viscous but at 150% acid stoichiometry, the SRAT products from the high aluminum sludges were very thin. This makes the glycolic acid/formic acid flowsheet an improvement for processing more viscous sludges. (6) The pH of the SRAT products was from 2.7-3.1 for the 150% acid stoichiometry runs and 5.1-6.1 for the 100% acid stoichiometry runs, significantly lower than is typical of the baseline nitric acid/formic acid flowsheet.

Lambert, D.; Koopman, D.

2011-06-30T23:59:59.000Z

305

GLYCOLIC-FORMIC ACID FLOWSHEET SLUDGE MATRIX STUDY  

DOE Green Energy (OSTI)

Testing was completed to demonstrate the viability of the newly developed glycolic acid/formic acid flowsheet on processing in the Defense Waste Processing Facility's (DWPF) Chemical Process Cell (CPC). The Savannah River National Laboratory (SRNL) initiated a sludge matrix study to evaluate the impact of changing insoluble solid composition on the processing characteristics of slurries in DWPF. Four sludge simulants were prepared to cover two compositional ranges in the waste. The first was high iron/low aluminum versus low iron/high aluminum (referred to as HiFe or LoFe in this report). The second was high calcium-manganese/low nickel, chromium, and magnesium versus low calcium-manganese/high nickel, chromium, and magnesium (referred to as HiMn or LoMn in this report). These two options can be combined to form four distinct sludge compositions. The sludge matrix study called for testing each of these four simulants near the minimum acid required for nitrite destruction (100% acid stoichiometry) and at a second acid level that produced significant hydrogen by noble metal catalyzed decomposition of formic acid (150% acid stoichiometry). Four simulants were prepared based on the four possible combinations of the Al/Fe and Mn-Ca/Mg-Ni-Cr options. Preliminary simulant preparation work has already been documented. The four simulants were used for high and low acid testing. Eight planned experiments (GF26 to GF33) were completed to demonstrate the viability of the glycolic-formic flowsheet. Composition and physical property measurements were made on the SRAT product. Composition measurements were made on the condensate from the Mercury Water Wash Tank (MWWT), Formic Acid Vent Condenser (FAVC), ammonia scrubber and on SRAT samples pulled throughout the SRAT cycle. Updated values for formate loss and nitrite-tonitrate conversion were found that can be used in the acid calculations for future sludge matrix process simulations with the glycolic acid/formic acid flowsheet. Preliminary results of the initial testing indicate: (1) Hydrogen generation rate was very low throughout all SRAT cycles. (2) The mercury concentration of the SRAT product was below the 0.8 wt% limit in all runs. (3) Nitrite in the SRAT product was <100 mg/kg for all runs. (4) Foaminess was not an issue using the nominal antifoam addition strategy in these tests. (5) The high aluminum sludges (LoFe, HM type sludges) were much more viscous than the Hi Fe sludges. At 100% acid stoichiometry, the SRAT products from the high aluminum sludges were very viscous but at 150% acid stoichiometry, the SRAT products from the high aluminum sludges were very thin. This makes the glycolic acid/formic acid flowsheet an improvement for processing more viscous sludges. (6) The pH of the SRAT products was from 2.7-3.1 for the 150% acid stoichiometry runs and 5.1-6.1 for the 100% acid stoichiometry runs, significantly lower than is typical of the baseline nitric acid/formic acid flowsheet.

Lambert, D.; Koopman, D.

2011-06-30T23:59:59.000Z

306

CRAD, Management - Office of River Protection K Basin Sludge Waste System |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office of River Protection K Basin Sludge Waste Office of River Protection K Basin Sludge Waste System CRAD, Management - Office of River Protection K Basin Sludge Waste System May 2004 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2004 assessment of the Management at the Office of River Protection K Basin Sludge Waste System. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Management - Office of River Protection K Basin Sludge Waste System More Documents & Publications CRAD, Emergency Management - Office of River Protection K Basin Sludge Waste System CRAD, Conduct of Operations - Office of River Protection K Basin Sludge

307

GAS BEHAVIOR IN LARGE DIAMETER CONTAINERS (LCDS) DURING & FOLLOWING LOADING WITH 105K EAST NORTH LOADOUT PIT SLUDGE  

DOE Green Energy (OSTI)

105K East NLOP sludge is an exceptionally benign environment with respect to producing large volumes of hydrogen quickly. In fact, should the uranium metal-water reaction become the dominant reaction for production of hydrogen, only 96 liters of hydrogen gas per m{sup 3} of sludge can be produced before the uranium metal in the sludge is consumed by the reaction. Accordingly, in an LDC containing 2.5 m{sup 3} of sludge, only 240 liters of hydrogen can be produced from the uranium-metal-water reaction. One of the conservatisms applied in this model is that the consumption of uranium metal in the reaction is not considered. The only flammable gas of interest in the calculation is hydrogen because the LDC will be vented through HEPA-type filters making it impossible to exclude aid-oxygen from reaching the interior of the LDC. Accordingly, it is assumed that sufficient oxygen to support combustion is always present in the headspace of the LDC. Two hydrogen limits are examined: (1) The Lower Flammability Limit (LFL) for hydrogen when argon is initially used as the cover gas. Since the LDC will be vented through two 2 inch ports fitted with HEPA-type filters, air will enter the LDC, diluting and eventually replacing the argon cover gas by: (a) Barometric breathing of the LDC during storage prior to processing. (b) Breathing by thermal expansion and contraction of the headspace gases during and following the transportation process. (c) Diffusion of air through the HEPA-type filtered vents during storage and processing. The LFL for hydrogen in an argon-lair mixture is the same as the LFL for hydrogen when air is the only cover gas in the LDC headspace (4%). Regardless of the exact mechanism for diluting and eventually replacing the argon with air, the headspace of a vented LDC will be diluted and will eventually contain only air. When 25% air (5% oxygen) is present, flammability is possible. Accordingly, 4% (the bounding value) will be used as the LFL for hydrogen in all calculations. The limit for hydrogen for the transportation window calculations (5%), (i.e., the normal transportation time shall not exceed 1/2 the time for hydrogen to reach 5% in any void space of the shipping container). Unlike the four case methodology used in SNF-18133, and the three case methodology used in the NLOP Addendum to SNF-18133 Revision 0, this analysis presents only the analysis necessary to establish the Safety Basis for LDCs filled with 105K East North Loadout Pit sludge using the normal (flow-through fill) method and the alternate (batch fill) method for two storage/processing locations: storage and processing at Building 325 or storage and processing at T Plant.

SHELOR, J.L.

2004-09-23T23:59:59.000Z

308

Pretreatment of neutralized cladding removal waste sludge: Results of the second design basis experiment  

SciTech Connect

For several years, the Pacific Northwest Laboratory (PNL) has been investigating methods to pretreat Hanford neutralized cladding removal waste (NCRW) sludge. In the past, Zircaloy-clad metallic U fuel was chemically decladded using the Zirflex process; NCRW sludge was formed when the decladding solution was neutralized for storage in carbon-steel tanks. This sludge, which is currently stored in Tanks 103-AW and 105-AW on the Hanford Site, primarily consists of insoluble Zr hydroxides and/or oxides and NaF. Significant quantities of Al, La, U, as well as other insoluble minor constituents are present in the sludge, along with sodium and potassium nitrates, nitrites, and hydroxides in the interstitial liquid. The sludge contains about 2,000 nCi of transuranic (TRU) material per gram of dry sludge, and mixed fission products. Therefore, the sludge must be handled as high-level waste (HLW). The NCRW sludge must be pretreated before treatment (e.g., vitrification) and disposal, so that the overall cost of disposal can be minimized. The NCRW pretreatment flowsheet was designed to achieve the following objectives: (a) to separate Am and Pu from the major sludge constituents (Na, Zr). (b) to separate Am and Pu from U. (c) to concentrate Am and Pu in a small volume for immobilization in borosilicate glass, based on Hanford Waste Vitrification Plant (HWVP). The flowsheet involves: (1) sludge washing, (2) sludge dissolution, (3) extraction of U with tributyl phosphate (TBP), and (4) extraction of TRUs with octyl(phenyl)-N,N-diisobutlycarbamoylmethyl-phosphine oxide (CMPO). As presented in the flowsheet, the NCRW sludge is first washed with 0.I M NaOH to remove interstitial liquid and soluble salts from the sludge including sodium and potassium fluorides, carbonates, hydroxides, nitrates, and nitrites. The washed sludge is then subjected to two dissolution steps to achieve near complete dissolution of Zr.

Lumetta, G.J.

1994-05-01T23:59:59.000Z

309

ORIGINAL PAPER Bioremediation of oily sludge-contaminated soil  

E-Print Network (OSTI)

materials in crude-oil storage tanks also causes problems to the environment (Mrayyan and Battikhi 2005 of oily sludge generated in water­oil separation systems at oilfields and accumulation of waste oily as priority environmental pollutants by the US Environmental Protection Agency (USEPA 1986) and are also

Ma, Lena

310

Monitoring the Fixed FGD Sludge Landfill--Conesville, Ohio  

Science Conference Proceedings (OSTI)

Three years of extensive monitoring of the first full-scale application of the fixed flue gas desulfurization sludge process proved it technically sound. This new disposal method offers utilities leachate control in a landfill that allows diverse use of disposal sites in the future.

1984-10-01T23:59:59.000Z

311

Elucidating the solid, liquid and gaseous products from batch pyrolysis of cotton-gin trash.  

E-Print Network (OSTI)

Cotton-gin trash (CGT) was pyrolyzed at different temperatures and reaction times using an externally-heated batch reactor. The average yields of output products (solid/char, liquid/bio-oil, and gaseous) were determined. The heating value (HV) of CGT was measured to be around 15-16 MJ kg- 1 (6500-7000 Btu lb-1). In the first set of tests, CGT was pyrolyzed at 600, 700, and 800°C and at 30, 45, and 60 min reaction period. The maximum char yield of 40% by weight (wt.%) was determined at 600°C and 30 min settings, however, the HV of char was low and almost similar to the HV of CGT. A maximum gas yield of 40 wt.% was measured at 800°C and 60 min and the highest liquid yield of 30 wt.% was determined at 800°C and 30 min. In the modified pyrolysis test, the effects of temperature (500, 600, 700, and 800°C) on the product yield and other properties were investigated. The experiment was performed using the same reactor purged with nitrogen at a rate of 1000 cm3 min-1. Gas yield increased as temperature was increased while the effect was opposite on char yield. The maximum char yield of 38 wt.% was determined at 500°C and 30 min. The char had the largest fraction in the energy output (70-83%) followed by gas (10-20%) and bio-oil (7- 9%). Maximum gas yield of 35 wt.% was determined at 800°C. The average yield of CO, H2 and total hydrocarbons (THC) generally increased with increased temperature but CO2 production decreased. Methane, ethane, and propane dominated the THC. The bio-oil yield at 600°C was the highest at about 30 wt.% among the temperature settings. The HV of bio-oil was low (2-5 MJ kg-1) due to minimal non-HC compounds and high moisture content (MC). A simple energy balance of the process was performed. The process was considered energy intensive due to the high amount of energy input (6100 kJ) while generating a maximum energy output of only 10%. After disregarding the energy used for preparation and pyrolysis, the energy losses ranged from 30-46% while the energy of the output represent between 55-70% of the input energy from CGT.

