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Sample records for actual tank samples

  1. CHARACTERIZATION AND ACTUAL WASTE TEST WITH TANK 5F SAMPLES

    SciTech Connect

    Hay, M. S.; Crapse, K. P.; Fink, S. D.; Pareizs, J. M.

    2007-08-30

    The initial phase of bulk waste removal operations was recently completed in Tank 5F. Video inspection of the tank indicates several mounds of sludge still remain in the tank. Additionally, a mound of white solids was observed under Riser 5. In support of chemical cleaning and heel removal programs, samples of the sludge and the mound of white solids were obtained from the tank for characterization and testing. A core sample of the sludge and Super Snapper sample of the white solids were characterized. A supernate dip sample from Tank 7F was also characterized. A portion of the sludge was used in two tank cleaning tests using oxalic acid at 50 C and 75 C. The filtered oxalic acid from the tank cleaning tests was subsequently neutralized by addition to a simulated Tank 7F supernate. Solids and liquid samples from the tank cleaning test and neutralization test were characterized. A separate report documents the results of the gas generation from the tank cleaning test using oxalic acid and Tank 5F sludge. The characterization results for the Tank 5F sludge sample (FTF-05-06-55) appear quite good with respect to the tight precision of the sample replicates, good results for the glass standards, and minimal contamination found in the blanks and glass standards. The aqua regia and sodium peroxide fusion data also show good agreement between the two dissolution methods. Iron dominates the sludge composition with other major contributors being uranium, manganese, nickel, sodium, aluminum, and silicon. The low sodium value for the sludge reflects the absence of supernate present in the sample due to the core sampler employed for obtaining the sample. The XRD and CSEM results for the Super Snapper salt sample (i.e., white solids) from Tank 5F (FTF-05-07-1) indicate the material contains hydrated sodium carbonate and bicarbonate salts along with some aluminum hydroxide. These compounds likely precipitated from the supernate in the tank. A solubility test showed the material

  2. Comparison of simulants to actual neutralized current acid waste: Process and product testing of three NCAW core samples from Tanks 101-AZ and 102-AZ

    SciTech Connect

    Morrey, E.V.; Tingey, J.M.

    1996-04-01

    A vitrification plant is planned to process the high-level waste (HLW) solids from Hanford Site tanks into canistered glass logs for disposal in a national repository. Programs have been established within the Pacific Northwest Laboratory Vitrification Technology Development (PVTD) Project to test and model simulated waste to support design, feed processability, operations, permitting, safety, and waste-form qualification. Parallel testing with actual radioactive waste is being performed on a laboratory-scale to confirm the validity of using simulants and glass property models developed from simulants. Laboratory-scale testing has been completed on three radioactive core samples from tanks 101-AZ and 102-AZ containing neutralized current acid waste (NCAW), which is one of the first waste types to be processed in the high-level waste vitrification plant under a privatization scenario. Properties of the radioactive waste measured during process and product testing were compared to simulant properties and model predictions to confirm the validity of simulant and glass property models work. This report includes results from the three NCAW core samples, comparable results from slurry and glass simulants, and comparisons to glass property model predictions.

  3. Comparison of simulants to actual neutralized current acid waste: process and product testing of three NCAW core samples from Tanks 101-AZ and 102-AZ

    SciTech Connect

    Morrey, E.V.; Tingey, J.M.; Elliott, M.L.

    1996-10-01

    A vitrification plant is planned to process the high-level waste (HLW) solids from Hanford Site tanks into canistered glass logs for disposal in a national repository. Programs were established within the Pacific Northwest Laboratory Vitrification Technology Development (PVTD) Project to test and model simulated waste to support design, feed processability, operations, permitting, safety, and waste-form qualification. Parallel testing with actual radioactive waste was performed on a laboratory-scale to confirm the validity of using simulants and glass property models developed from simulants. Laboratory-scale testing has been completed on three radioactive core samples from tanks 101-AZ and 102-AZ containing neutralized current acid waste (NCAW), which is one of the first waste types to be processed in the high-level waste vitrification plant under a privatization scenario. Properties of the radioactive waste measured during process and product testing were compared to simulant properties and model predictions to confirm the validity of simulant and glass property ,models work. This report includes results from the three NCAW core samples, comparable results from slurry and glass simulants, and comparisons to glass property model predictions.

  4. FRACTIONAL CRYSTALLIZATION FLOWSHEET TESTS WITH ACTUAL TANK WASTE

    SciTech Connect

    HERTING, D.L.

    2006-10-18

    Laboratory-scale flowsheet tests of the fractional crystallization process were conducted with actual tank waste samples in a hot cell at the 222-S Laboratory. The process is designed to separate medium-curie liquid waste into a low-curie stream for feeding to supplemental treatment and a high-curie stream for double-shell tank storage. Separations criteria (for Cs-137 sulfate, and sodium) were exceeded in all three of the flowsheet tests that were performed.

  5. FRACTIONAL CRYSTALLIZATION FLOWSHEET TESTS WITH ACTUAL TANK WASTE

    SciTech Connect

    HERTING, D.L.

    2007-04-13

    Laboratory-scale flowsheet tests of the fractional crystallization process were conducted with actual tank waste samples in a hot cell at the 2224 Laboratory. The process is designed to separate medium-curie liquid waste into a low-curie stream for feeding to supplemental treatment and a high-curie stream for double-shell tank storage. Separations criteria (for Cesium-137 sulfate and sodium) were exceeded in all three of the flowsheet tests that were performed.

  6. Waste tank sample transport

    SciTech Connect

    Field, J.G.; Mercado, M.S.; Smith, R.J.; Thornton, J.W.

    1994-08-01

    Since 1943, radioactive liquid waste has been stored in underground storage tanks at the Hanford Site in Richland, Washington. The waste was the result of chemical separation processes for the production of fissile defense materials. Associated with the current environmental cleanup mission, waste characterization and processing programs are requiring the extraction of samples from the tanks. Approved onsite packaging are in place and in use for transfers of samples from the tanks to onsite laboratories. Initiatives are under way to develop and procure packaging for sample shipments to offsite laboratories. This paper will provide a current status of the tank sample packaging used at the Hanford Site, as well as the project status for new packaging to be used for offsite shipments.

  7. TANK 5 SAMPLING

    SciTech Connect

    Vrettos, N; William Cheng, W; Thomas Nance, T

    2007-11-26

    Tank 5 at the Savannah River Site has been used to store high level waste and is currently undergoing waste removal processes in preparation for tank closure. Samples were taken from two locations to determine the contents in support of Documented Safety Analysis (DSA) development for chemical cleaning. These samples were obtained through the use of the Drop Core Sampler and the Snowbank Sampler developed by the Engineered Equipment & Systems (EES) group of the Savannah River National Laboratory (SRNL).

  8. Vacuum Drying of Actual Transuranic Waste from Hanford Tanks

    SciTech Connect

    Tingey, Joel M.

    2004-05-20

    Composites of sludge from Tanks 241-B-203, 241-T-203, 241 T 204, and 241-T-110 at the Hanford Site were prepared at the Hanford 222-S Laboratory from core samples retrieved from these tanks. These tank composites may not be representative of the entire contents of the tank but provide some indication of the properties of the waste within these underground storage tanks. The composite samples were diluted with water at the Radiochemical Processing Laboratory at Pacific Northwest National Laboratory to represent the slurries that are expected to be received from tank retrieval operations and processed to produce a final waste stream. The dilutions were vacuum dried at 60 C and 26 in. of mercury ({approx} 100 torr). Semi-quantitative measurements of stickiness and cohesive strength were made on these dilutions as a function of drying time. Mass loss as a function of drying time and total solids concentration of the initial dilution and at the conclusion of drying were also measured. Visual observations of the sludge were recorded throughout the drying process.

  9. Tank 12H residuals sample analysis report

    SciTech Connect

    Oji, L. N.; Shine, E. P.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.

    2015-06-11

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 12H final characterization samples to determine the residual tank inventory prior to grouting. Eleven Tank 12H floor and mound residual material samples and three cooling coil scrape samples were collected and delivered to SRNL between May and August of 2014.

  10. PCB Analysis Plan for Tank Archive Samples

    SciTech Connect

    NGUYEN, D.M.

    2001-03-22

    This analysis plan specifies laboratory analysis, quality assurance/quality control (QA/QC), and data reporting requirements for analyzing polychlorinated biphenyls (PCB) concentrations in archive samples. Tank waste archive samples that are planned for PCB analysis are identified in Nguyen 2001. The tanks and samples are summarized in Table 1-1. The analytical data will be used to establish a PCB baseline inventory in Hanford tanks.

  11. FRACTIONAL CRYSTALLIZATION LABORATORY TESTING FOR INCLUSION & COPRECIPITATION WITH ACTUAL TANK WASTE

    SciTech Connect

    WARRANT, R.W.

    2006-12-11

    Fractional crystallization is being considered as a pretreatment method to support supplemental treatment of retrieved single-shell tank (SST) saltcake waste at the Hanford Site. The goal of the fractional crystallization process is to optimize the separation of the radioactivity (radionuclides) from the saltcake waste and send it to the Waste Treatment and Immobilization Plant and send the bulk of the saltcake to the supplemental treatment plant (bulk vitrification). The primary factors that influence the separation efficiency are (1) solid/liquid separation efficiency, (2) contaminant inclusions, and (3) co-precipitation. This is a report of testing for factors (2) and (3) with actual tank waste samples. For the purposes of this report, contaminant inclusions are defined as the inclusion of supernatant, containing contaminating radionuclides, in a pocket within the precipitating saltcake crystals. Co-precipitation is defined as the simultaneous precipitation of a saltcake crystal with a contaminating radionuclide. These two factors were tested for various potential fractional crystallization product salts by spiking the composite tank waste samples (SST Early or SST Late, external letter CH2M-0600248, ''Preparation of Composite Tank Waste Samples for ME-21 Project'') with the desired target salt and then evaporating to precipitate that salt. SST Early represents the typical composition of dissolved saltcake early in the retrieval process, and SST Late represents the typical composition during the later stages of retrieval.

  12. 340 Representative sampling verification tank sampling and analysis plan

    SciTech Connect

    Olander, A.R., Westinghouse Hanford

    1996-08-07

    This Sampling and Analysis Plan contains requirements for characterizing the 340 vault tank 1. The objective of the sampling and characterization is to determine if the tank is homogeneous when agitated and which sampling method provides the most representative sample. A secondary objective is to collect and characterize solid samples.