Aquino, Froilan Ludana

2007-12-01T23:59:59.000Z

312

Effect of Antifoam Agent on Oxidative Leaching of Hanford Tank Sludge Simulants  

SciTech Connect

Oxidative leaching of simulant tank waste containing an antifoam agent (AFA) to reduce the chromium content of the sludge was tested using permanganate as the oxidant in 0.25 M NaOH solutions. AFA is added to the waste treatment process to prevent foaming. The AFA, Dow Corning Q2-3183A, is a surface-active polymer that consists of polypropylene glycol, polydimethylsiloxane, octylphenoxy polyethoxy ethanol, treated silica, and polyether polyol. Some of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) waste slurries contain high concentrations of undissolved solids that would exhibit undesirable behavior without AFA addition. These tests were conducted to determine the effect of the AFA on oxidative leaching of Cr(III) in waste by permanganate. It has not previously been determined what effect AFA has on the permanganate reaction. This study was conducted to determine the effect AFA has on the oxidation of the chromium, plus plutonium and other criticality-related elements, specifically Fe, Ni and Mn. During the oxidative leaching process, Mn is added as liquid permanganate solution and is converted to an insoluble solid that precipitates as MnO2 and becomes part of the solid waste. Caustic leaching was performed followed by an oxidative leach at either 25°C or 45°C. Samples of the leachate and solids were collected at each step of the process. Initially, Battelle-Pacific Northwest Division (PNWD) was contracted by Bechtel National, Inc. to perform these further scoping studies on oxidative alkaline leaching. The data obtained from the testing will be used by the WTP operations to develop procedures for permanganate dosing of Hanford tank sludge solids during oxidative leaching. Work was initially conducted under contract number 24590-101-TSA-W000-00004. In February 2007, the contract mechanism was switched to Pacific Northwest National Laboratory (PNNL) operating Contract DE-AC05-76RL01830. In summary, this report describes work focused on determining the effect of AFA on chromium oxidation by permanganate with Hanford sludge simulant.

Rapko, Brian M.; Jones, Susan A.; Lumetta, Gregg J.; Peterson, Reid A.

2010-02-26T23:59:59.000Z

313

Final Report - Glass Formulation Development and Testing for DWPF High AI2O3 HLW Sludges, VSL-10R1670-1, Rev. 0, dated 12/20/10  

Science Conference Proceedings (OSTI)

The principal objective of the work described in this Final Report is to develop and identify glass frit compositions for a specified DWPF high-aluminum based sludge waste stream that maximizes waste loading while maintaining high production rate for the waste composition provided by ORP/SRS. This was accomplished through a combination of crucible-scale, vertical gradient furnace, and confirmation tests on the DM100 melter system. The DM100-BL unit was selected for these tests. The DM100-BL was used for previous tests on HLW glass compositions that were used to support subsequent tests on the HLW Pilot Melter. It was also used to process compositions with waste loadings limited by aluminum, bismuth, and chromium, to investigate the volatility of cesium and technetium during the vitrification of an HLW AZ-102 composition, to process glass formulations at compositional and property extremes, and to investigate crystal settling on a composition that exhibited one percent crystals at 963{degrees}C (i.e., close to the WTP limit). The same melter was selected for the present tests in order to maintain comparisons between the previously collected data. The tests provide information on melter processing characteristics and off-gas data, including formation of secondary phases and partitioning. Specific objectives for the melter tests are as follows: Determine maximum glass production rates without bubbling for a simulated SRS Sludge Batch 19 (SB19). Demonstrate a feed rate equivalent to 1125 kg/m{sup 2}/day glass production using melt pool bubbling. Process a high waste loading glass composition with the simulated SRS SB19 waste and measure the quality of the glass product. Determine the effect of argon as a bubbling gas on waste processing and the glass product including feed processing rate, glass redox, melter emissions, etc.. Determine differences in feed processing and glass characteristics for SRS SB19 waste simulated by the co-precipitated and direct-hydroxide methods. The above tests were proposed based on previous tests for WTP in which there were few differences in the melter processing characteristics, such as processing rate and melter emissions, between precipitated and direct hydroxide simulants, even though there were differences in rheological properties. To the extent this similarity is found also for simulants for SRS HLW, the direct hydroxide methods may offer the potential for faster, simpler, and cheaper simulant production. There was no plan to match the yield stress and particle size of the direct hydroxide simulant to that of the precipitated simulant because that would have increased the preparation cost and complexity and defeated the purpose of the tests. These objectives were addressed by first developing a series of glass frits and then conducting a crucible scale study to determine the waste loading achievable for the waste composition and to select the preferred frit. Waste loadings were increased until the limits of a glass property were exceeded experimentally. Glass properties for evaluation included: viscosity, electrical conductivity, crystallinity (including liquidus temperature and nepheline formation after canister centerline cooling (CCC) heat-treatment), gross glass phase separation, and the 7- day Product Consistency Test (PCT, ASTM-1285) response. Glass property limits were based upon the constraints used for DWPF process control.

Kruger, Albert A.; Pegg, I. L.; Kot, W. K.; Gan, H.; Matlack, K. S.

2013-11-13T23:59:59.000Z

314

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

SciTech Connect

The long-term behavior of Hanford Site K Basin sludge with respect to loss of supernatant water and solids compaction is important in designing sludge storage and handling systems. This report describes the results of laboratory tests performed to understand and predict K Basin sludge drying and compaction rates under extended (28-month) {approx}34 C hot cell storage. Tests were conducted with six K Basin sludge materials, a control sample of simulated K Basin sludge, and a control sample containing only K Basin supernatant liquid. All samples were held in graduated cylinders fitted with threaded plastic caps. Quantitative data were gathered on how the mass and volume of K Basin sludge, and its associated supernatant liquid, changed with respect to storage time. The tests showed that the K Basin sludge samples lost water unpredictably, depending on cap seal tightness, with projected dryout times for a 1-cm cover water depth ranging from 5 to 216 months. Though the ambient radiation field ({approx}5 Rad/hour) likely contributed to cap seal degradation, water evaporation rates were found to be independent of the contained material (water vs. sludge; radioactive vs. non-radioactive sludge). Although water was lost at variable rates from sludge samples during storage in the hot cell (and, presumably, in long-term containerized storage), the sludge itself had no intrinsic propensity to enhance or diminish the rate of water evaporation compared with that exhibited by water stored in the same environment. Most of the compaction of the six KE Basin sludges and the simulated sludge occurred in the first week. Subsequent compaction to 28-months time provided little additional increase in settled sludge density. Agitating the settled sludge likewise had little to no effect on the density. However, one tested sludge contained unreacted uranium metal that began to generate corrosion product hydrogen gas after 78 days of settling and strongly altered the apparent sludge density. T he lengthy induction time shows again that uranium metal-bearing sludge may lie quiescent for long periods, even at comparatively warm temperatures, before initiating gas generation. When the testing was completed, the sludge samples were removed from the graduated cylinders. Most sludge re-suspended readily but a canister sludge sample that had previously been allowed to dry out during storage self-cemented into a hard-cake monolith and could not be re-suspended. Settled sludge density and the concentrations of 154Eu, 241Am, and the plutonium isotopes were found to follow the dry basis uranium concentration in the sludge solids. These findings amplify observations made in prior characterization studies that showed that sludge density and radiolytic, fissile material, and TRU (primarily 241Am and 238,239,240Pu) concentrations are proportional to uranium concentration. The sludge pH, found to decrease from {approx}8 to {approx}5 with a dry basis uranium concentration increase from {approx}2.5 to 82 wt% , provides data useful in designing sludge storage and process equipment.

Delegard, Calvin H.; Poloski, Adam P.; Schmidt, Andrew J.; Chenault, Jeffrey W.

2005-02-28T23:59:59.000Z

315

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

DOE Green Energy (OSTI)

The Waste Isolation Pilot Plant (WIPP) is being considered for the disposal of K Basin sludge as RH-TRU. Because the hydrogen gas concentration in the 55-gallon RH-TRU sealed drums to be transported to WIPP is limited by flammability safety, the number of containers and shipments likely will be driven by the rate of hydrogen generated by the uranium metal-water reaction (U + 2 H{sub 2}O {yields} UO{sub 2} + 2 H{sub 2}) in combination with the hydrogen generated from water and organic radiolysis. Gas generation testing was conducted with uranium metal particles of known surface area, in simulated K West (KW) Basin canister sludge and immobilized in candidate grout solidification matrices. This study evaluated potential for Portland cement and magnesium phosphate grouts to inhibit the reaction of water with uranium metal in the sludge and thereby permit higher sludge loading to the disposed waste form. The best of the grouted waste forms decreased the uranium metal-water reaction by a factor of four.

Delegard, Calvin H.; Schmidt, Andrew J.; Sell, Rachel L.; Sinkov, Sergei I.; Bryan, Samuel A.; Gano, Sue; Thornton, Brenda M.

2004-08-19T23:59:59.000Z

316

Optimal design and operation of multivessel batch distillation with fixed product demand. Modelling, simulation and optimisation of design and operation parameters in multivessel batch distillation under fixed product demand scenario and strict product specifications using simple dynamic model in gPROMS.  

E-Print Network (OSTI)

??Increased interest in unconventional batch distillation column configurations offers new opportunities for increasing the flexibility and energy efficiency of batch distillation. One configuration of particular… (more)

Mahmud, Mohamed Taher Mustafa

2010-01-01T23:59:59.000Z

317

Molybdenum uptake by forage crops grown on sewage sludge -- Amended soils in the field and greenhouse  

Science Conference Proceedings (OSTI)

Molybdenum (Mo) is a plant-available element in soils that can adversely affect the health of farm animals. There is a need for more information on its uptake into forage crops from waste materials, such as sewage sludge, applied to agricultural land. Field and greenhouse experiments with several crops grown on long-term sewage sludge-amended soils as well as soils recently amended with dewatered (DW) and alkaline-stabilized (ALK) sludges indicated that Mo supplied from sludge is readily taken up by legumes in particular. Excessive uptake into red clover (Trifolium pratense L.) was seen in a soil that had been heavily amended with sewage sludge 20 yr earlier, where the soil contained about 3 mg Mo/kg soil, three times the background soil concentration. The greenhouse and field studies indicated that Mo can have a long residual availability in sludge-amended soils. The effect of sludge application was to decrease Cu to Mo ratios in legume forages, canola (Brassica napus var. napus) and soybeans [Glycine max (L.) Merr.] below the recommended limit of 2:1 for ruminant diets, a consequence of high bioavailability of Mo and low uptake of Cu added in sludge. Molybdenum uptake coefficients (UCs) for ALK sludge were higher than for DW sludge, presumably due to the greater solubility of Mo measured in the more alkaline sludges and soils. Based on these UCs, it is tentatively recommended that cumulative Mo loadings on forages grown on nonacid soils should not exceed 1.0 kg/ha from ALK sludge or 4.0 kg/ha from DW sludge.

McBride, M.B.; Richards, B.K.; Steenhuis, T.; Spiers, G.

2000-06-01T23:59:59.000Z

318

HIGH SODIUM SIMULANT TESTING TO SUPPORT SB8 SLUDGE PREPARATION  

Science Conference Proceedings (OSTI)

Scoping studies were completed for high sodium simulant SRAT/SME cycles to determine any impact to CPC processing. Two SRAT/SME cycles were performed with simulant having sodium supernate concentration of 1.9M at 130% and 100% of the Koopman Minimum Acid requirement. Both of these failed to meet DWPF processing objectives related to nitrite destruction and hydrogen generation. Another set of SRAT/SME cycles were performed with simulant having a sodium supernate concentration of 1.6M at 130%, 125%, 110%, and 100% of the Koopman Minimum Acid requirement. Only the run at 110% met DWPF processing objectives. Neither simulant had a stoichiometric factor window of 30% between nitrite destruction and excessive hydrogen generation. Based on the 2M-110 results it was anticipated that the 2.5M stoichiometric window for processing would likely be smaller than from 110-130%, since it appeared that it would be necessary to increase the KMA factor by at least 10% above the minimum calculated requirement to achieve nitrite destruction due to the high oxalate content. The 2.5M-130 run exceeded the DWPF hydrogen limits in both the SRAT and SME cycle. Therefore, testing of this wash endpoint was halted. This wash endpoint with this minimum acid requirement and mercury-noble metal concentration profile appears to be something DWPF should not process due to an overly narrow window of stoichiometry. The 2M case was potentially processable in DWPF, but modifications would likely be needed in DWPF such as occasionally accepting SRAT batches with undestroyed nitrite for further acid addition and reprocessing, running near the bottom of the as yet ill-defined window of allowable stoichiometric factors, potentially extending the SRAT cycle to burn off unreacted formic acid before transferring to the SME cycle, and eliminating formic acid additions in the frit slurry.

Newell, J.

2012-09-19T23:59:59.000Z

319

6 Batch Injection and Slipped Beam Tune Measurements in Fermilab's Main Injector  

E-Print Network (OSTI)

During Nova operations it is planned to run the Fermilab Recycler in a 12 batch slip stacking mode. In preparation for this, measurements of the tune during a six batch injection and then as the beam is slipped by changing the RF frequency, but without a 7th injection, have been carried out in the Main Injector. The coherent tune shifts due to the changing beam intensity were measured and compared well with the theoretically expected tune shift. The tune shifts due to changing RF frequency, required for slip stacking, also compare well with the linear theory, although some nonlinear affects are apparent at large frequency changes. These results give us confidence that the expected tunes shifts during 12 batch slip stacking Recycler operations can be accommodated.

Scott, D J; Kourbanis, I; Seiya, K; Yan, M -J

2013-01-01T23:59:59.000Z

320

6 Batch Injection and Slipped Beam Tune Measurements in Fermilab?s Main Injector  

Science Conference Proceedings (OSTI)

During NOVA operations it is planned to run the Fermilab Recycler in a 12 batch slip stacking mode. In preparation for this, measurements of the tune during a six batch injection and then as the beam is decelerated by changing the RF frequency have been carried out in the Main Injector. The coherent tune shifts due to the changing beam intensity were measured and compared well with the theoretically expected tune shift. The tune shifts due to changing RF frequency, required for slip stacking, also compare well with the linear theory, although some nonlinear affects are apparent at large frequency changes. These results give us confidence that the expected tunes shifts during 12 batch slip stacking Recycler operations can be accommodated.

Scott, D.J.; Capista, D.; Kourbanis, I.; Seiya, K.; Yan, M.-J.; /Fermilab

2012-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

SLUDGE CHARACTERIZATION AND SRAT SIMULATIONS USING A NITRITE-FREE SLUDGE SIMULANT  

DOE Green Energy (OSTI)

Understanding catalytic hydrogen generation is fundamental to the safe operation of the Defense Waste Processing Facility (DWPF) Chemical Process Cell (CPC). Two Sludge Receipt and Adjustment Tank (SRAT) simulations were completed at the Aiken County Technology Laboratory (ACTL) of the Savannah River National Laboratory (SRNL) using a nitrite-free starting simulant. One simulation was trimmed with Rh and Hg and the other with Ru and Hg. The two noble metals were trimmed at the upper end of the recent Rh-Ru-Hg study. Mercury was trimmed at 1.5 wt% in the total solids. Excess acid comparable in quantity to that in the recent Rh-Ru-Hg matrix study was used. In spite of the favorable conditions for hydrogen generation, virtually no hydrogen production was observed during either SRAT simulation. The Rh test result confirmed the postulated significance of nitrite ion to the catalytic reactions producing hydrogen in CPC testing with normal DWPF sludge simulants. As for Ru, however, previous testing has shown that Ru activated for hydrogen generation only after nitrite destruction. Therefore, Ru could have potentially been catalytically active from the start of the nitrite-free SRAT test, but no such activity was seen. The nitrite-free Ru test result suggests that the intermediate form detected in the bead-frit melter feed preparation Ru solubility profiles was some form of nitro-Ru complex. The nitro-Ru complex is apparently not catalytically active for hydrogen generation but is a precursor to the catalytically active form (presumably a different complex not involving nitrite ligands). Removing nitrite ion from the system prevented the Ru catalyst precursor from forming and consequently blocked formation of the catalytically active form. These results, along with the results of a simulation in which sodium nitrite was metered into the SRAT to prevent ligand substitution reactions that occur during nitrite destruction from occurring in order to reduce hydrogen generation, have greatly clarified the role of the nitrite ion in SRAT hydrogen generation. The new findings add to the overall fundamental understanding of catalytic hydrogen generation during waste processing in the DWPF. These findings also address one of the issues raised in the Future Work section of the recent summary document concerning catalytic hydrogen generation in the CPC. The knowledge gained should facilitate planning future experiments.

Koopman, D.

2009-12-17T23:59:59.000Z

322

CX-004447: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

447: Categorical Exclusion Determination 447: Categorical Exclusion Determination CX-004447: Categorical Exclusion Determination L Basin Vacuum System Replacement CX(s) Applied: B1.3 Date: 10/15/2010 Location(s): Aiken, South Carolina Office(s): Savannah River Operations Office The L Area Disassembly Basin vacuum system will be replaced and used to vacuum the Horizontal Bundle and Bucket Storage area and Transfer Bay of the basin floor. Most of the basin floor sludge will be sent to the L Area Monitor Basin, and the sludge from the resin-affected zones will be sent to solid waste. Revision 1: This revision adds vacuuming of the Transfer Bay and sending of most of the sludge to the Monitor Basin instead of Settler Tank. DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-004447.pdf More Documents & Publications

323

CX-002997: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

97: Categorical Exclusion Determination 97: Categorical Exclusion Determination CX-002997: Categorical Exclusion Determination EM-31 Alternative Chemical Cleaning Program CX(s) Applied: B3.6 Date: 05/24/2010 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office Two types of testing will be conducted. Dissolution testing of sludge materials and organic destruction scoping tests with spent acids containing dissolved sludge materials. (1) Dissolution Testing - Dissolution testing will involve treatment of sludge simulants and known mineral phases with inorganic acids, carboxylic acids, mixtures of acids, other complexants, and caustic. The solubilities of selected components and the fate of various species will be examined under a range of conditions. Testing will

324

CX-002526: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

26: Categorical Exclusion Determination 26: Categorical Exclusion Determination CX-002526: Categorical Exclusion Determination Environmental Management-31 Alternative Chemical Cleaning (ACC) Program CX(s) Applied: B3.6 Date: 05/24/2010 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office Two types of testing will be conducted. Dissolution testing of sludge materials and organic destruction scoping tests with spent acids containing dissolved sludge materials. Dissolution testing will involve treatment of sludge simulants and known mineral phases with inorganic acids, carboxylic acids, mixtures of acids, other complexants, and caustic. Organic destruction will likely involve the production of gases including oxides of carbon and nitrogen which will be released into the hood ventilation

325

CX-006411: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

411: Categorical Exclusion Determination 411: Categorical Exclusion Determination CX-006411: Categorical Exclusion Determination EM-31 Alternative Chemical Cleaning (ACC) Program CX(s) Applied: B3.6 Date: 05/24/2010 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office Two types of testing will be conducted. Dissolution testing of sludge materials and organic destruction scoping tests with spent acids containing dissolved sludge materials. (1) Dissolution Testing - Dissolution testing will involve treatment of sludge simulants and known mineral phases with inorganic acids, carboxylic acids, mixtures of acids, other complexants, and caustic. The solubilities of selected components and the fate of various species will be examined under a range of conditions. Testing will

326

CX-002206: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

206: Categorical Exclusion Determination 206: Categorical Exclusion Determination CX-002206: Categorical Exclusion Determination Real-Waste Testing of Enhanced Chemical Cleaning for Sludge Heel Removal CX(s) Applied: B3.6 Date: 04/16/2010 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office Enhanced Chemical Cleaning (ECC) is a process for dissolving high-level waste (HLW) tank heel sludge with 1% by weight oxalic acid with pH controlled to 2 followed by decomposition of the oxalic acid and separation of the precipitated solids by evaporation. The decomposition oxalic acid is accomplished in an external Advanced Oxidation Process (AOP) involving ozone injection and ultraviolet (UV) light exposure. Testing of the sludge dissolution, oxalate decomposition, precipitated solids separation, and

327

CRAD, Training - Office of River Protection K Basin Sludge Waste System |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office of River Protection K Basin Sludge Waste Office of River Protection K Basin Sludge Waste System CRAD, Training - Office of River Protection K Basin Sludge Waste System May 2004 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2004 assessment of the Environment, Safety and Health program at the Office of River Protection K Basin Sludge Waste System. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Office of River Protection K Basin Sludge Waste System More Documents & Publications CRAD, Emergency Management - Office of River Protection K Basin Sludge

328

CRAD, Engineering - Office of River Protection K Basin Sludge Waste System  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Engineering - Office of River Protection K Basin Sludge Waste Engineering - Office of River Protection K Basin Sludge Waste System CRAD, Engineering - Office of River Protection K Basin Sludge Waste System May 2004 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2004 assessment of the Engineering program at the Office of River Protection K Basin Sludge Waste System. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Engineering - Office of River Protection K Basin Sludge Waste System More Documents & Publications CRAD, Emergency Management - Office of River Protection K Basin Sludge

329

EA-1042: Proposed Changes to the Sanitary Sludge Land Application Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

042: Proposed Changes to the Sanitary Sludge Land Application 042: Proposed Changes to the Sanitary Sludge Land Application Program on the Oak Ridge Reservation, Oak Ridge, Tennesee EA-1042: Proposed Changes to the Sanitary Sludge Land Application Program on the Oak Ridge Reservation, Oak Ridge, Tennesee SUMMARY This EA evaluates the environmental impacts of the proposal to raise the sludge land application loading limits from the current, self-imposed conservative 48 metric tons/ha lifetime loading to the U.S. Environmental Protection Agency-approved and Tennessee Department of Environment and Conservation-permitted level of 110 metric tons/ha. The U.S. Department of Energy's Oak Ridge National Laboratory also proposes to add its K-25 Site pretreated sewage sludge to the existing sewage sludge land application program on the Oak Ridge Reservation in Oak Ridge, Tennessee.