  13. 340 Representative sampling verification tank sampling and analysis plan

    SciTech Connect

    Olander, A.R., Westinghouse Hanford

    1996-08-21

    This Sampling and Analysis Plan contains requirements for characterizing the 340 vault tank 1. The objective of the sampling and characterization is to determine if the tank is homogeneous when agitated and which sampling method provides the most representative sample. A secondary objective is to collect and characterize solid samples.

  14. 340 representative sampling verification tank sampling and analysis plan

    SciTech Connect

    Halgren, D.L., Westinghouse Hanford

    1996-09-09

    This Sampling and Analysis Plan contains requirements for characterizing the 340 vault tank 1. The objective of the sampling and characterization is to determine if the tank is homogeneous when agitated and which sampling method provides the most representative sample. A secondary objective is to collect and characterize solid samples.

  15. Task Technical and Quality Assurance Plan for Determining Uranium and Plutonium Solubility in Actual Tank Waste Supernates

    SciTech Connect

    King, William D.

    2005-06-28

    Savannah River Site tank waste supernates contain small quantities of dissolved uranium and plutonium. Due to the large volume of supernates, significant quantities of dissolved uranium and plutonium are managed as part of waste transfers, evaporation and pretreatment at the Savannah River Site in tank farm operations, the Actinide Removal Project (ARP), and the Salt Waste Processing Facility (SWPF). Previous SRNL studies have investigated the effect of temperature and major supernate components on the solubility of uranium and plutonium. Based on these studies, equations were developed for the prediction of U and Pu solubility in tank waste supernates. The majority of the previous tests were conducted with simulated waste solutions. The current testing is intended to determine solubility in actual tank waste samples (as-received, diluted, and combinations of tank samples) as a function of composition and temperature. Results will be used to validate and build on the existing solubility equations.

  16. CHARACTERIZATION OF TANK 19F SAMPLES

    SciTech Connect

    Oji, L.; Diprete, D.; Click, D.

    2009-12-17

    The Savannah River National Laboratory (SRNL) was asked by Liquid Waste Operations to characterize Tank 19F closure samples. Tank 19F slurry samples analyzed included the liquid and solid fractions derived from the slurry materials along with the floor scrape bottom Tank 19F wet solids. These samples were taken from Tank 19F in April 2009 and made available to SRNL in the same month. Because of limited amounts of solids observed in Tank 19F samples, the samples from the north quadrants of the tank were combined into one Tank 19F North Hemisphere sample and similarly the south quadrant samples were combined into one Tank 19F South Hemisphere sample. These samples were delivered to the SRNL shielded cell. The Tank 19F samples were analyzed for radiological, chemical and elemental components. Where analytical methods yielded additional contaminants other than those requested by the customer, these results were also reported. The target detection limits for isotopes analyzed were based on detection values of 1E-04 {micro}Ci/g for most radionuclides and customer desired detection values of 1E-05 {micro}Ci/g for I-129, Pa-231, Np-237, and Ra-226. While many of the target detection limits, as specified in the technical task request and task technical and quality assurance plans were met for the species characterized for Tank 19F, some were not met. In a number of cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. SRNL, in conjunction with the plant customer, reviewed all these cases and determined that the impacts were negligible.

  17. CHARACTERIZATION OF THE TANK 18F SAMPLES

    SciTech Connect

    Oji, L.; Click, D.; Diprete, D.

    2009-12-17

    The Savannah River National Laboratory (SRNL) was asked by Liquid Waste Operations to characterize Tank 18F closure samples. Tank 18F slurry samples analyzed included the liquid and solid fractions derived from the 'as-received' slurry materials along with the floor scrape bottom Tank 18F wet solids. These samples were taken from Tank 18F in March 2009 and made available to SRNL in the same month. Because of limited amounts of solids observed in Tank 18F samples, the samples from the north quadrants of the tank were combined into one North Tank 18F Hemisphere sample and similarly the south quadrant samples were combined into one South Tank 18F Hemisphere sample. These samples were delivered to the SRNL shielded cell. The Tank 18F samples were analyzed for radiological, chemical and elemental components. Where analytical methods yielded additional contaminants other than those requested by the customer, these results were also reported. The target detection limits for isotopes analyzed were 1E-04 {micro}Ci/g for most radionuclides and customer desired detection values of 1E-05 {micro}Ci/g for I-129, Pa-231, Np-237, and Ra-226. While many of the minimum detection limits, as specified in the technical task request and task technical and quality assurance plans were met for the species characterized for Tank 18F, some were not met due to spectral interferences. In a number of cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. SRNL, in conjunction with the plant customer, reviewed all these cases and determined that the impacts were negligible.

  18. Data Report for Catch Tank Vapor Sampling

    SciTech Connect

    NGUYEN, D.M.

    2000-09-28

    CH2M HILL Hanford Group, Inc. (CHG) is responsible for developing and maintaining the authorization basis for River Protection Project (RPP) facilities and operations. This responsibility includes closure of the Flammable Gas Unreviewed Safety Question (USQ) for waste tank ancillary equipment such as catch tanks, double-contained receiver tanks, 244-AR and 244-CR vaults, 242-S and 242-T Evaporators, and inactive miscellaneous underground storage tanks. To support closure of the Flammable Gas USQ for catch tanks, an analysis of the flammable gas hazard was performed. This document provides a summary of flammable gas data obtained from RPP active catch tanks in FY 2000. Flammable gas level measurements for each catch tank (other than 241-AX-152) are discussed on a tank-by-tank basis in Section 3.0. Conclusions based on the data are provided in Section 4.0. This section also includes recommendations that would be useful when conducting vapor sampling for other miscellaneous tanks (e.g., inactive miscellaneous underground storage tanks).

  19. RECOMMENDATIONS FOR SAMPLING OF TANK 19 IN F TANK FARM

    SciTech Connect

    Harris, S.; Shine, G.

    2009-12-14

    Representative sampling is required for characterization of the residual material in Tank 19 prior to operational closure. Tank 19 is a Type IV underground waste storage tank located in the F-Tank Farm. It is a cylindrical-shaped, carbon steel tank with a diameter of 85 feet, a height of 34.25 feet, and a working capacity of 1.3 million gallons. Tank 19 was placed in service in 1961 and initially received a small amount of low heat waste from Tank 17. It then served as an evaporator concentrate (saltcake) receiver from February 1962 to September 1976. Tank 19 also received the spent zeolite ion exchange media from a cesium removal column that once operated in the Northeast riser of the tank to remove cesium from the evaporator overheads. Recent mechanical cleaning of the tank removed all mounds of material. Anticipating a low level of solids in the residual waste, Huff and Thaxton [2009] developed a plan to sample the waste during the final clean-up process while it would still be resident in sufficient quantities to support analytical determinations in four quadrants of the tank. Execution of the plan produced fewer solids than expected to support analytical determinations in all four quadrants. Huff and Thaxton [2009] then restructured the plan to characterize the residual separately in the North and the South regions: two 'hemispheres.' This document provides sampling recommendations to complete the characterization of the residual material on the tank bottom following the guidance in Huff and Thaxton [2009] to split the tank floor into a North and a South hemisphere. The number of samples is determined from a modification of the formula previously published in Edwards [2001] and the sample characterization data for previous sampling of Tank 19 described by Oji [2009]. The uncertainty is quantified by an upper 95% confidence limit (UCL95%) on each analyte's mean concentration in Tank 19. The procedure computes the uncertainty in analyte concentration as a

  20. Small Waste Tank Sampling and Retrieval System

    SciTech Connect

    Magleby, Mary Theresa

    2002-08-01

    At the Test Reactor Area of the Idaho National Engineering and Environmental Laboratory (INEEL), four 1500-gal catch tanks were found to contain RCRAhazardous waste. A system was needed to obtain a representative sample of the liquid, as well as the hardpacked heels, and to ultimately homogenize and remove the tank contents for disposal. After surveying the available technologies, the AEA Fluidic Pulse Mixing and Retrieval System was chosen for a technology demonstration. A demonstration, conducted with nonhazardous surrogate material, proved that the system was capable of loosening the hard-packed heel, homogenizing the entire tank contents, and collecting a representative sample. Based on the success of the demonstration, a detailed evaluation was done to determine the applicability of the system to other tanks. The evaluation included the sorting of data on more than 700 tanks to select candidates for further deployment of the system. A detailed study was also done to determine if the purchase of a second system would be cost effective. The results of the evaluation indicated that a total of thirteen tanks at the INEEL are amenable to sampling and/or remediation using the AEA Fluidic Pulse Mixing and Retrieval System. Although the currently-owned system appears sufficient for the needs of one INEEL program, it is insufficient to meet the combined needs at the INEEL. The INEEL will commence operation of the system on the TRA-730 Catch Tank System in June 2002.

  1. RECOMMENDATIONS FOR SAMPLING OF TANK 18 IN F TANK FARM

    SciTech Connect

    Shine, G.

    2009-12-14

    Representative sampling is required for characterization of the residual floor material in Tank 18 prior to operational closure. Tank 18 is an 85-foot diameter, 34-foot high carbon steel tank with nominal operating volume of 1,300,000 gallons. It is a Type IV tank, and has been in service storing radioactive materials since 1959. Recent mechanical cleaning of the tank removed all mounds of material. Anticipating a low level of solids in the residual material, Huff and Thaxton [2009] developed a plan to sample the material during the final clean-up process while it would still be resident in sufficient quantities to support analytical determinations in four quadrants of the tank. Execution of the plan produced fewer solids than expected to support analytical determinations in all four quadrants. Huff and Thaxton [2009] then restructured the plan to characterize the residual floor material separately in the North and the South regions: two 'hemispheres.' This document provides sampling recommendations to complete the characterization of the residual material on the tank bottom following the guidance in Huff and Thaxton [2009] to split the tank floor into a North and a South hemisphere. The number of samples is determined from a modification of the formula previously published in Edwards [2001] and the sample characterization data for previous sampling of Tank 18 described by Oji [2009]. The uncertainty is quantified by an upper 95% confidence limit (UCL95%) on each analyte's mean concentration in Tank 18. The procedure computes the uncertainty in analyte concentration as a function of the number of samples, and the final number of samples is determined when the reduction in the uncertainty from an additional sample no longer has a practical impact on results. The characterization of the full suite of analytes in the North hemisphere is currently supported by a single Mantis rover sample obtained from a compact region near the center riser. A floor scrape sample was

  2. High priority tank sampling and analysis report

    SciTech Connect

    Brown, T.M.

    1998-03-05

    In July 1993, the Defense Nuclear Facilities Safety Board (DNFSB) transmitted Recommendation 93-5 (Conway 1993) to the US Department of Energy (DOE). Recommendation 93-5 noted that there was insufficient tank waste technical information and the pace to obtain it was too slow to ensure that Hanford Site wastes could be safely stored, that associated operations could be conducted safely, and that future disposal data requirements could be met. In May 1996, the DOE issued Revision 1 of the Recommendation 93-5 Implementation Plan (DOE-RL 1996). The Implementation Plan revision presented a modified approach to achieve the original plan`s objectives. The approach concentrated on actions necessary to ensure that wastes can be safely stored, that operations can be safely conducted, and that timely characterization information for the tank waste Disposal Program could be obtained. The Implementation Plan proposed 28 High Priority tanks, which, if sampled and analyzed, were expected to provide information to answer questions regarding safety and disposal issues. The High Priority tank list was originally developed in Section 9.0 of the Tank Waste Characterization Basis (Brown et al. 1995) by integrating the needs of the various safety and disposal programs. The High Priority tank list represents a set of tanks that were expected to provide the highest information return for characterization resources expended. The High Priority tanks were selected for near-term core sampling and were not expected to be the only tanks that would provide meaningful information. Sampling and analysis of non-High Priority tanks also could be used to provide scientific and technical data to confirm assumptions, calibrate models, and measure safety related phenomenological characteristics of the waste. When the sampling and analysis results of the High Priority and other tanks were reviewed, it was expected that a series of questions should be answered allowing key decisions to be made. The first

  3. Tank 241-C-109 vapor sampling and analysis tank characterization report. Revision 1

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank C-109. The drivers and objectives of the waste tank headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports.

  4. TESTING OF THE SPINTEK ROTARY MICROFILTER USING ACTUAL HANFORD WASTE SAMPLES

    SciTech Connect

    HUBER HJ

    2010-04-13

    The SpinTek rotary microfilter was tested on actual Hanford tank waste. The samples were a composite of archived Tank 241-AN-105 material and a sample representing single-shell tanks (SST). Simulants of the two samples have been used in non-rad test runs at the 222-S laboratory and at Savannah River National Laboratory (SRNL). The results of these studies are compared in this report. Two different nominal pore sizes for the sintered steel rotating disk filter were chosen: 0.5 and 0.1 {micro}m. The results suggest that the 0.5-{micro}m disk is preferable for Hanford tank waste for the following reasons: (1) The filtrate clarity is within the same range (<<4 ntu for both disks); (2) The filtrate flux is in general higher for the 0.5-{micro}m disk; and (3) The 0.1-{micro}m disk showed a higher likelihood of fouling. The filtrate flux of the actual tank samples is generally in the range of 20-30% compared to the equivalent non-rad tests. The AN-105 slurries performed at about twice the filtrate flux of the SST slurries. The reason for this difference has not been identified. Particle size distributions in both cases are very similar; comparison of the chemical composition is not conclusive. The sole hint towards what material was stuck in the filter pore holes came from the analysis of the dried flakes from the surface of the fouled 0.1-{micro}m disk. A cleaning approach developed by SRNL personnel to deal with fouled disks has been found adaptable when using actual Hanford samples. The use of 1 M nitric acid improved the filtrate flux by approximately two times; using the same simulants as in the non-rad test runs showed that the filtrate flux was restored to 1/2 of its original amount.

  5. Physical Property and Rheological Testing of Actual Transuranic Waste from Hanford Single-Shell Tanks

    SciTech Connect

    Tingey, Joel M. ); Gao, Johnway ); Delegard, Calvin H. ); Bagaasen, Larry M. ); Wells, Beric E. )

    2003-08-25

    Composites of sludge from Hanford tanks 241-B-203 (B-203), 241-T-203 (T-203), 241-T-204 (T-204), and 241-T-110 (T-110) were prepared at the Hanford 222-S Laboratory and transferred to the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory (PNNL) for measurement of the composites' physical properties. These tank composites were prepared from core samples retieved from these tanks. These core samples may not be representative of the entire contents of the tank but provide some indication of the properties of the waste in these underground storage tanks. Dilutions in water were prepared from the composite samples. The measurements included paint filter tests, viscosity, shear strength, settling and centrifuging behavior, a qualitative test of stickiness, total solids concentration, and extrusion tests to estimate shear strength.

  6. Tank 241-BY-106 vapor sampling and analysis tank characterization report. Revision 1

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    Tank 241-BY-106 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in {open_quotes}Program Plan for the Resolution of Tank Vapor Issues.{close_quotes} Tank 241-BY-106 was vapor sampled in accordance with {open_quotes}Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.{close_quotes}

  7. Tank 241-BY-105 vapor sampling and analysis tank characterization report. Revision 1

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    Tank 241-BY-105 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in {open_quotes}Program Plan for the Resolution of Tank Vapor Issues.{close_quotes} Tank 241-BY-105 was vapor sampled in accordance with {open_quotes}Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.{close_quotes}

  8. Characterization, Leaching, and Filtrations Testing of Ferrocyanide Tank sludge (Group 8) Actual Waste Composite

    SciTech Connect

    Fiskum, Sandra K.; Billing, Justin M.; Crum, J. V.; Daniel, Richard C.; Edwards, Matthew K.; Shimskey, Rick W.; Peterson, Reid A.; MacFarlan, Paul J.; Buck, Edgar C.; Draper, Kathryn E.; Kozelisky, Anne E.

    2009-02-28

    This is the final report in a series of eight reports defining characterization, leach, and filtration testing of a wide variety of Hanford tank waste sludges. The information generated from this series is intended to supplement the Waste Treatment and Immobilization Plant (WTP) project understanding of actual waste behaviors associated with tank waste sludge processing through the pretreatment portion of the WTP. The work described in this report presents information on a high-iron waste form, specifically the ferrocyanide tank waste sludge. Iron hydroxide has been shown to pose technical challenges during filtration processing; the ferrocyanide tank waste sludge represented a good source of the high-iron matrix to test the filtration processing.

  9. Vapor sampling of the headspace of radioactive waste storage tanks

    SciTech Connect

    Reynolds, D.A., Westinghouse Hanford

    1996-05-22

    This paper recants the history of vapor sampling in the headspaces of radioactive waste storage tanks at Hanford. The first two tanks to receive extensive vapor pressure sampling were Tanks 241-SY-101 and 241-C-103. At various times, a gas chromatography, on-line mass spectrometer, solid state hydrogen monitor, FTIR, and radio acoustic ammonia monitor have been installed. The head space gas sampling activities will continue for the next few years. The current goal is to sample the headspace for all the tanks. Some tank headspaces will be sampled several times to see the data vary with time. Other tanks will have continuous monitors installed to provide additional data.

  10. ACTUAL WASTE TESTING OF GYCOLATE IMPACTS ON THE SRS TANK FARM

    SciTech Connect

    Martino, C.

    2014-05-28

    Glycolic acid is being studied as a replacement for formic acid in the Defense Waste Processing Facility (DWPF) feed preparation process. After implementation, the recycle stream from DWPF back to the high-level waste Tank Farm will contain soluble sodium glycolate. Most of the potential impacts of glycolate in the Tank Farm were addressed via a literature review and simulant testing, but several outstanding issues remained. This report documents the actual-waste tests to determine the impacts of glycolate on storage and evaporation of Savannah River Site high-level waste. The objectives of this study are to address the following: Determine the extent to which sludge constituents (Pu, U, Fe, etc.) dissolve (the solubility of sludge constituents) in the glycolate-containing 2H-evaporator feed. Determine the impact of glycolate on the sorption of fissile (Pu, U, etc.) components onto sodium aluminosilicate solids. The first objective was accomplished through actual-waste testing using Tank 43H and 38H supernatant and Tank 51H sludge at Tank Farm storage conditions. The second objective was accomplished by contacting actual 2H-evaporator scale with the products from the testing for the first objective. There is no anticipated impact of up to 10 g/L of glycolate in DWPF recycle to the Tank Farm on tank waste component solubilities as investigated in this test. Most components were not influenced by glycolate during solubility tests, including major components such as aluminum, sodium, and most salt anions. There was potentially a slight increase in soluble iron with added glycolate, but the soluble iron concentration remained so low (on the order of 10 mg/L) as to not impact the iron to fissile ratio in sludge. Uranium and plutonium appear to have been supersaturated in 2H-evaporator feed solution mixture used for this testing. As a result, there was a reduction of soluble uranium and plutonium as a function of time. The change in soluble uranium concentration was

  11. TESTING OF ENHANCED CHEMICAL CLEANING OF SRS ACTUAL WASTE TANK 5F AND TANK 12H SLUDGES

    SciTech Connect

    Martino, C.; King, W.

    2011-08-22

    using SRS sludge tank sample material. A Task Technical and Quality Assurance Plan (TTQAP) details the experimental plan as outlined by the Technical Task Request (TTR). The TTR identifies that the data produced by this testing and results included in this report will support the technical baseline with portions having a safety class functional classification. The primary goals for SRNL RWT are as follows: (1) to confirm ECC performance with real tank sludge samples, (2) to determine the impact of ECC on fate of actinides and the other sludge metals, and (3) to determine changes, if any, in solids flow and settling behavior.

  12. STEAM REFORMING TECHNOLOGY DEMONSTRATION FOR THE DESTRUCTION OF ORGANICS ON ACTUAL DOE SAVANNAH RIVER SITE TANK 48H WASTE 9138

    SciTech Connect

    Burket, P

    2009-02-24

    This paper describes the design of the Bench-scale Steam Reformer (BSR); a processing unit for demonstrating steam reforming technology on actual radioactive waste [1]. It describes the operating conditions of the unit used for processing a sample of Savannah River Site (SRS) Tank 48H waste. Finally, it compares the results from processing the actual waste in the BSR to processing simulant waste in the BSR to processing simulant waste in a large pilot scale unit, the Fluidized Bed Steam Reformer (FBSR), operated at Hazen Research Inc. in Golden, CO. The purpose of this work was to prove that the actual waste reacted in the same manner as the simulant waste in order to validate the work performed in the pilot scale unit which could only use simulant waste.

  13. CHARACTERIZATION OF TANK 16H ANNULUS SAMPLES

    SciTech Connect

    Hay, M.; Reboul, S.