330

Vessel-Spanning Bubble Formation in K-Basin Sludge Stored in Large-Diameter Containers  

DOE Green Energy (OSTI)

The K Basin sludge to be retrieved and stored in the large diameter containers (LDCs) contains some fraction of uranium metal that generates hydrogen gas, which introduces potential upset conditions. One postulated upset condition is a rising plug of sludge supported by a hydrogen bubble that is driven into the vent filters at the top of the container. In laboratory testing with actual K Basin sludge, vessel-spanning bubbles that lifted plugs of sludge were observed in 3-inch-diameter graduated cylinders. This report presents a series of analytical assessments performed by the Pacific Northwest National Laboratory to address the potential for the generation of a vessel spanning bubble in the LDCs. The assessments included the development and evaluation of static and dynamic bubble formation models over the projected range of K Basin sludge physical properties. Additionally, the theory of circular plates was extrapolated to examine conditions under which a plug of sludge would collapse and release a spanning bubble.

Terrones, Guillermo; Gauglitz, Phillip A.

2002-03-01T23:59:59.000Z

331

Application of microwave energy for in-drum solidification of simulated precipitation sludge  

SciTech Connect

The application of microwave energy for in-container solidification of simulated transuranic contaminated precipitation sludges has been tested. Results indicate volume reductions to 83% are achievable by the continuous feeding of pre-dried sludge into a waste container while applying microwave energy. An economic evaluation was completed showing achievable volume and weight reductions to 87% compared with a current immobilization process for wet sludge. 7 refs., 15 figs., 16 tabs.

Petersen, R.D.; Johnson, A.J.; Swanson, S.D.; Thomas, R.L. (ed.)

1987-08-17T23:59:59.000Z

332

Conditions of utilization of coal mining and processing sludges as slurry fuel  

Science Conference Proceedings (OSTI)

The results of this study have shown that coal sludge can be used as slurry fuel (like coal-water fuel (CWF)) providing that its ash content does not exceed 30% and the amount in the fuel is at least 55%. The conventional CWF preparation technologies are inapplicable to the fabrication of water-sludge fuel; therefore, special technologies with allowance for the ash content, the particle size, and the water content of coal sludge are demanded.

E.G. Gorlov; A.I. Seregin; G.S. Khodakov [Institute for Fossil Fuels, Moscow (Russian Federation)

2007-12-15T23:59:59.000Z

333

Microwave Thermal Hydrolysis Of Sewage Sludge As A Pretreatment Stage For Anaerobic Digestion  

Science Conference Proceedings (OSTI)

This article focuses on the effects of microwave thermal hydrolysis on sewage sludge anaerobic digestion. Volatile suspended solid (VSS) and COD solubilization of treated sludge were investigated. It was found that the microwave hydrolysis provided a rapid and efficient process to release organics from sludge. The increase of organic dissolution ratio was not obvious when holding time was over 5 min. The effect of the VSS solubilization was mainly dependent on temperature. The highest value of VSS dissolving ratio

W. Qiao; W. Wang; R. Xun

2008-01-01T23:59:59.000Z

334

Remote Handled Transuranic Sludge Retrieval Transfer And Storage System At Hanford  

SciTech Connect

This paper describes the systems developed for processing and interim storage of the sludge managed as remote-handled transuranic (RH-TRU). An experienced, integrated CH2M HILL/AFS team was formed to design and build systems to retrieve, interim store, and treat for disposal the K West Basin sludge, namely the Sludge Treatment Project (STP). A system has been designed and is being constructed for retrieval and interim storage, namely the Engineered Container Retrieval, Transfer and Storage System (ECRTS).

Raymond, Rick E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Frederickson, James R. [AREVA, Avignon (France); Criddle, James [AREVA, Avignon (France); Hamilton, Dennis [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Johnson, Mike W. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2012-10-18T23:59:59.000Z

335

Disposition Options for Hanford Site K-Basin Spent Nuclear Fuel Sludge  

SciTech Connect

This report provides summary-level information about a group of options that have been identified for the disposition of spent-nuclear-fuel sludge in the K-Basins at the Hanford Site. These options are representative of the range of likely candidates that may be considered for disposition of the sludge. The product of each treatment option would be treated sludge that would meet waste acceptance requirements for disposal as transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP).

Mellinger, George B.; Delegard, Calvin H.; Gerber, Mark A.; Naft, Barry N.; Schmidt, Andrew J.; Walton, Terry L.

2004-01-18T23:59:59.000Z

336

Oxygen-enriched coincineration of MSW and sewage sludge: Final report  

Science Conference Proceedings (OSTI)

Federal regulations banning ocean dumping of sewage sludge coupled with stricter regulations on the disposal of sewage sludge in landfills have forced municipalities, especially those in the northeast United States, to consider alternate methods for disposal of this solid waste. Coincineration of municipal solid waste (MSW) and sludge has proven to be economically attractive for both Europe and Japan, but has not yet proven to be a viable sludge disposal technology in the United States because of a history of operational problems in existing facilities. The most prevalent problem in coincinerating MSW and a dewatered sewage sludge (15 to 25% solids) is incomplete sludge combustion. Incomplete sludge combustion is primarily a function of sludge particle size, occurring when the surface of the sludge particle dries and hardens, while the inner mass is unaffected. This phenomenon is commonly referred to in the industry as the {open_quotes}hamburger effect.{close_quotes} In an effort to promote technology development in this area, Air Products and Chemicals, Inc. teamed with the US Department of Energy (DOE) through the National Renewable Energy Laboratory (NREL) to evaluate a new process being developed for the disposal of a dewatered sewage sludge, {open_quotes}Oxygen-Enriched Coincineration of MSW and Sewage Sludge.{close_quotes} This report provides a comprehensive summary of the pilot demonstration test program for oxygen-enriched coincineration of MSW and sewage sludge. This report describes the pilot test facility, instrumentation, and methods of data collection and data analyses; describes how the tests were executed; and discusses the test results. Recommendations for the future development of this technology in the current marketplace are also provided.

Not Available

1994-01-01T23:59:59.000Z

337

SLUDGE TREATMENT PROJECT ENGINEERED CONTAINER RETRIEVAL AND TRANSFER SYSTEM PRELIMINARY DESIGN HAZARD ANALYSIS SUPPLEMENT 1  

Science Conference Proceedings (OSTI)

This 'What/If' Hazards Analysis addresses hazards affecting the Sludge Treatment Project Engineered Container Retrieval and Transfer System (ECRTS) NPH and external events at the preliminary design stage. In addition, the hazards of the operation sequence steps for the mechanical handling operations in preparation of Sludge Transport and Storage Container (STSC), disconnect STSC and prepare STSC and Sludge Transport System (STS) for shipping are addressed.

FRANZ GR; MEICHLE RH

2011-07-18T23:59:59.000Z

338

march 07 batch contrasctor pension comments.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Andy Lang Andy Lang Sent: Friday, March 30, 2007 10:30 AM To: contractor pensions Cc: Andy Lang Subject: Response to request for info on holding costs down on govt contractor pensions Hello. I saw the brief article in the March 26th Washington Post regarding the very high costs of government contractor pensions and the request for help through this e-mail. These high costs are partly because the benefits tend to be high and partly due to the way actuaries determine them. I am a retired life, health and pension consulting actuary--and a huge critic of actuaries. It is well known among pension actuaries but nowhere else, that for pension plan sponsors that get reimbursements from tax dollars, such as Medicare eligible physicians groups and hospitals, government

339

Review of the Hanford Sludge Treatment Project, February 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

HSS Independent Activity Report - Rev. 0 Report Number: HIAR-RL-2012-02-27 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Sludge Treatment Project Dates of Activity : 02/27/2012 - 03/01/2012 Report Preparer: Jake Wechselberger Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), performed operational awareness reviews of the Sludge Treatment Project (STP), Engineered Container Retrieval and Transfer System (ECRTS) during site visits. Result: During the period February 27 - March 1, 2012, an HSS representative attended the Defense Nuclear Facilities Safety Board

340

Review of the Hanford Sludge Treatment Project, February 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HSS Independent Activity Report - Rev. 0 Report Number: HIAR-RL-2012-02-27 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Sludge Treatment Project Dates of Activity : 02/27/2012 - 03/01/2012 Report Preparer: Jake Wechselberger Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), performed operational awareness reviews of the Sludge Treatment Project (STP), Engineered Container Retrieval and Transfer System (ECRTS) during site visits. Result: During the period February 27 - March 1, 2012, an HSS representative attended the Defense Nuclear Facilities Safety Board

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

ACCIDENT ANALYSES & CONTROL OPTIONS IN SUPPORT OF THE SLUDGE WATER SYSTEM SAFETY ANALYSIS  

Science Conference Proceedings (OSTI)

This report documents the accident analyses and nuclear safety control options for use in Revision 7 of HNF-SD-WM-SAR-062, ''K Basins Safety Analysis Report'' and Revision 4 of HNF-SD-SNF-TSR-001, ''Technical Safety Requirements - 100 KE and 100 KW Fuel Storage Basins''. These documents will define the authorization basis for Sludge Water System (SWS) operations. This report follows the guidance of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', for calculating onsite and offsite consequences. The accident analysis summary is shown in Table ES-1 below. While this document describes and discusses potential control options to either mitigate or prevent the accidents discussed herein, it should be made clear that the final control selection for any accident is determined and presented in HNF-SD-WM-SAR-062.