    2012-04-16

    The closure of Tank 16H will require removal of material from the annulus of the tank. Samples from Tank 16H annulus were characterized and tested to provide information to evaluate various alternatives for removing the annulus waste. The analysis found all four annulus samples to be composed mainly of Si, Na, and Al and lesser amounts of other elements. The XRD data indicate quartz (SiO{sub 2}) and sodium aluminum nitrate silicate hydrate (Na{sub 8}(Al{sub 6}Si{sub 6}O{sub 24})(NO{sub 3}){sub 2}.4H{sub 2}O) as the predominant crystalline mineral phases in the samples. The XRD data also indicate the presence of crystalline sodium nitrate, sodium nitrite, gibbsite, hydrated sodium bicarbonate, and muscovite. Based on the weight of solids remaining at the end of the test, the water leaching test results indicate approximately 20-35% of the solids dissolved after three contacts with an approximately 3:1 volume of water at 45 C. The chemical analysis of the leachates and the XRD results of the remaining solids indicate sodium salts of nitrate, nitrite, sulfate, and possibly carbonate/bicarbonate make up the majority of the dissolved material. The majority of these salts were dissolved in the first water contact and simply diluted with each subsequent water contact. The water leaching removed large amounts of the uranium in two of the samples and {approx}1/3 of the {sup 99}Tc from all four samples. Most of the other radionuclides analyzed showed low solubility in the water leaching test. The preliminary data on the oxalic acid leaching test indicate the three acid contacts at 45 C dissolved from {approx}34-47% of the solids. The somewhat higher dissolution found in the oxalic acid leaching test versus the water leaching test might be offset by the tendency of the oxalic acid solutions to take on a gel-like consistency. The filtered solids left behind after three oxalic acid contacts were sticky and formed large clumps after drying. These two observations could indicate

  14. ANALYSIS OF SAMPLES FROM TANK 6F CHEMICAL CLEANING

    SciTech Connect

    Poirier, M.; Fink, S.

    2010-02-02

    Savannah River Remediation (SRR) is preparing Tank 6F for closure. The first step in preparing the tank for closure is mechanical sludge removal. In mechanical sludge removal, personnel add liquid (e.g., inhibited water or supernate salt solution) to the tank to form a slurry. They mix the liquid and sludge with pumps, and transfer the slurry to another tank for further processing. Mechanical sludge removal effectively removes the bulk of the sludge from a tank, but is not able to remove all of the sludge. In Tank 6F, SRR estimated a sludge heel of 5,984 gallons remained after mechanical sludge removal. To remove this sludge heel, SRR performed chemical cleaning. The chemical cleaning included two oxalic acid strikes, a spray wash, and a water wash. SRR conducted the first oxalic acid strike as follows. Personnel added 110,830 gallons of 8 wt % oxalic acid to Tank 6F and mixed the contents of Tank 6F with two submersible mixer pumps (SMPs) for approximately four days. Following the mixing, they transferred 115,903 gallons of Tank 6F material to Tank 7F. The SMPs were operating when the transfer started and were shut down approximately five hours after the transfer started. SRR collected a sample of the liquid from Tank 6F and submitted it to SRNL for analysis. Mapping of the tank following the transfer indicated that 2,400 gallons of solids remained in the tank. SRR conducted the second oxalic acid strike as follows. Personnel added 28,881 gallons of 8 wt % oxalic acid to Tank 6F. Following the acid addition, they visually inspected the tank and transferred 32,247 gallons of Tank 6F material to Tank 7F. SRR collected a sample of the liquid from Tank 6F and submitted it to SRNL for analysis. Mapping of the tank following the transfer indicated that 3,248 gallons of solids remained in the tank. Following the oxalic acid strikes, SRR performed Spray Washing with oxalic acid to remove waste collected on internal structures, cooling coils, tank top internals, and tank

  15. Tank 241-C-110 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank 241-C-110. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedure that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  16. Tank 241-C-109 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    This report presents the details of the Hanford waste tank characterization study for tank 241-C-109. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  17. Tank 241-SX-106 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank 241-SX-106. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedure that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  18. Tank 241-C-107 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank 241-C-107. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  19. Tank 241-C-102 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank 241-C-102. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  20. ANALYSIS OF SAMPLES FROM TANK 5F CHEMICAL CLEANING

    SciTech Connect

    Poirier, M.; Fink, S.

    2011-03-07

    The Savannah River Site (SRS) is preparing Tank 5F for closure. The first step in preparing the tank for closure is mechanical sludge removal. Following mechanical sludge removal, SRS performed chemical cleaning with oxalic acid to remove the sludge heel. Personnel are currently assessing the effectiveness of the chemical cleaning. SRS personnel collected liquid samples during chemical cleaning and submitted them to Savannah River National Laboratory (SRNL) for analysis. Following chemical cleaning, they collected a solid sample (also known as 'process sample') and submitted it to SRNL for analysis. The authors analyzed these samples to assess the effectiveness of the chemical cleaning process. The conclusions from this work are: (1) With the exception of iron, the dissolution of sludge components from Tank 5F agreed with results from the actual waste demonstration performed in 2007. The fraction of iron removed from Tank 5F by chemical cleaning was significantly less than the fraction removed in the SRNL demonstrations. The likely cause of this difference is the high pH following the first oxalic acid strike. (2) Most of the sludge mass remaining in the tank is iron and nickel. (3) The remaining sludge contains approximately 26 kg of barium, 37 kg of chromium, and 37 kg of mercury. (4) Most of the radioactivity remaining in the residual material is beta emitters and {sup 90}Sr. (5) The chemical cleaning removed more than {approx} 90% of the uranium isotopes and {sup 137}Cs. (6) The chemical cleaning removed {approx} 70% of the neptunium, {approx} 83% of the {sup 90}Sr, and {approx} 21% of the {sup 60}Co. (7) The chemical cleaning removed less than 10% of the plutonium, americium, and curium isotopes. (8) The chemical cleaning removed more than 90% of the aluminium, calcium, and sodium from the tank. (9) The cleaning operations removed 61% of lithium, 88% of non-radioactive strontium, and 65% of zirconium. The {sup 90}Sr and non-radioactive strontium were measured

  1. Laboratory Demonstration of the Pretreatment Process with Caustic and Oxidative Leaching Using Actual Hanford Tank Waste

    SciTech Connect

    Fiskum, Sandra K.; Billing, Justin M.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Snow, Lanee A.

    2009-01-01

    This report describes the bench-scale pretreatment processing of actual tank waste materials through the entire baseline WTP pretreatment flowsheet in an effort to demonstrate the efficacy of the defined leaching processes on actual Hanford tank waste sludge and the potential impacts on downstream pretreatment processing. The test material was a combination of reduction oxidation (REDOX) tank waste composited materials containing aluminum primarily in the form of boehmite and dissolved S saltcake containing Cr(III)-rich entrained solids. The pretreatment processing steps tested included • caustic leaching for Al removal • solids crossflow filtration through the cell unit filter (CUF) • stepwise solids washing using decreasing concentrations of sodium hydroxide with filtration through the CUF • oxidative leaching using sodium permanganate for removing Cr • solids filtration with the CUF • follow-on solids washing and filtration through the CUF • ion exchange processing for Cs removal • evaporation processing of waste stream recycle for volume reduction • combination of the evaporated product with dissolved saltcake. The effectiveness of each process step was evaluated by following the mass balance of key components (such as Al, B, Cd, Cr, Pu, Ni, Mn, and Fe), demonstrating component (Al, Cr, Cs) removal, demonstrating filterability by evaluating filter flux rates under various processing conditions (transmembrane pressure, crossflow velocities, wt% undissolved solids, and PSD) and filter fouling, and identifying potential issues for WTP. The filterability was reported separately (Shimskey et al. 2008) and is not repeated herein.

  2. CHARACTERIZATION OF TANK 11H AND TANK 51H POST ALUMINUM DISSOLUTION PROCESS SAMPLES

    SciTech Connect

    Hay, M; Daniel McCabe, D

    2008-05-16

    A dip sample of the liquid phase from Tank 11H and a 3-L slurry sample from Tank 51H were obtained and sent to Savannah River National Laboratory for characterization. These samples provide data to verify the amount of aluminum dissolved from the sludge as a result of the low temperature aluminum dissolution process conducted in Tank 51H. The characterization results for the as-received Tank 11H and Tank 51H supernate samples and the total dried solids of the Tank 51H sludge slurry sample appear quite good with respect to the precision of the sample replicates and minimal contamination present in the blank. The two supernate samples show similar concentrations for the major components as expected.

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

    SciTech Connect

    Adu-Wusu, K; Paul Burket, P

    2009-03-31

    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

  4. Tank 241-TY-103 rotary core sampling and analysis

    SciTech Connect

    Jo, J.

    1995-10-30

    This Sampling and Analysis Plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for two rotary-mode core samples from tank 241-TY-103

  5. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    SciTech Connect

    Peters, T. B.

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  6. PERFORMANCE TESTING OF THE NEXT-GENERATION CSSX SOLVENT WITH ACTUAL SRS TANK WASTE

    SciTech Connect

    Pierce, R.; Peters, T.; Crowder, M.; Fink, S.

    2011-11-01

    Efforts are underway to qualify the Next-Generation Solvent for the Caustic Side Solvent Extraction (CSSX) process. Researchers at multiple national laboratories have been involved in this effort. As part of the effort to qualify the solvent extraction system at the Savannah River Site (SRS), SRNL performed a number of tests at various scales. First, SRNL completed a series of batch equilibrium, or Extraction-Scrub-Strip (ESS), tests. These tests used {approx}30 mL of Next-Generation Solvent and either actual SRS tank waste, or waste simulant solutions. The results from these cesium mass transfer tests were used to predict solvent behavior under a number of conditions. At a larger scale, SRNL assembled 12 stages of 2-cm (diameter) centrifugal contactors. This rack of contactors is structurally similar to one tested in 2001 during the demonstration of the baseline CSSX process. Assembly and mechanical testing found no issues. SRNL performed a nonradiological test using 35 L of cesium-spiked caustic waste simulant and 39 L of actual tank waste. Test results are discussed; particularly those related to the effectiveness of extraction.

  7. Tank 241-BY-105 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    Tank BY-105 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-105 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-105 using the vapor sampling system (VSS) on July 7, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 26 C. Air from the Tank BY-105 headspace was withdrawn via a heated sampling probe mounted in riser 10A, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 65 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 46 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 10 trip blanks provided by the laboratories.