WILLIAMS, J.C.

2003-11-15T23:59:59.000Z

342

PROGRESS WITH K BASINS SLUDGE RETRIEVAL STABILIZATION & PACKAGING AT THE HANFORD NUCLEAR SITE  

SciTech Connect

This paper shows how Fluor Hanford and BNG America have combined nuclear plant skills from the U.S. and the U.K. to devise methods to retrieve and treat the sludge that has accumulated in K Basins at the Hanford Site over many years. Retrieving the sludge is the final stage in removing fuel and sludge from the basins to allow them to be decontaminated and decommissioned, so as to remove the threat of contamination of the Columbia River. A description is given of sludge retrieval using vacuum lances and specially developed nozzles and pumps into Consolidation Containers within the basins. The special attention that had to be paid to the heat generation and potential criticality issues with the irradiated uranium-containing sludge is described. The processes developed to re-mobilize the sludge from the Consolidation Containers and pump it through flexible and transportable hose-in-hose piping to the treatment facility are explained with particular note made of dealing with the abrasive nature of the sludge. The treatment facility, housed in an existing Hanford building, is described, and the uranium-corrosion and grout packaging processes explained. The uranium corrosion process is a robust, tempered process very suitable for dealing with a range of differing sludge compositions. Optimization and simplification of the original sludge corrosion process design is described and the use of transportable and reusable equipment is indicated. The processes and techniques described in the paper are shown to have wide applicability to nuclear cleanup.

KNOLLMEYER, P.M.; PHILLIPS, C; TOWNSON, P.S.

2006-01-30T23:59:59.000Z

343

International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry  

E-Print Network (OSTI)

Sludge treatment to increase biogas production. Available atal. , no date) Use of biogas from anaerobic sludge digestionsludge are mass reduction, biogas production, and improved

Hasanbeigi, Ali

2013-01-01T23:59:59.000Z

344

Use of Batch and Column Methodologies to Assess Utility Waste Leaching and Subsurface Chemical Attenuation  

Science Conference Proceedings (OSTI)

Often, a combination of batch and column methods is used in the laboratory to test wastes for leaching and attenuation potentials. This literature review addresses the strengths and limitations of using these two methods to predict leachate generation and subsequent attenuation at coal combustion waste management sites.

1991-05-13T23:59:59.000Z

345

Effects of Fe2+ on the Anaerobic Digestion of Chicken Manure: A Batch Study  

Science Conference Proceedings (OSTI)

Trace elements are considered to be essential for anaerobic process. Laboratory-scale batch studies were undertaken to evaluate the effect of Fe2+on the biogas production from chicken manure at mesophilic condition (37 ±1°C). The biogas production ... Keywords: anaerobic digestion, chicken manure, dynamics, iron, stimulation and inhibition

Zhang Wanqin; Guo Jianbin; Wu Shubiao; Dong Renjie; Zhou Jie; Lang Qianqian; Li Xin; Lv Tao; Pang Changle; Chen Li; Wang Baozhi

2012-07-01T23:59:59.000Z

346

Bid Prices When Demand Is a Mix of Individual and Batch Bookings  

Science Conference Proceedings (OSTI)

Industries such as aviation, hospitality, and package tours often face both individual and batch bookings, requiring one unit and multiple units of capacity, respectively. Using bid prices is a common practice in accepting or rejecting an incoming booking ... Keywords: air cargo, bid prices, nonlinear programming formulation, revenue management

Andreea Popescu, Earl Barnes, Ellis Johnson, Pinar Keskinocak

2013-05-01T23:59:59.000Z

347

Batch fabrication of cantilever array aperture probes for scanning near-field optical microscopy  

Science Conference Proceedings (OSTI)

We have developed a novel batch fabrication process for cantilever array aperture probes used in scanning near-field optical microscopy (SNOM). The array probes, consisting of 16 parallel cantilevers with each tip having an identical aperture, are proposed ... Keywords: Cantilever probes, Nanofabrication, Scanning near-field optical microscopy (SNOM)

Y. Zhang; K. E. Docherty; J. M. R. Weaver

2010-05-01T23:59:59.000Z

348

Restructuring Batch View Maintenance Efficiently Bin Liu, Elke A. Rundensteiner and David Finkel  

E-Print Network (OSTI)

with existing batch algorithms. Categories and Subject Descriptors: H.2.4 [Database Management]: Systems maintenance strategies within the TxnWrap system [3]. The experiments are conducted on four Pentium III 500MHz Systems (TODS), 2004, to appear. [4] A. Gupta and I. Mumick. Maintenance of Materialized Views: Problems

349

Neural network based controller for Cr6+-Fe2+ batch reduction process  

Science Conference Proceedings (OSTI)

An automated pilot plant has been designed and commissioned to carry out online/real-time data acquisition and control for the Cr^6^+-Fe^2^+ reduction process. Simulated data from the Cr^6^+-Fe^2^+ model derived are validated with online data and laboratory ... Keywords: Batch system, Neural Networks, ORP, Redox process

Chew Chun Ming; M. A. Hussain; M. K. Aroua

2011-11-01T23:59:59.000Z

350

Sorption of Eu(III) on Attapulgite Studied by Batch, XPS and EXAFS Techniques  

E-Print Network (OSTI)

Sorption of Eu(III) on Attapulgite Studied by Batch, XPS and EXAFS Techniques Q.H. FAN,, , X.L. TAN, , J.X. LI , X.K. WANG* , W.S. WU* , G. Montavon&* Key Laboratory of Novel Thin Film Solar Cells, the sorption of Eu(III) at the solid-water interface is important for the performance assessment of nuclear

Paris-Sud XI, Université de

351

Machine-Generated Algorithms, Proofs and Software for the Batch Verification of Digital Signature Schemes  

E-Print Network (OSTI)

expand upon an extended abstract on AutoBatch appearing in ACM CCS 2012 in a number of ways. We add a new Advanced Research Projects Agency (DARPA) and the Air Force Research Laboratory (AFRL) under contract FA (DARPA) and the Air Force Research Laboratory (AFRL) under contract FA8750-11-2-0211, the Office of Naval

352

Enhanced genetic algorithm-based fuzzy multiobjective strategy to multiproduct batch plant design  

Science Conference Proceedings (OSTI)

This paper addresses the problem of the optimal design of batch plants with imprecise demands in product amounts. The design of such plants necessary involves how equipment may be utilized, which means that plant scheduling and production must constitute ... Keywords: Fuzzy numbers, Genetic algorithms, Imprecise demand, Multiobjective optimization, Net present value, Plant design, Production scheduling

A. A. Aguilar-Lasserre; L. Pibouleau; C. Azzaro-Pantel; S. Domenech

2009-09-01T23:59:59.000Z

353

Engineered nanoparticles in wastewater and wastewater sludge - Evidence and impacts  

SciTech Connect

Nanotechnology has widespread application in agricultural, environmental and industrial sectors ranging from fabrication of molecular assemblies to microbial array chips. Despite the booming application of nanotechnology, there have been serious implications which are coming into light in the recent years within different environmental compartments, namely air, water and soil and its likely impact on the human health. Health and environmental effects of common metals and materials are well-known, however, when the metals and materials take the form of nanoparticles - consequential hazards based on shape and size are yet to be explored. The nanoparticles released from different nanomaterials used in our household and industrial commodities find their way through waste disposal routes into the wastewater treatment facilities and end up in wastewater sludge. Further escape of these nanoparticles into the effluent will contaminate the aquatic and soil environment. Hence, an understanding of the presence, behavior and impact of these nanoparticles in wastewater and wastewater sludge is necessary and timely. Despite the lack of sufficient literature, the present review attempts to link various compartmentalization aspects of the nanoparticles, their physical properties and toxicity in wastewater and wastewater sludge through simile drawn from other environmental streams.

Brar, Satinder K., E-mail: satinder.brar@ete.inrs.c [INRS-ETE, Universite du Quebec, 490, Rue de la Couronne, Quebec, G1K 9A9 (Canada); Verma, Mausam [Department of Biological Engineering, Sexton Campus, Dalhousie University, Halifax, Nova Scotia, Canada B3J 2X4 (Canada); Tyagi, R.D. [INRS-ETE, Universite du Quebec, 490, Rue de la Couronne, Quebec, G1K 9A9 (Canada); Surampalli, R.Y. [US Environmental Protection Agency, P.O. Box 17-2141, Kansas City, KS 66117 (United States)

2010-03-15T23:59:59.000Z

354

Renovation of a pear orchard site with sludge compost  

Science Conference Proceedings (OSTI)

A lime-stabilized sewage sludge compost was used as a surface amendment to improve the soil and nutritional status of a number of established pear cultivars grown on an acidic, low fertility soil site. Leaf Ca status was significantly increased while trace metals were not elevated and in most cases decreased by sludge compost over the course of the study. Soil chemical properties were modified in a manner similar to liming. Addition of sludge composts, particularly low metal containing materials, appears to represent an acceptable aid in renovating established pear orchards located on poor soil sites. Leaf, fruit flesh or peel Cd were not significantly effected by the compost addition. The compost added twice the recommended level of available N the first year and sub-optimum N the following two years. Leaf N, although significantly increased in the composted versus non-composted controls, was below sufficiency levels by the third year after addition. This indicates that compost cannot fully supply required N from a one time application even over the short term.

Korcak, R.F.

1986-01-01T23:59:59.000Z

355

Simulation of substrate degradation in composting of sewage sludge  

Science Conference Proceedings (OSTI)

To simulate the substrate degradation kinetics of the composting process, this paper develops a mathematical model with a first-order reaction assumption and heat/mass balance equations. A pilot-scale composting test with a mixture of sewage sludge and wheat straw was conducted in an insulated reactor. The BVS (biodegradable volatile solids) degradation process, matrix mass, MC (moisture content), DM (dry matter) and VS (volatile solid) were simulated numerically by the model and experimental data. The numerical simulation offered a method for simulating k (the first-order rate constant) and estimating k{sub 20} (the first-order rate constant at 20 {sup o}C). After comparison with experimental values, the relative error of the simulation value of the mass of the compost at maturity was 0.22%, MC 2.9%, DM 4.9% and VS 5.2%, which mean that the simulation is a good fit. The k of sewage sludge was simulated, and k{sub 20}, k{sub 20s} (first-order rate coefficient of slow fraction of BVS at 20 {sup o}C) of the sewage sludge were estimated as 0.082 and 0.015 d{sup -1}, respectively.

Zhang Jun [Center for Environmental Remediation, Institute of Geographic Sciences and Natural Resources Research, Chinese Academy of Sciences, 11A Datun Road, Beijing 100101 (China); Gao Ding, E-mail: gaod@igsnrr.ac.c [Center for Environmental Remediation, Institute of Geographic Sciences and Natural Resources Research, Chinese Academy of Sciences, 11A Datun Road, Beijing 100101 (China); Chen Tongbin; Zheng Guodi; Chen Jun; Ma Chuang; Guo Songlin [Center for Environmental Remediation, Institute of Geographic Sciences and Natural Resources Research, Chinese Academy of Sciences, 11A Datun Road, Beijing 100101 (China); Du Wei [Beijing GreenTech Environmental Engineering Company, Beijing 100080 (China)

2010-10-15T23:59:59.000Z

356

Sludge mobilization with submerged nozzles in horizontal cylindrical tanks  

SciTech Connect

The Melton Valley Storage Tanks (MVSTs) and the evaporator service tanks at the Oak Ridge National Laboratory (ORNL) are used for the collection and storage of liquid low-level waste (LLLW). Wastes collected in these tanks are typically acidic when generated and are neutralized with sodium hydroxide to protect the tanks from corrosion; however, the high pH of the solution causes the formation of insoluble compounds that precipitate. These precipitates formed a sludge layer approximately 0.6 to 1.2 m (2 to 4 ft) deep in the bottom of the tanks. The sludge in the MVSTs and the evaporator service tanks will eventually need to be removed from the tanks and treated for final disposal or transferred to another storage facility. The primary options for removing the sludge include single-point sluicing, use of a floating pump, robotic sluicing, and submerged-nozzle sluicing. The objectives of this study were to (1) evaluate the feasibility of submerged-nozzle sluicing in horizontal cylindrical tanks and (2) obtain experimental data to validate the TEMPEST (time-dependent, energy, momentun, pressure, equation solution in three dimensions) computer code.

Hylton, T.D.; Cummins, R.L.; Youngblood, E.L.; Perona, J.J.

1995-10-01T23:59:59.000Z

357

Filtration and Leach Testing for PUREX Cladding Sludge and REDOX Cladding Sludge Actual Waste Sample Composites  

SciTech Connect

A testing program evaluating actual tank waste was developed in response to Task 4 from the M-12 External Flowsheet Review Team (EFRT) issue response plan (Barnes and Voke 2006). The test program was subdivided into logical increments. The bulk water-insoluble solid wastes that are anticipated to be delivered to the Hanford Waste Treatment and Immobilization Plant (WTP) were identified according to type such that the actual waste testing could be targeted to the relevant categories. Under test plan TP RPP WTP 467 (Fiskum et al. 2007), eight broad waste groupings were defined. Samples available from the 222S archive were identified and obtained for testing. Under this test plan, a waste testing program was implemented that included: • Homogenizing the archive samples by group as defined in the test plan. • Characterizing the homogenized sample groups. • Performing parametric leaching testing on each group for compounds of interest. • Performing bench-top filtration/leaching tests in the hot cell for each group to simulate filtration and leaching activities if they occurred in the UFP2 vessel of the WTP Pretreatment Facility. This report focuses on a filtration/leaching test performed using two of the eight waste composite samples. The sample groups examined in this report were the plutonium-uranium extraction (PUREX) cladding waste sludge (Group 3, or CWP) and reduction-oxidation (REDOX) cladding waste sludge (Group 4, or CWR). Both the Group 3 and 4 waste composites were anticipated to be high in gibbsite, thus requiring caustic leaching. WTP RPT 167 (Snow et al. 2008) describes the homogenization, characterization, and parametric leaching activities before benchtop filtration/leaching testing of these two waste groups. Characterization and initial parametric data in that report were used to plan a single filtration/leaching test using a blend of both wastes. The test focused on filtration testing of the waste and caustic leaching for aluminum, in the form of gibbsite, and its impact on filtration. The initial sample was diluted with a liquid simulant to simulate the receiving concentration of retrieved tank waste into the UFP2 vessel (< 10 wt% undissolved solids). Filtration testing was performed on the dilute waste sample and dewatered to a higher solids concentration. Filtration testing was then performed on the concentrated slurry. Afterwards, the slurry was caustic leached to remove aluminum present in the undissolved solid present in the waste. The leach was planned to simulate leaching conditions in the UFP2 vessel. During the leach, slurry supernate samples were collected to measure the dissolution rate of aluminum in the waste. After the slurry cooled down from the elevated leach temperature, the leach liquor was dewatered from the solids. The remaining slurry was rinsed and dewatered with caustic solutions to remove a majority of the dissolved aluminum from the leached slurry. The concentration of sodium hydroxide in the rinse solutions was high enough to maintain the solubility of the aluminum in the dewatered rinse solutions after dilution of the slurry supernate. Filtration tests were performed on the final slurry to compare to filtration performance before and after caustic leaching.

Shimskey, Rick W.; Billing, Justin M.; Buck, Edgar C.; Casella, Amanda J.; Crum, Jarrod V.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Hallen, Richard T.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Swoboda, Robert G.

2009-03-02T23:59:59.000Z

358

Tank 12 Sludge Characterization and Aluminum Dissolution Demonstration  

Science Conference Proceedings (OSTI)

A 3-L sludge slurry sample from Tank 12 was characterized and then processed through an aluminum dissolution demonstration. The dominant constituent of the sludge was found to be aluminum in the form of boehmite. The iron content was minor, about one-tenth that of the aluminum. The salt content of the supernatant was relatively high, with a sodium concentration of {approx}7 M. Due to these characteristics, the yield stress and plastic viscosity of the unprocessed slurry were relatively high (19 Pa and 27 cP), and the settling rate of the sludge was relatively low ({approx}20% settling over a two and a half week period). Prior to performing aluminum dissolution, plutonium and gadolinium were added to the slurry to simulate receipt of plutonium waste from H-Canyon. Aluminum dissolution was performed over a 26 day period at a temperature of 65 C. Approximately 60% of the insoluble aluminum dissolved during the demonstration, with the rate of dissolution slowing significantly by the end of the demonstration period. In contrast, approximately 20% of the plutonium and less than 1% of the gadolinium partitioned to the liquid phase. However, about a third of the liquid phase plutonium became solubilized prior to the dissolution period, when the H-Canyon plutonium/gadolinium simulant was added to the Tank 12 slurry. Quantification of iron dissolution was less clear, but appeared to be on the order of 1% based on the majority of data (a minor portion of the data suggested iron dissolution could be as high as 10%). The yield stress of the post-dissolution slurry (2.5 Pa) was an order of magnitude lower than the initial slurry, due most likely to the reduced insoluble solids content caused by aluminum dissolution. In contrast, the plastic viscosity remained unchanged (27 cP). The settling rate of the post-dissolution slurry was higher than the initial slurry, but still relatively low compared to settling of typical high iron content/low salt content sludges. Approximately 40% of the post-dissolution sludge settled over a three week period. The corresponding volume of supernatant that was decanted from the waste was approximately 35% of the total waste volume. The decanted supernatant contained approximately one-third of the dissolved aluminum and exhibited a mild greenish-grey hue.

Reboul, S.; Hay, M.; Zeigler, K; Stone, M.

2010-05-05T23:59:59.000Z

359

TANK 12 SLUDGE CHARACTERIZATION AND ALUMINUM DISSOLUTION DEMONSTRATION  

Science Conference Proceedings (OSTI)

A 3-L sludge slurry sample from Tank 12 was characterized and then processed through an aluminum dissolution demonstration. The dominant constituent of the sludge was found to be aluminum in the form of boehmite. The iron content was minor, about one-tenth that of the aluminum. The salt content of the supernatant was relatively high, with a sodium concentration of {approx}7 M. Due to these characteristics, the yield stress and plastic viscosity of the unprocessed slurry were relatively high (19 Pa and 27 cP), and the settling rate of the sludge was relatively low ({approx}20% settling over a two and a half week period). Prior to performing aluminum dissolution, plutonium and gadolinium were added to the slurry to simulate receipt of plutonium waste from H-Canyon. Aluminum dissolution was performed over a 26 day period at a temperature of 65 C. Approximately 60% of the insoluble aluminum dissolved during the demonstration, with the rate of dissolution slowing significantly by the end of the demonstration period. In contrast, approximately 20% of the plutonium and less than 1% of the gadolinium partitioned to the liquid phase. However, about a third of the liquid phase plutonium became solubilized prior to the dissolution period, when the H-Canyon plutonium/gadolinium simulant was added to the Tank 12 slurry. Quantification of iron dissolution was less clear, but appeared to be on the order of 1% based on the majority of data (a minor portion of the data suggested iron dissolution could be as high as 10%). The yield stress of the post-dissolution slurry (2.5 Pa) was an order of magnitude lower than the initial slurry, due most likely to the reduced insoluble solids content caused by aluminum dissolution. In contrast, the plastic viscosity remained unchanged (27 cP). The settling rate of the post-dissolution slurry was higher than the initial slurry, but still relatively low compared to settling of typical high iron content/low salt content sludges. Approximately 40% of the post-dissolution sludge settled over a three week period. The corresponding volume of supernatant that was decanted from the waste was approximately 35% of the total waste volume. The decanted supernatant contained approximately one-third of the dissolved aluminum and exhibited a mild greenish-grey hue.

Reboul, S; Michael Hay, M; Kristine Zeigler, K; Michael Stone, M

2009-03-25T23:59:59.000Z

360

STP-ECRTS - THERMAL AND GAS ANALYSES FOR SLUDGE TRANSPORT AND STORAGE CONTAINER (STSC) STORAGE AT T PLANT  

DOE Green Energy (OSTI)

The Sludge Treatment Project (STP) is responsible for the disposition of sludge contained in the six engineered containers and Settler tank within the 105-K West (KW) Basin. The STP is retrieving and transferring sludge from the Settler tank into engineered container SCS-CON-230. Then, the STP will retrieve and transfer sludge from the six engineered containers in the KW Basin directly into a Sludge Transport and Storage Containers (STSC) contained in a Sludge Transport System (STS) cask. The STSC/STS cask will be transported to T Plant for interim storage of the STSC. The STS cask will be loaded with an empty STSC and returned to the KW Basin for loading of additional sludge for transportation and interim storage at T Plant. CH2MHILL Plateau Remediation Company (CHPRC) contracted with Fauske & Associates, LLC (FAI) to perform thermal and gas generation analyses for interim storage of STP sludge in the Sludge Transport and Storage Container (STSCs) at T Plant. The sludge types considered are settler sludge and sludge originating from the floor of the KW Basin and stored in containers 210 and 220, which are bounding compositions. The conditions specified by CHPRC for analysis are provided in Section 5. The FAI report (FAI/10-83, Thermal and Gas Analyses for a Sludge Transport and Storage Container (STSC) at T Plant) (refer to Attachment 1) documents the analyses. The process considered was passive, interim storage of sludge in various cells at T Plant. The FATE{trademark} code is used for the calculation. The results are shown in terms of the peak sludge temperature and hydrogen concentrations in the STSC and the T Plant cell. In particular, the concerns addressed were the thermal stability of the sludge and the potential for flammable gas mixtures. This work was performed with preliminary design information and a preliminary software configuration.