  8. Tank 241-BY-106 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    Tank BY-106 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-106 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-106 using the vapor sampling system (VSS) on July 8, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 27 C. Air from the Tank BY-106 headspace was withdrawn via a heated sampling probe mounted in riser 10B, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 65 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 46 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 10 trip blanks provided by the laboratories.

  9. Characterization, Leaching, and Filtration Testing for Tributyl Phosphate (TBP, Group 7) Actual Waste Sample Composites

    SciTech Connect

    Edwards, Matthew K.; Billing, Justin M.; Blanchard, David L.; Buck, Edgar C.; Casella, Amanda J.; Casella, Andrew M.; Crum, J. V.; Daniel, Richard C.; Draper, Kathryn E.; Fiskum, Sandra K.; Jagoda, Lynette K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Snow, Lanee A.; Swoboda, Robert G.

    2009-03-09

    .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. 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 waste-testing program included homogenizing the samples by group, characterizing the solids and aqueous phases, and performing parametric leaching tests. The tributyl phosphate sludge (TBP, Group 7) is the subject of this report. The Group 7 waste was anticipated to be high in phosphorus as well as aluminum in the form of gibbsite. Both are believed to exist in sufficient quantities in the Group 7 waste to address leaching behavior. Thus, the focus of the Group 7 testing was on the removal of both P and Al. 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.

  10. Analysis Of The Tank 5F Final Characterization Samples-2011

    SciTech Connect

    Oji, L. N.; Diprete, D.; Coleman, C. J.; Hay, M. S.

    2012-09-27

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  11. ANALYSIS OF THE TANK 5F FINAL CHARACTERIZATION SAMPLES-2011

    SciTech Connect

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.

    2012-08-03

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  12. ANALYSIS OF THE TANK 5F FINAL CHARATERIZATION SAMPLES-2011

    SciTech Connect

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.

    2012-01-20

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  13. Filtration and Leach Testing for REDOX Sludge and S-Saltcake Actual Waste Sample Composites

    SciTech Connect

    Shimskey, Rick W.; Billing, Justin M.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Geeting, John GH; Hallen, Richard T.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Snow, Lanee A.; Swoboda, Robert G.

    2009-02-20

    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.( ) The test 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. Under test plan TP-RPP-WTP-467, 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 filtration/leaching tests performed on two of the eight waste composite samples and follow-on parametric tests to support aluminum leaching results from those tests.

  14. Characterization of the Tank 19F Closure Grab and Core Samples and the Tank 18F Dip Sample

    SciTech Connect

    Swingle, R.F.

    2002-05-02

    The results of analyses of the Tank 19F closure characterization samples are included herein. The samples analyzed include the two Tank 19F grab samples (FTF-075 and FTF-077) and a Tank 18F dip sample (FTF-076) taken in September 2001 and a Tank 19F core sample (FTF-118) taken in December 2001. The FTF-075 and FTF-077 grab samples were pulled from Tank 19F and the FTF-076 dip sample was pulled from Tank 18F in September 2001 as part of the characterization process for closure of Tank 19F. The samples were delivered to the Savannah River Technology Center (SRTC) Shielded Cells on September 28, 2001 and placed in the Shielded Cells on October 2, 2001. The samples were opened and both grab samples were found to contain plenty of material to allow completion of the analyses. The samples were dark and resembled marsh muck (see Figures 1 and 2). The dip sample was also found to contain plenty of material. The sample looked like muddy water (Figure 4). The FTF-118F core sample was pulled from Tank 19F in December 2001 as part of the characterization process for closure of the tank. The sample was delivered to the SRTC Shielded Cells on December 6, 2001 and placed in the Shielded Cells on December 7, 2001. The sample was opened and found to contain plenty of material to allow completion of the analyses. As evident in Figure 3, the sample resembled a somewhat drier version of the previous grab samples FTF-075 and FTF-077. A group consisting of SRTC Waste Processing Technology (WPT) section personnel and High Level Waste Engineering (HLWE) personnel viewed the sample when it was opened and came to the consensus that the sample appeared to be homogeneous. The decision was made to treat the sample as a single phase and analyze accordingly. Initially, small portions were archived from the top, middle and bottom of the sample in case it is later decided to analyze the levels of the sample separately. The analytical results from the two grab samples and the core sample were all

  15. ARTIFACT FORMATION DURING NEUTRALIZATION OF TANK 50 SAMPLES

    SciTech Connect

    Crump, S.; Young, J.

    2014-08-01

    Degradation products have been identified in the extracts of Tank 50 samples analyzed by semivolatile organic compound analysis (SVOA) using gas chromatography/mass spectrometry (GC/MS). These materials, identified as short chain alkyl alcohols, were formed by acidification during sample preparation. A number of questions were raised about the formation of these and other materials reported in Tank 50 surface samples, and this report serves to address these questions.

  16. CHARACTERIZATION OF TANK 18F WALL AND SCALE SAMPLES

    SciTech Connect

    Hay, Michael; Click, Damon; Diprete, c.; Diprete, David

    2010-03-01

    Samples from the wall of Tank 18F were obtained to determine the associated source term using a special wall sampling device. Two wall samples and a scale sample were obtained and characterized at the Savannah River National Laboratory (SRNL). All the analyses of the Tank 18F wall and scale samples met the targeted detection limits. The upper wall samples show {approx}2X to 6X higher concentrations for U, Pu, and Np on an activity per surface area basis than the lower wall samples. On an activity per mass basis, the upper and lower wall samples show similar compositions for U and Pu. The Np activity is still {approx}2.5X higher in the upper wall sample on a per mass basis. The scale sample contains 2-3X higher concentrations of U, Pu, and Sr-90 than the wall samples on an activity per mass basis. The plutonium isotopics differ for all three wall samples (upper, lower, and scale samples). The Pu-238 appears to increase as a proportion of total plutonium as you move up the tank wall from the lowest sample (scale sample) to the upper wall sample. The elemental composition of the scale sample appears similar to other F-Area PUREX sludge compositions. The composition of the scale sample is markedly different than the material on the floor of Tank 18F. However, the scale sample shows elevated Mg and Ca concentrations relative to typical PUREX sludge as do the floor samples.

  17. ANALYSIS OF THE TANK 6F FINAL CHARACTERIZATION SAMPLES-2012

    SciTech Connect

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.; Shine, G.

    2012-06-28

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm-243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  18. Analysis of the Tank 6F Final Characterization Samples-2012

    SciTech Connect

    Oji, L. N.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.; Shine, E. P.

    2013-01-31

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm- 243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  19. Analysis Of The Tank 6F Final Characterization Samples-2012

    SciTech Connect

    Oji, L. N.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.; Shine, E. P.

    2012-09-27

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm-243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  20. Hot cell remote nuclear scanning of tank core samples

    SciTech Connect

    Beck, M.A.; Blewett, G.R.; Troyer, G.L.; Keele, B.D.; Addleman, R.S.

    1995-11-01

    A Westinghouse Hanford Company (WHC)-designed remote measurement system has been constructed for gamma and beta isotopic characterization of Hanford Site high-level waste tank core sample materials in a hot cell. A small, collimated, planar CdZnTe detector is used for gamma-ray spectroscopy. Spectral resolution of 2% full-width-at-maximum at 662 kiloelectronvolts (keV) has been obtained remotely using risetime compensation and limited pulse shape discrimination (PSD). Isotopic measurement of high-energy beta emitters was accomplished with a ruggedly made, deeply depleted, surface barrier silicon detector. The primary function of the remote nuclear screening system is to provide a fast, qualitative stratigraphic assessment (with isotopic information) of high-level radioactive material. Both gamma spectroscopy and beta measurements have been performed on actual core segments. Differences in radionuclide content, which correspond with color or texture variations, have been seen in constant cross section core samples, although for many samples the activity variation can be ascribed to geometry and/or mass factors. Discussion of the design, implementation, results and potential benefits will be presented.

  1. Double Shell Tank (DST) Process Waste Sampling Subsystem Specification

    SciTech Connect

    RASMUSSEN, J.H.

    2000-05-03

    This specification establishes the performance requirements and provides references to the requisite codes and standards to be applied to the Double-Shell Tank (DST) Process Waste Sampling Subsystem which supports the first phase of Waste Feed Delivery.

  2. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect

    Peters, T. B.; Fink, S. D.

    2012-12-11

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  3. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect

    Peters, T. B.; Fink, S. D.

    2012-12-20

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  4. STATISTICAL ANALYSIS OF TANK 18F FLOOR SAMPLE RESULTS

    SciTech Connect

    Harris, S.

    2010-09-02

    Representative sampling has been completed for characterization of the residual material on the floor of Tank 18F as per the statistical sampling plan developed by Shine [1]. Samples from eight locations have been obtained from the tank floor and two of the samples were archived as a contingency. Six samples, referred to in this report as the current scrape samples, have been submitted to and analyzed by SRNL [2]. This report contains the statistical analysis of the floor sample analytical results to determine if further data are needed to reduce uncertainty. Included are comparisons with the prior Mantis samples results [3] to determine if they can be pooled with the current scrape samples to estimate the upper 95% confidence limits (UCL{sub 95%}) for concentration. Statistical analysis revealed that the Mantis and current scrape sample results are not compatible. Therefore, the Mantis sample results were not used to support the quantification of analytes in the residual material. Significant spatial variability among the current sample results was not found. Constituent concentrations were similar between the North and South hemispheres as well as between the inner and outer regions of the tank floor. The current scrape sample results from all six samples fall within their 3-sigma limits. In view of the results from numerous statistical tests, the data were pooled from all six current scrape samples. As such, an adequate sample size was provided for quantification of the residual material on the floor of Tank 18F. The uncertainty is quantified in this report by an upper 95% confidence limit (UCL{sub 95%}) on each analyte concentration. The uncertainty in analyte concentration was calculated as a function of the number of samples, the average, and the standard deviation of the analytical results. The UCL{sub 95%} was based entirely on the six current scrape sample results (each averaged across three analytical determinations).

  5. STATISTICAL ANALYSIS OF TANK 19F FLOOR SAMPLE RESULTS

    SciTech Connect

    Harris, S.