CROWE RD; APTHORPE R; LEE SJ; PLYS MG

2010-04-29T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Design and Optimization of Condenser and Centrifuge Units for Enhancement of a Batch Vacuum Frying System  

E-Print Network (OSTI)

A batch vacuum frying system, which processes fruits and vegetables, includes a frying pan, a surface-condenser, and a vacuum pump. With health and safety issues in mind, this research focused on developing a modified surface-condenser to prevent cavitation of the vacuum pump. The final oil-content was reduced by centrifugal de- oiling of the product under vacuum, which make the product healthier than what is currently available. The de-oiling mechanism consists of a centrifuge with a motor attached to the basket shaft, rotating up to 750 rpm (63 g units). The condenser consists of a (counter- flow) spiral-coil heat exchanger (SHE) connected to a refrigeration system that uses R404a refrigerant. De-oiling for 40 s at 300 and 750 RPM removed up to 67% and 72% of the chip’s surface oil, respectively. At 750 RPM for 10 s, 40 s, and 60 s the oil-content was reduced by 38%, 44%, and 51%, respectively. The convective heat transfer coefficient (h) of the frying oil was determined at 120°C and 140°C using the lumped capacitance method. The h-values were 217±13 W/m2K (120°C) and 258±37 W/m2K (140°C) using a copper-ball thermocouple. The h- values increased to 3.6 times during the boiling period. COMSOLTM Multiphysics was used to model the heat transfer in the vacuum fryer pan. Based on the simulation results, a 1.5 cm thick insulation material was installed in the fryer to reduce the energy losses. The refrigeration system operates at Tevap = -26°C and Tcond = 50°C with 26°C sub-cooling. Sensitivity analysis showed that the system Coefficient of Performance (COP) was about 3.87 at these conditions and compressor power requirement (CPR) was 74 W (85% efficiency) when frying 30 g of potatoes slices. The best results were obtained at Tevap = -10°C and Tcond = 40°C with 26°C sub-cooling and superheat of 5°C. The predicted COP was 4 and the CPR 70 W. The ice-formation on coils reduced the condensation rate. Reducing the refrigerant temperature to -10°C (from -26°C) reduced the condensation rate by 30%. These results show a more effective vacuum frying system for high-quality fruits and vegetables than the system previously used.

Pandey, Akhilesh

2009-12-01T23:59:59.000Z

362

Chemical and physical property of rice straw waste and hospital sewage sludge in turned windrow aeration system  

Science Conference Proceedings (OSTI)

Most sewage sludge from hospital wastewater treatment plants in Northern Thailand are also being to incinerator and agricultural fields. Land application of hospital sewage sludge has serious effects on environmental. The main goal of this investigation ... Keywords: co-composting, hospital sewage sludge, rice straw waste, turned windrow aeration

Khajornsak Sopajaree; Apisit Sancom

2008-02-01T23:59:59.000Z

363

Grout and glass performance in support of stabilization/solidification of ORNL tank sludges  

Science Conference Proceedings (OSTI)

Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) and Bethel Valley Evaporator Storage Tanks (BVEST) pending treatment for disposal. In addition, some sludges and supernatants also requiring treatment remain in two inactive tank systems: the gunite and associated tanks (GAAT) and the old hydrofracture (OHF) tank. The waste consists of two phases: sludge and supernatant. The sludges contain a high amount of radioactivity, and some are classified as TRU sludges. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough to be defined as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste. Grouting and vitrification are currently two likely stabilization/solidification alternatives for mixed wastes. Grouting has been used to stabilize/solidify hazardous and low-level radioactive waste for decades. Vitrification has been developed as a high-level radioactive alternative for decades and has been under development recently as an alternative disposal technology for mixed waste. The objective of this project is to define an envelope, or operating window, for grout and glass formulations for ORNL tank sludges. Formulations will be defined for the average composition of each of the major tank farms (BVEST/MVST, GAAT, and OHF) and for an overall average composition of all tank farms. This objective is to be accomplished using surrogates of the tank sludges with hot testing of actual tank sludges to check the efficacy of the surrogates.

Spence, R.D.; Mattus, C.H.; Mattus, A.J.

1998-09-01T23:59:59.000Z

364

Impact of EPS on Digestion of Waste Activate Sludge Thomas Gostanian  

E-Print Network (OSTI)

is by either aerobic or anaerobic self-digestion, in which the bacteria consume their own mass. Currently are particular in their assistance of either aerobic or anaerobic digestion. Direct samples of activated sludgeImpact of EPS on Digestion of Waste Activate Sludge Thomas Gostanian Faculty Mentor: Professor Chul

Mountziaris, T. J.

365

Anaerobic treatment of sludge from a nitrification-denitrification landfill leachate plant  

Science Conference Proceedings (OSTI)

The viability of anaerobic digestion of sludge from a MSW landfill leachate treatment plant, with COD values ranging between 15,000 and 19,400 mg O{sub 2} dm{sup -3}, in an upflow anaerobic sludge blanket reactor was studied. The reactor employed had a useful capacity of 9 l, operating at mesophilic temperature. Start-up of the reactor was carried out in different steps, beginning with diluted sludge and progressively increasing the amount of sludge fed into the reactor. The study was carried out over a period of 7 months. Different amounts of methanol were added to the feed, ranging between 6.75 and 1 cm{sup 3} dm{sup -3} of feed in order to favour the growth of methanogenic flora. The achieved biodegradation of the sludge using an upflow anaerobic sludge blanket Reactor was very high for an HRT of 9 days, obtaining decreases in COD of 84-87% by the end of the process. Purging of the digested sludge represented {approx}16% of the volume of the treated sludge.

Maranon, E. [Chemical and Environmental Engineering Department, Higher Polytechnic School of Engineering, University of Oviedo, Campus of Viesques, 33204 Gijon (Spain)]. E-mail: emara@uniovi.es; Castrillon, L. [Chemical and Environmental Engineering Department, Higher Polytechnic School of Engineering, University of Oviedo, Campus of Viesques, 33204 Gijon (Spain); Fernandez, Y. [Chemical and Environmental Engineering Department, Higher Polytechnic School of Engineering, University of Oviedo, Campus of Viesques, 33204 Gijon (Spain); Fernandez, E. [COGERSA, 33697 Serin, Gijon (Spain)

2006-07-01T23:59:59.000Z

366

Investigation of EPS Characteristics and their Effects on Waste Activated Sludge Digestion  

E-Print Network (OSTI)

be accomplished through use of aerobic or anaerobic self digestion, but choice of digestion type in practice to predict aerobic and anaerobic digestion potential. Future Work: · The anaerobic reactors are still running sludge. It performs only slightly better than the unsonicated sludge in anaerobic digestion

Mountziaris, T. J.

367

Segregation of Uranium Metal from K Basin Sludge: Results from Vendor Testing  

SciTech Connect

Under contract to Fluor Hanford, Pacific Northwest National Laboratory directed laboratory, bench-scale, and pilot-scale vendor testing to evaluate the use of commercial gravity mineral concentration technology to remove and concentrate uranium metal from Hanford K Basin sludge. Uranium metal in the sludge corrodes by reacting with water to generate heat and hydrogen gas, and may constrain shipment and disposal of the sludge to the Waste Isolation Pilot Plant as remote-handled transuranic waste. Separating uranium metal from the K Basin sludge is expected to be similar to some gold recovery operations. Consequently, the capabilities of commercial gravity mineral concentration technologies were assessed for their applicability to K Basin sludge streams. Overall, the vendor testing demonstrated the technical feasibility of using gravity concentration equipment to separate the K Basin sludge into a high-volume uranium metal-depleted stream and a low-volume uranium metal-rich stream. I n test systems, more than 96% of the uranium metal surrogate was concentrated into 10 to 30% of the sludge mass (7 to 24% of the sludge volume). With more prototypical equipment and stream recycle, higher recoveries may be achieved.

Schmidt, Andrew J.; Elmore, Monte R.; Delegard, Calvin H.

2004-09-21T23:59:59.000Z

368

SLUDGE PARTICLE SEPAPATION EFFICIENCIES DURING SETTLER TANK RETRIEVAL INTO SCS-CON-230  

SciTech Connect

The purpose of this document is to release, into the Hanford Document Control System, FA1/0991, Sludge Particle Separation Efficiencies for the Rectangular SCS-CON-230 Container, by M. Epstein and M. G. Plys, Fauske & Associates, LLC, June 2009. The Sludge Treatment Project (STP) will retrieve sludge from the 105-K West Integrated Water Treatment System (IWTS) Settler Tanks and transfer it to container SCS-CON-230 using the Settler Tank Retrieval System (STRS). The sludge will enter the container through two distributors. The container will have a filtration system that is designed to minimize the overflow of sludge fines from the container to the basin. FAI/09-91 was performed to quantify the effect of the STRS on sludge distribution inside of and overflow out of SCS-CON-230. Selected results of the analysis and a system description are discussed. The principal result of the analysis is that the STRS filtration system reduces the overflow of sludge from SCS-CON-230 to the basin by roughly a factor of 10. Some turbidity can be expected in the center bay where the container is located. The exact amount of overflow and subsequent turbidity is dependent on the density of the sludge (which will vary with location in the Settler Tanks) and the thermal gradient between the SCS-CON-230 and the basin. Attachment A presents the full analytical results. These results are applicable specifically to SCS-CON-230 and the STRS filtration system's expected operating duty cycles.

DEARING JI; EPSTEIN M; PLYS MG

2009-07-16T23:59:59.000Z

369

Modeling of Sludge Compost Maturity Degree Based on Radial Basic Function Network for Sewage Treatment  

Science Conference Proceedings (OSTI)

Because of the complicated interaction of the sludge compost components, it makes the compost maturity degree judging system appear the non-linearity and uncertainty. According to the physical circumstances of sludge compost, a compost maturity degree ... Keywords: Compost, Maturity degree, Radial basic function network, Modeling

Jingwen Tian; Meijuan Gao; Yanxia Liu; Shiru Zhou; Fan Zhang

2008-10-01T23:59:59.000Z

370

Characteristics of Dewatered Sewage Sludge and Green Waste Co-composting  

Science Conference Proceedings (OSTI)

The purpose of this work is to study the characteristics of the co-composting of sewage sludge and green waste (weight ratio 8:1). The indexes such as temperature, total nitrogen and total organic carbon contents, germination index, were analyzed to ... Keywords: sewage sludge, Composting, Maturity index

Hua Zhang; Delong Lv; Leilei Wei

2011-08-01T23:59:59.000Z

371

A Collaborative Effort to Address the Distribution of Plutonium-Contaminated Sludge in Livermore, California  

E-Print Network (OSTI)

For over a half-century, the U.S. Department of Energy nuclear weapons laboratory in Livermore, California has worked with plutonium in the course of its mission to research and develop nuclear weapons. Plutonium releases via the Laboratory’s sewer system resulted in the contamination of sewage sludge that was distributed and used widely as soil conditioner in parks, landscaping around public buildings, and in home lawns and gardens. The amount of sludge distributed and the concentration of the radioactivity in the sludge are uncertain. In 1999, research was undertaken to investigate the historic distribution of sewage sludge (1958-1976) in Livermore. Navigating the uncertainties surrounding the sludge distribution more than forty years after it began presented an enormous ethical challenge. Community members who received the sludge at no cost were not told that the sludge they received may have been contaminated with plutonium, and the log-book that had recorded the names and addresses of sludge recipients had disappeared. The half-life of weapons-grade plutonium is about 24,000 years. Therefore, former, current, and future Livermore residents are at potential increased risk of cancer and other health impacts from their largely unrecognized and therefore unavoidable

Patrice Sutton; A Jacqueline Cabasso; A Tracy Barreau; B Marylia Kelley C

2007-01-01T23:59:59.000Z

372

TEMPEST code modifications and testing for erosion-resisting sludge simulations  

Science Conference Proceedings (OSTI)

The TEMPEST computer code has been used to address many waste retrieval operational and safety questions regarding waste mobilization, mixing, and gas retention. Because the amount of sludge retrieved from the tank is directly related to the sludge yield strength and the shear stress acting upon it, it is important to incorporate the sludge yield strength into simulations of erosion-resisting tank waste retrieval operations. This report describes current efforts to modify the TEMPEST code to simulate pump jet mixing of erosion-resisting tank wastes and the models used to test for erosion of waste sludge with yield strength. Test results for solid deposition and diluent/slurry jet injection into sludge layers in simplified tank conditions show that the modified TEMPEST code has a basic ability to simulate both the mobility and immobility of the sludges with yield strength. Further testing, modification, calibration, and verification of the sludge mobilization/immobilization model are planned using erosion data as they apply to waste tank sludges.

Onishi, Y.; Trent, D.S.

1998-01-01T23:59:59.000Z

373

Enhancement of methane production in the anaerobic digestion of sewage sludges  

DOE Green Energy (OSTI)

The effect of powdered activated carbon on stressed anaerobic digesters utilizing a sewage sludge substrate was evaluated. The addition of carbon resulted in increased methanee production and greater process stability. The degree of enhancement appeared to be proportional to carbon concentration over the dose range studied (500-10,000 mg/l). A maximum increase in methane production of about 150% was observed at the highest carbon dose. The effect of 1500 mg/l carbon, 4000 mg/l coal, and 4000 mg/l flyash on relatively unstressed digesters was also examined. Units using a sewage sludge substrate were operated at 10 and 20 day SRT's. A 12% increase in methane production was observed in a carbon dosed digester functioning at a 10 day detention time. Enhancement was not evident with carbon at a 20 day SRT. No significant improvement in methane production was obtained in any of the digesters using coal or flyash as additives. Using the experimental data, a technique was developed for estimating the efficiencies of the methane forming and acid forming steps in the anaerobic digestion process. The results indicated that in stressed systems both stages of the digestion process were enhanced by the addition of powdered carbon. In the relatively unstressed systems, when enhancement did occur, only the scid forming step was affected. This information will supplement current research at determining the mechanism(s) by which carbon enhances the digestion process.Based on the results of this study, it appears that the benefits of carbon addition are greatest in stressed systems. Only very moderate increases in methane production would probably be attainable in well operating digesters. Coal and flyash do not seem to be effective in enhancing gas production in unstressed systems. However, their effectiveness has not been tested in stressed situations.

Spencer, R.R.

1978-05-10T23:59:59.000Z

374

SEISMIC DESIGN REQUIREMENTS SELECTION METHODOLOGY FOR THE SLUDGE TREATMENT & M-91 SOLID WASTE PROCESSING FACILITIES PROJECTS  

SciTech Connect

In complying with direction from the U.S. Department of Energy (DOE), Richland Operations Office (RL) (07-KBC-0055, 'Direction Associated with Implementation of DOE-STD-1189 for the Sludge Treatment Project,' and 08-SED-0063, 'RL Action on the Safety Design Strategy (SDS) for Obtaining Additional Solid Waste Processing Capabilities (M-91 Project) and Use of Draft DOE-STD-I 189-YR'), it has been determined that the seismic design requirements currently in the Project Hanford Management Contract (PHMC) will be modified by DOE-STD-1189, Integration of Safety into the Design Process (March 2007 draft), for these two key PHMC projects. Seismic design requirements for other PHMC facilities and projects will remain unchanged. Considering the current early Critical Decision (CD) phases of both the Sludge Treatment Project (STP) and the Solid Waste Processing Facilities (M-91) Project and a strong intent to avoid potentially costly re-work of both engineering and nuclear safety analyses, this document describes how Fluor Hanford, Inc. (FH) will maintain compliance with the PHMC by considering both the current seismic standards referenced by DOE 0 420.1 B, Facility Safety, and draft DOE-STD-1189 (i.e., ASCE/SEI 43-05, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, and ANSI!ANS 2.26-2004, Categorization of Nuclear Facility Structures, Systems and Components for Seismic Design, as modified by draft DOE-STD-1189) to choose the criteria that will result in the most conservative seismic design categorization and engineering design. Following the process described in this document will result in a conservative seismic design categorization and design products. This approach is expected to resolve discrepancies between the existing and new requirements and reduce the risk that project designs and analyses will require revision when the draft DOE-STD-1189 is finalized.

RYAN GW

2008-04-25T23:59:59.000Z

375

Microsoft Word - 2010 Hanford Sludge Treatment Project Visit _May 17-19 2010_ _final_  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tour of the Hanford Sludge Treatment Project - May 17-19, 2010 Tour of the Hanford Sludge Treatment Project - May 17-19, 2010 The U.S. Department of Energy Office of Independent Oversight, within the Office of Health, Safety and Security (HSS), conducted an orientation visit to the Department of Energy, Richland Operations Office (DOE-RL) and the Hanford Site in Richland, Washington during the period May 17-19, with DOE-RL managers/staff and contractor managers and supporting staff responsible for the ongoing K-Basins Sludge Treatment Project. The purpose of the visit was to ascertain ways in which HSS would be able to carry out its independent oversight responsibilities with respect to this project in a method that encourages collaboration with DOE-RL. The K-Basin Sludge Treatment Project involves transferring sludge that has been recovered from

376

Site Visit Report, Hanford Sludge Treatment Project 105-KW - August 2011 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sludge Treatment Project 105-KW - August Sludge Treatment Project 105-KW - August 2011 Site Visit Report, Hanford Sludge Treatment Project 105-KW - August 2011 August 2011 Hanford Sludge Treatment Project 105-KW Final Safety Analysis Report Review This report documents the results of a review conducted by the Office of Health, Safety and Security (HSS) of selected aspects of the 105-KW Basin Final Safety Analysis Report (HNF-SD-WM-SAR-062, Revision 14C) for the Sludge Treatment Project at the Hanford Site. HSS's review of the K-West Basin FSAR found it to be generally adequate with respect to the scope of this review. However, some aspects of the FSAR accident analyses of two events may warrant further review: MCO transport cask drop into the K-Basin, and the fire accident event involving the cask

377

Composition and Technical Basis for K Basin Settler Sludge Simulant for Inspection, Retrieval, and Pump Testing  

SciTech Connect

This report provides the formulation and technical basis for a K Basin Settler Tank Sludge simulant that will be used by the K Basin Closure Project (KBC) to test and develop equipment/approaches for Settler Tank sludge level measurement and retrieval in a mock-up test system of the actual Settler Tanks. The sludge simulant may also be used to demonstrate that the TOYO high pressure positive displacement pump design (reversing valves and hollow balls) is suitable for transfer of Settler Tank sludge from the K West (KW) Basin to the Cold Vacuum Drying Facility (CVDF) (~500 ft). As requested the by the K Basins Sludge Treatment Project (STP) the simulant is comprised of non-radioactive (and non-uranium) constituents.

Schmidt, Andrew J.; Zacher, Alan H.

2007-06-25T23:59:59.000Z

378

Grout and Glass Performance in Support of Stabilization/Solidification of the MVST Tank Sludges  

SciTech Connect

Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) pending treatment for disposal. The waste separates into two phases: sludge and supematant. Some of the supematant from these tanks has been decanted, solidified into a grout, and stored for disposal as a solid low-level waste. The sludges in the tank bottoms have been accumulating ,for several years. Some of the sludges contain a high amount of gamma activity (e.g., `37CS concentration range of 0.01 3-11 MBq/g) and contain enough transuranic (TRU) radioisotopes to be classified as TRU wastes. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough in the available total constituent analysis for the MVST sludge to be classified as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste.

Gilliam, T.M.; Spence, R.D.

1998-11-01T23:59:59.000Z

379

Applicability of the sludge processing technical standard to type IV waste tanks with high fluoride concentration  

SciTech Connect

Type IV waste tanks at the Savannah River Plant which contain ballast water (tanks 17, 18, 19, 20, and 24) have solution compositions that are generally within the database developed for corrosion protection of the sludge processing tanks. Therefore the technical standard covering tank chemistry limits during sludge processing is applicable to the Type TV tanks. However, Tank 20 contains levels of fluoride higher than those treated in the sludge processing database. To confirm the applicability of the sludge processing technical standard, cyclic potentiodynamic polarization scans for pitting susceptibility were run in a simulant of the Tank 20 contents. The nitrite inhibitor level specified by the standards did inhibit pitting corrosion in the simulant. Pitting was inhibited also at the same nitrite level but with 30 percent higher concentrations of chloride, fluoride, and sulfate. Thus the sludge processing technical standard has been shown to provide corrosion protection to type IV tanks containing ballast water.

Zapp, P.E.

1992-03-31T23:59:59.000Z

380

Rocky Flats ash test procedure (sludge stabilization)  

SciTech Connect

Rocky Flats Ash items have been identified as the next set of materials to be stabilized. This test is being run to determine charge sizes and soak times to completely stabilize the Rocky Flats Ash items. The information gathered will be used to generate the heating rampup cycle for stabilization. This test will also gain information on the effects of the glovebox atmosphere (moisture) on the stabilized material. This document provides instructions for testing Rocky Flats Ash in the HC-21C muffle furnace process.

Winstead, M.L.

1995-09-14T23:59:59.000Z

Note: This page contains sample records for the topic "determination sludge batch" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.