    2010-09-02

    Representative sampling has been completed for characterization of the residual material on the floor of Tank 19F as per the statistical sampling plan developed by Harris and Shine. Samples from eight locations have been obtained from the tank floor and two of the samples were archived as a contingency. Six samples, referred to in this report as the current scrape samples, have been submitted to and analyzed by SRNL. This report contains the statistical analysis of the floor sample analytical results to determine if further data are needed to reduce uncertainty. Included are comparisons with the prior Mantis samples results to determine if they can be pooled with the current scrape samples to estimate the upper 95% confidence limits (UCL95%) for concentration. Statistical analysis revealed that the Mantis and current scrape sample results are not compatible. Therefore, the Mantis sample results were not used to support the quantification of analytes in the residual material. Significant spatial variability among the current scrape sample results was not found. Constituent concentrations were similar between the North and South hemispheres as well as between the inner and outer regions of the tank floor. The current scrape sample results from all six samples fall within their 3-sigma limits. In view of the results from numerous statistical tests, the data were pooled from all six current scrape samples. As such, an adequate sample size was provided for quantification of the residual material on the floor of Tank 19F. The uncertainty is quantified in this report by an UCL95% on each analyte concentration. The uncertainty in analyte concentration was calculated as a function of the number of samples, the average, and the standard deviation of the analytical results. The UCL95% was based entirely on the six current scrape sample results (each averaged across three analytical determinations).

  6. Modeling water retention of sludge simulants and actual saltcake tank wastes

    SciTech Connect

    Simmons, C.S.

    1996-07-01

    The Ferrocyanide Tanks Safety Program managed by Westinghouse hanford Company has been concerned with the potential combustion hazard of dry tank wastes containing ferrocyanide chemical in combination with nitrate salts. Pervious studies have shown that tank waste containing greater than 20 percent of weight as water could not be accidentally ignited. Moreover, a sustained combustion could not be propagated in such a wet waste even if it contained enough ferrocyanide to burn. Because moisture content is a key critical factor determining the safety of ferrocyanide-containing tank wastes, physical modeling was performed by Pacific Northwest National laboratory to evaluate the moisture-retaining behavior of typical tank wastes. The physical modeling reported here has quantified the mechanisms by which two main types of tank waste, sludge and saltcake, retain moisture in a tank profile under static conditions. Static conditions usually prevail after a tank profile has been stabilized by pumping out any excess interstitial liquid, which is not naturally retained by the waste as a result of physical forces such as capillarity.

  7. Tank 241-Z-361 vapor sampling and analysis plan

    SciTech Connect

    BANNING, D.L.

    1999-02-23

    Tank 241-Z-361 is identified in the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement), Appendix C, (Ecology et al. 1994) as a unit to be remediated under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). As such, the U.S. Environmental Protection Agency will serve as the lead regulatory agency for remediation of this tank under the CERCLA process. At the time this unit was identified as a CERCLA site under the Tri-Party Agreement, it was placed within the 200-ZP-2 Operable Unit. In 1997, The Tri-parties redefined 200 Area Operable Units into waste groupings (Waste Site Grouping for 200 Areas Soils Investigations [DOE-RL 1992 and 1997]). A waste group contains waste sites that share similarities in geological conditions, function, and types of waste received. Tank 241-Z-361 is identified within the CERCLA Plutonium/Organic-rich Process Condensate/Process Waste Group (DOE-RL 1992). The Plutonium/Organic-rich Process Condensate/Process Waste Group has been prioritized for remediation beginning in the year 2004. Results of Tank 216-Z-361 sampling and analysis described in this Sampling and Analysis Plan (SAP) and in the SAP for sludge sampling (to be developed) will determine whether expedited response actions are required before 2004 because of the hazards associated with tank contents. Should data conclude that remediation of this tank should occur earlier than is planned for the other sites in the waste group, it is likely that removal alternatives will be analyzed in a separate Engineering Evaluation/Cost Analysis (EE/CA). Removal actions would proceed after the U.S. Environmental Protection Agency (EPA) signs an Action Memorandum describing the selected removal alternative for Tank 216-Z-361. If the data conclude that there is no immediate threat to human health and the environment from this tank, remedial actions for the tank will be defined in a

  8. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect

    Peters, T.; Fink, S.

    2012-03-26

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

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

    SciTech Connect

    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.

    2009-03-02

    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

  10. Modeling of Boehmite Leaching from Actual Hanford High-Level Waste Samples

    SciTech Connect

    Snow, L.A.; Rapko, B.M.; Poloski, A.P.; Peterson, R.A.

    2007-07-01

    The U.S. Department of Energy plans to vitrify approximately 60,000 metric tons of high-level waste (HLW) sludge from underground storage tanks at the Hanford Site in Southwest Washington State. To reduce the volume of HLW requiring treatment, a goal has been set to remove a significant quantity of the aluminum, which comprises nearly 70 percent of the sludge. Aluminum is found in the form of gibbsite and sodium aluminate, which can be easily dissolved by washing the waste stream with caustic, and boehmite, which comprises nearly half of the total aluminum, but is more resistant to caustic dissolution and requires higher treatment temperatures and hydroxide concentrations. Chromium, which makes up a much smaller amount ({approx}3%) of the sludge, must also be removed because there is a low tolerance for chromium in the HLW immobilization process. In this work, the coupled dissolution kinetics of aluminum and chromium species during caustic leaching of actual Hanford HLW samples is examined. The experimental results are used to develop a model that provides a basis for predicting dissolution dynamics from known process temperature and hydroxide concentration. (authors)

  11. Modeling of Boehmite Leaching from Actual Hanford High-Level Waste Samples

    SciTech Connect

    Peterson, Reid A.; Lumetta, Gregg J.; Rapko, Brian M.; Poloski, Adam P.

    2007-06-27

    The Department of Energy plans to vitrify approximately 60,000 metric tons of high level waste sludge from underground storage tanks at the Hanford Nuclear Reservation. To reduce the volume of high level waste requiring treatment, a goal has been set to remove about 90 percent of the aluminum, which comprises nearly 70 percent of the sludge. Aluminum in the form of gibbsite and sodium aluminate can be easily dissolved by washing the waste stream with caustic, but boehmite, which comprises nearly half of the total aluminum, is more resistant to caustic dissolution and requires higher treatment temperatures and hydroxide concentrations. In this work, the dissolution kinetics of aluminum species during caustic leaching of actual Hanford high level waste samples is examined. The experimental results are used to develop a shrinking core model that provides a basis for prediction of dissolution dynamics from known process temperature and hydroxide concentration. This model is further developed to include the effects of particle size polydispersity, which is found to strongly influence the rate of dissolution.

  12. Total cyanide analysis of tank core samples: Analytical results and supporting investigations. Revision 1

    SciTech Connect

    Pool, K.H.

    1994-03-01

    The potential for a ferrocyanide explosion in Hanford site single-shelled waste storage tanks (SSTS) poses a serious safety concern. This potential danger developed in the 1950s when {sup 137}Cs was scavenged during the reprocessing of uranium recovery process waste by co-precipitating it along with sodium in nickel ferrocyanide salt. Sodium or potassium ferrocyanide and nickel sulfate were added to the liquid waste stored in SSTs. The tank storage space resulting from the scavenging process was subsequently used to store other waste types. Ferrocyanide salts in combinations with oxidizing agents, such as nitrate and nitrite, are known to explode when key parameters (temperature, water content, oxidant concentration, and fuel [cyanide]) are in place. Therefore, reliable total cyanide analysis data for actual SST materials are required to address the safety issue. Accepted cyanide analysis procedures do not yield reliable results for samples containing nickel ferrocyanide materials because the compounds are insoluble in acidic media. Analytical chemists at Pacific Northwest Laboratory (PNL) have developed a modified microdistillation procedure (see below) for analyzing total cyanide in waste tank matrices containing nickel ferrocyanide materials. Pacific Northwest Laboratory analyzed samples from Hanford Waste Tank 241-C-112 cores 34, 35, and 36 for total cyanide content using technical procedure PNL-ALO-285 {open_quotes}Total Cyanide by Remote Microdistillation and Agrentometric Titration,{close_quotes} Rev. 0. This report summarizes the results of these analyses along with supporting quality control data, and, in addition, summarizes the results of the test to check the efficacy of sodium nickel ferrocyanide solubilization from an actual core sample by aqueous EDTA/en to verify that nickel ferrocyanide compounds were quantitatively solubilized before actual distillation.

  13. ANALYSIS OF THE SALT FEED TANK CORE SAMPLE

    SciTech Connect

    Reigel, M.; Cheng, W.

    2012-01-26

    The Saltstone Production Facility (SPF) immobilizes and disposes of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site (SRS). Low-level waste (LLW) streams from processes at SRS are stored in Tank 50 until the LLW can be transferred to the SPF for treatment and disposal. The Salt Feed Tank (SFT) at the Saltstone Production Facility (SPF) holds approximately 6500 gallons of low level waste from Tank 50 as well as drain water returned from the Saltstone Disposal Facility (SDF) vaults. Over the past several years, Saltstone Engineering has noted the accumulation of solids in the SFT. The solids are causing issues with pump performance, agitator performance, density/level monitoring, as well as taking up volume in the tank. The tank has been sounded at the same location multiple times to determine the level of the solids. The readings have been 12, 25 and 15 inches. The SFT is 8.5 feet high and 12 feet in diameter, therefore the solids account for approximately 10 % of the tank volume. Saltstone Engineering has unsuccessfully attempted to obtain scrape samples of the solids for analysis. As a result, Savannah River National Laboratory (SRNL) was tasked with developing a soft core sampler to obtain a sample of the solids and to analyze the core sample to aid in determining a path forward for removing the solids from the SFT. The source of the material in the SFT is the drain water return system where excess liquid from the Saltstone disposal vaults is pumped back to the SFT for reprocessing. It has been shown that fresh grout from the vault enter the drain water system piping. Once these grout solids return to the SFT, they settle in the tank, set up, and can't be reprocessed, causing buildup in the tank over time. The composition of the material indicates that it is potentially toxic for chromium and mercury and the primary radionuclide is cesium-137. Qualitative measurements

  14. A BASIS FOR MODIFYING THE TANK 12 COMPOSITE SAMPLING DESIGN

    SciTech Connect

    Shine, G.

    2014-11-25

    The SRR sampling campaign to obtain residual solids material from the Savannah River Site (SRS) Tank Farm Tank 12 primary vessel resulted in obtaining appreciable material in all 6 planned source samples from the mound strata but only in 5 of the 6 planned source samples from the floor stratum. Consequently, the design of the compositing scheme presented in the Tank 12 Sampling and Analysis Plan, Pavletich (2014a), must be revised. Analytical Development of SRNL statistically evaluated the sampling uncertainty associated with using various compositing arrays and splitting one or more samples for compositing. The variance of the simple mean of composite sample concentrations is a reasonable standard to investigate the impact of the following sampling options. Composite Sample Design Option (a). Assign only 1 source sample from the floor stratum and 1 source sample from each of the mound strata to each of the composite samples. Each source sample contributes material to only 1 composite sample. Two source samples from the floor stratum would not be used. Composite Sample Design Option (b). Assign 2 source samples from the floor stratum and 1 source sample from each of the mound strata to each composite sample. This infers that one source sample from the floor must be used twice, with 2 composite samples sharing material from this particular source sample. All five source samples from the floor would be used. Composite Sample Design Option (c). Assign 3 source samples from the floor stratum and 1 source sample from each of the mound strata to each composite sample. This infers that several of the source samples from the floor stratum must be assigned to more than one composite sample. All 5 source samples from the floor would be used. Using fewer than 12 source samples will increase the sampling variability over that of the Basic Composite Sample Design, Pavletich (2013). Considering the impact to the variance of the simple mean of the composite sample concentrations

  15. Statistical Analysis Of Tank 5 Floor Sample Results

    SciTech Connect

    Shine, E. P.

    2012-08-01

    Sampling has been completed for the characterization of the residual material on the floor of Tank 5 in the F-Area Tank Farm at the Savannah River Site (SRS), near Aiken, SC. The sampling was performed by Savannah River Remediation (SRR) LLC using a stratified random sampling plan with volume-proportional compositing. The plan consisted of partitioning the residual material on the floor of Tank 5 into three non-overlapping strata: two strata enclosed accumulations, and a third stratum consisted of a thin layer of material outside the regions of the two accumulations. Each of three composite samples was constructed from five primary sample locations of residual material on the floor of Tank 5. Three of the primary samples were obtained from the stratum containing the thin layer of material, and one primary sample was obtained from each of the two strata containing an accumulation. This report documents the statistical analyses of the analytical results for the composite samples. The objective of the analysis is to determine the mean concentrations and upper 95% confidence (UCL95) bounds for the mean concentrations for a set of analytes in the tank residuals. The statistical procedures employed in the analyses were consistent with the Environmental Protection Agency (EPA) technical guidance by Singh and others [2010]. Savannah River National Laboratory (SRNL) measured the sample bulk density, nonvolatile beta, gross alpha, and the radionuclide, elemental, and chemical concentrations three times for each of the composite samples. The analyte concentration data were partitioned into three separate groups for further analysis: analytes with every measurement above their minimum detectable concentrations (MDCs), analytes with no measurements above their MDCs, and analytes with a mixture of some measurement results above and below their MDCs. The means, standard deviations, and UCL95s were computed for the analytes in the two groups that had at least some measurements

  16. STATISTICAL ANALYSIS OF TANK 5 FLOOR SAMPLE RESULTS

    SciTech Connect

    Shine, E.

    2012-03-14

    Sampling has been completed for the characterization of the residual material on the floor of Tank 5 in the F-Area Tank Farm at the Savannah River Site (SRS), near Aiken, SC. The sampling was performed by Savannah River Remediation (SRR) LLC using a stratified random sampling plan with volume-proportional compositing. The plan consisted of partitioning the residual material on the floor of Tank 5 into three non-overlapping strata: two strata enclosed accumulations, and a third stratum consisted of a thin layer of material outside the regions of the two accumulations. Each of three composite samples was constructed from five primary sample locations of residual material on the floor of Tank 5. Three of the primary samples were obtained from the stratum containing the thin layer of material, and one primary sample was obtained from each of the two strata containing an accumulation. This report documents the statistical analyses of the analytical results for the composite samples. The objective of the analysis is to determine the mean concentrations and upper 95% confidence (UCL95) bounds for the mean concentrations for a set of analytes in the tank residuals. The statistical procedures employed in the analyses were consistent with the Environmental Protection Agency (EPA) technical guidance by Singh and others [2010]. Savannah River National Laboratory (SRNL) measured the sample bulk density, nonvolatile beta, gross alpha, radionuclide, inorganic, and anion concentrations three times for each of the composite samples. The analyte concentration data were partitioned into three separate groups for further analysis: analytes with every measurement above their minimum detectable concentrations (MDCs), analytes with no measurements above their MDCs, and analytes with a mixture of some measurement results above and below their MDCs. The means, standard deviations, and UCL95s were computed for the analytes in the two groups that had at least some measurements above their

  17. Statistical Analysis of Tank 5 Floor Sample Results

    SciTech Connect

    Shine, E. P.

    2013-01-31

    Sampling has been completed for the characterization of the residual material on the floor of Tank 5 in the F-Area Tank Farm at the Savannah River Site (SRS), near Aiken, SC. The sampling was performed by Savannah River Remediation (SRR) LLC using a stratified random sampling plan with volume-proportional compositing. The plan consisted of partitioning the residual material on the floor of Tank 5 into three non-overlapping strata: two strata enclosed accumulations, and a third stratum consisted of a thin layer of material outside the regions of the two accumulations. Each of three composite samples was constructed from five primary sample locations of residual material on the floor of Tank 5. Three of the primary samples were obtained from the stratum containing the thin layer of material, and one primary sample was obtained from each of the two strata containing an accumulation. This report documents the statistical analyses of the analytical results for the composite samples. The objective of the analysis is to determine the mean concentrations and upper 95% confidence (UCL95) bounds for the mean concentrations for a set of analytes in the tank residuals. The statistical procedures employed in the analyses were consistent with the Environmental Protection Agency (EPA) technical guidance by Singh and others [2010]. Savannah River National Laboratory (SRNL) measured the sample bulk density, nonvolatile beta, gross alpha, and the radionuclide1, elemental, and chemical concentrations three times for each of the composite samples. The analyte concentration data were partitioned into three separate groups for further analysis: analytes with every measurement above their minimum detectable concentrations (MDCs), analytes with no measurements above their MDCs, and analytes with a mixture of some measurement results above and below their MDCs. The means, standard deviations, and UCL95s were computed for the analytes in the two groups that had at least some measurements

  18. Vapor space sampling of ferrocyanide tanks, Hanford Site, Richland, Washington

    SciTech Connect

    Not Available

    1991-07-01

    Environmental assessment (EA), to assess environmental impacts associated with tank vapor space (dome) gas sampling of 24 Hanford Site single-shell waste tanks that contain ferrocyanide-nitrate compounds to determine whether or not the tanks contain flammable or toxic gases. The proposed action would be conducted using non-sparking materials, sparkless tools, and a portable containment shelter (greenhouse) and plastic ground cover. DOE needs to take this action to help define the required controls to prevent or mitigate the potential for an accident during future, more intrusive sampling of these tanks. Based on the evaluation in the EA (which examined the environmental impacts of the proposed action and reasonable alternatives), DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an Environmental Impact Statement is not required, and the Department is issuing this Finding of No Significant Impact (FONSI).

  19. Rheology and TIC/TOC results of ORNL tank samples

    SciTech Connect

    Pareizs, J. M.; Hansen, E. K.

    2013-04-26

    The Savannah River National Laboratory (SRNL)) was requested by Oak Ridge National Laboratory (ORNL) to perform total inorganic carbon (TIC), total organic carbon (TOC), and rheological measurements for several Oak Ridge tank samples. As received slurry samples were diluted and submitted to SRNL-Analytical for TIC and TOC analyses. Settled solids yield stress (also known as settled shear strength) of the as received settled sludge samples were determined using the vane method and these measurements were obtained 24 hours after the samples were allowed to settled undisturbed. Rheological or flow properties (Bingham Plastic viscosity and Bingham Plastic yield stress) were determined from flow curves of the homogenized or well mixed samples. Other targeted total suspended solids (TSS) concentrations samples were also analyzed for flow properties and these samples were obtained by diluting the as-received sample with de-ionized (DI) water.

  20. Actual-Waste Tests of Enhanced Chemical Cleaning for Retrieval of SRS HLW Sludge Tank Heels and Decomposition of Oxalic Acid - 12256

    SciTech Connect

    Martino, Christopher J.; King, William D.; Ketusky, Edward T.

    2012-07-01

    Savannah River National Laboratory conducted a series of tests on the Enhanced Chemical Cleaning (ECC) process using actual Savannah River Site waste material from Tanks 5F and 12H. Testing involved sludge dissolution with 2 wt% oxalic acid, the decomposition of the oxalates by ozonolysis (with and without the aid of ultraviolet light), the evaporation of water from the product, and tracking the concentrations of key components throughout the process. During ECC actual waste testing, the process was successful in decomposing oxalate to below the target levels without causing substantial physical or chemical changes in the product sludge. During ECC actual waste testing, the introduction of ozone was successful in decomposing oxalate to below the target levels. This testing did not identify physical or chemical changes in the ECC product sludge that would impact downstream processing. The results from these tests confirm observations made by AREVA NP during larger scale testing with waste simulants. This testing, however, had a decreased utilization of ozone, requiring approximately 5 moles of ozone per mole of oxalate decomposed. Decomposition of oxalates in sludge dissolved in 2 wt% OA to levels near 100 ppm oxalate using ECC process conditions required 8 to 12.5 hours without the aid of UV light and 4.5 to 8 hours with the aid of UV light. The pH and ORP were tracked during decomposition testing. Sludge components were tracked during OA decomposition, showing that most components have the highest soluble levels in the initial dissolved sludge and early decomposition samples and exhibit lower soluble levels as OA decomposition progresses. The Deposition Tank storage conditions that included pH adjustment to approximately 1 M free hydroxide tended to bring the soluble concentrations in the ECC product to nearly the same level for each test regardless of storage time, storage temperature, and contact with other tank sludge material. (authors)

  1. Sample Results From Tank 48H Samples HTF-48-14-158, -159, -169, and -170

    SciTech Connect

    Peters, T.; Hang, T.

    2015-04-28

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 48H in support of determining the cause for the unusually high dose rates at the sampling points for this tank. A set of two samples was taken from the quiescent tank, and two additional samples were taken after the contents of the tank were mixed. The results of the analyses of all the samples show that the contents of the tank have changed very little since the analysis of the previous sample in 2012. The solids are almost exclusively composed of tetraphenylborate (TPB) salts, and there is no indication of acceleration in the TPB decomposition. The filtrate composition shows a moderate increase in salt concentration and density, which is attributable to the addition of NaOH for the purposes of corrosion control. An older modeling simulation of the TPB degradation was updated, and the supernate results from a 2012 sample were run in the model. This result was compared to the results from the 2014 recent sample results reported in this document. The model indicates there is no change in the TPB degradation from 2012 to 2014. SRNL measured the buoyancy of the TPB solids in Tank 48H simulant solutions. It was determined that a solution of density 1.279 g/mL (~6.5M sodium) was capable of indefinitely suspending the TPB solids evenly throughout the solution. A solution of density 1.296 g/mL (~7M sodium) caused a significant fraction of the solids to float on the solution surface. As the experiments could not include the effect of additional buoyancy elements such as benzene or hydrogen generation, the buoyancy measurements provide an upper bound estimate of the density in Tank 48H required to float the solids.

  2. Tank 241-TX-113 rotary mode core sampling and analysis plan

    SciTech Connect

    McCain, D.J.

    1998-08-04

    This sampling and analysis plan (SAP) identities characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for push mode core samples from tank 241-TX-113 (TX-113). The Tank Characterization Technical Sampling Basis document identities Retrieval, Pretreatment and Immobilization as an issue that applies to tank TX-113. As a result, a 150 gram composite of solids shall be made and archived for that program. This tank is not on a Watch List.

  3. Ion exchange removal of cesium from simulated and actual supernate from Hanford tanks 241-SY-101 and 241-SY-103

    SciTech Connect

    Brown, G.N.; Bontha, J.R.; Carlson, C.D.

    1995-09-01

    Pacific Northwest Laboratory (PNL), in conjunction with the Process Chemistry and Statistics Section of Westinghouse Hanford Company (WHC), conducted this study as part of the Supernatant Treatment Development Task for the Initial Pretreatment Module (IPM) Applied Engineering Project. The study assesses the performance of the CS-100 ion exchange material for removing cesium from simulated and actual alkaline supernate from Hanford tanks 241-SY-101 and 241-SY-103. The objective of these experiments is to compare the cesium ion exchange loading and elution profiles of actual and simulated wastes. Specific experimental objectives include (1) demonstration of decontamination factors (DF) for cesium removal, 92) verification of simulant performance, (3) investigation of waste/exchanger chemistry, and (4) determination of the radionuclide content of the regenerated CS-100 resin prior to disposal.

  4. Characterization and decant of Tank 42H sludge sample ESP-200

    SciTech Connect

    Hay, M.S.

    2000-04-25

    DWPF Engineering requested that the Savannah River Technology Center (SRTC) provide a demonstration of the DWPF flowsheet on sludge from Tank 42H in the Shielded Cell facility. A 5 liter sample of the Tank 42H sludge (ESP-200), obtained with the tank contents fully mixed, arrived at SRTC on January 20, 1998. This report details receipt of the 5 liter sample at SRTC, the decant of the sample, and the characterization of the pre- and post-decant Tank 42H sludge. Evaluation of the measured composition of the supernate indicates Sample ESP-200 became diluted approximately 20 percent by volume prior to receipt. This dilution complicates the relationship of the characterization of Post-Decant ESP-200 to the current contents of Tank 42H. For the purposes of modeling the current tank contents of Tank 42H, this report provides an estimated composition based on analytical data of recent samples from Tank 42H.

  5. Statistical Methods and Tools for Hanford Staged Feed Tank Sampling

    SciTech Connect

    Fountain, Matthew S.; Brigantic, Robert T.; Peterson, Reid A.

    2013-10-01

    This report summarizes work conducted by Pacific Northwest National Laboratory to technically evaluate the current approach to staged feed sampling of high-level waste (HLW) sludge to meet waste acceptance criteria (WAC) for transfer from tank farms to the Hanford Waste Treatment and Immobilization Plant (WTP). The current sampling and analysis approach is detailed in the document titled Initial Data Quality Objectives for WTP Feed Acceptance Criteria, 24590-WTP-RPT-MGT-11-014, Revision 0 (Arakali et al. 2011). The goal of this current work is to evaluate and provide recommendations to support a defensible, technical and statistical basis for the staged feed sampling approach that meets WAC data quality objectives (DQOs).

  6. HYDRAULIC CONDUCTIVITY OF SALTSTONE FORMULATED USING 1Q11, 2Q11 AND 3Q11 TANK 50 SLURRY SAMPLES

    SciTech Connect

    Reigel, M.; Nichols, R.

    2012-06-27

    As part of the Saltstone formulation work requested by Waste Solidification Engineering (WSE), Savannah River National Laboratory (SRNL) was tasked with preparing Saltstone samples for fresh property analysis and hydraulic conductivity measurements using actual Tank 50 salt solution rather than simulated salt solution. Samples of low level waste salt solution collected from Tank 50H during the first, second, and third quarters of 2011 were used to formulate the Saltstone samples. The salt solution was mixed with premix (45 wt % slag, 45 wt % fly ash, and 10 wt % cement), in a ratio consistent with facility operating conditions during the quarter of interest. The fresh properties (gel, set, bleed) of each mix were evaluated and compared to the recommended acceptance criteria for the Saltstone Production Facility. ASTM D5084-03, Method C was used to measure the hydraulic conductivity of the Saltstone samples. The hydraulic conductivity of Saltstone samples prepared from 1Q11 and 2Q11 samples of Tank 50H is 4.2E-9 cm/sec and 2.6E-9 cm/sec, respectively. Two additional 2Q11 and one 3Q11 sample were not successfully tested due to the inability to achieve stable readings during saturation and testing. The hydraulic conductivity of the samples made from Tank 50H salt solution compare well to samples prepared with simulated salt solution and cured under similar conditions (1.4E-9 - 4.9E-8 cm/sec).

  7. REPORT ON ELECTROCHEMICAL CORROSION TESTING FOR TANK 241-AN-106 USING 2009 SAMPLING CAMPAIGN GRAB SAMPLES

    SciTech Connect

    WYRWAS RB

    2010-05-11

    Based on an ENRAF waste surface measurement taken February 1, 2009, double-shell tank (DST) 24l-AN-l06 (AN-106) contained approximately 278.98 inches (793 kgal) of waste. A zip cord measurement from the tank on February 1, 2009, indicated a settled solids layer of 9l.7 inches in height (280 kgal). The supernatant layer in February 2009, by difference, was approximately 187 inches deep (514 kgal). Laboratory results from AN-l06 February 1, 2009 (see Table 2) grab samples indicated the supernatant was below the chemistry limit that applied at the time as identified in HNF-SD-WM-TSR-006, 'Tank Farms Technical Safety Requirements', Administrative Control (AC) 5.16, 'Corrosion Mitigation Controls.' The limits have since been removed from the Technical Safety Requirements (TSR) and are captured in OSD-T-15l-00007, 'Operating Specifications for the Double-Shell Storage Tanks.' Problem evaluation request WRPS-PER-2009-0218 was submitted February 9,2009, to document the finding that the supernatant chemistry for grab samples taken from the middle and upper regions of the supernatant was noncompliant with the chemistry control limits. The lab results for the samples taken from the bottom region of the supernatant met AC 5.16 limits.

  8. Tank 241-SY-101 push mode core sampling and analysis plan

    SciTech Connect

    CONNER, J.M.

    1998-10-09

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for push mode core samples from tank 241-SY-101 (SY-101). It is written in accordance with Data Quality Objective to Support Resolution of the Flammable Gas Safety Issue (Bauer 1998), Low Activity Waste Feed Data Quality Objectives (Wiemers and Miller 1997 and DOE 1998), Data Quality Objectives for TWRS Privatization Phase I: Confirm Tank T is an Appropriate Feed Source for Low-Activity Waste Feed Batch X (Certa 1998), and the Tank Safety Screening Data Quality Objective (Dukelow et al. 1995). The Tank Characterization Technical Sampling Basis document (Brown et al. 1998) indicates that these issues apply to tank SY-101 for this sampling event. Brown et al. also identifies high-level waste, regulatory, pretreatment and disposal issues as applicable issues for this tank. However, these issues will not be addressed via this sampling event.

  9. Sampling and Analysis Plan for Catch Tank 241ER311 Vapor

    SciTech Connect

    NGUYEN, D.M.

    1999-11-15

    This tank sampling and analysis plan (TSAF') identifies the sample collection, laboratory analysis, quality assurance/quality control (QA/QC) objectives for the characterization of catch tank 241-ER-311 vapor space. Data to be collected under this revision (Revision 2) of the TSAP will be used to evaluate the effectiveness of the portable exhauster recently installed for the tank. Vapor samples taken previous to the issuance of this revision shall be analyzed in accordance with Revision 1.

  10. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 4 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect

    Peters, T.; Fink, S.

    2011-06-22

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H to qualify them for use in the Integrated Salt Disposition Program (ISDP) Batch 4 processing. All sample results agree with expectations based on prior analyses where available. No issues with the projected Salt Batch 4 strategy are identified. This revision includes additional data points that were not available in the original issue of the document, such as additional plutonium results, the results of the monosodium titanate (MST) sorption test and the extraction, scrub strip (ESS) test. This report covers the revision to the Tank 21H qualification sample results for Macrobatch (Salt Batch) 4 of the Integrated Salt Disposition Program (ISDP). A previous document covers initial characterization which includes results for a number of non-radiological analytes. These results were used to perform aluminum solubility modeling to determine the hydroxide needs for Salt Batch 4 to prevent the precipitation of solids. Sodium hydroxide was then added to Tank 21 and additional samples were pulled for the analyses discussed in this report. This work was specified by Task Technical Request and by Task Technical and Quality Assurance Plan (TTQAP).

  11. Tank 30 and 37 Supernatant Sample Cross-Check and Evaporator Feed Qualification Analysis-2012

    SciTech Connect

    Oji, L. N.

    2013-03-07

    This report summarizes the analytical data reported by the F/H and Savannah River National Laboratories for the 2012 cross-check analysis for high level waste supernatant liquid samples from SRS Tanks 30 and 37. The intent of this Tank 30 and 37 sample analyses was to perform cross-checks against routine F/H Laboratory analyses (corrosion and evaporator feed qualification programs) using samples collected at the same time from both tanks as well as split samples from the tanks.

  12. Tank 241-AZ-101 and tank 241-AZ-102, airlift circulator operation vapor sampling and analysis plan

    SciTech Connect

    TEMPLETON, A.M.

    1999-06-02

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of the tank 241-AZ-101 and 241-AZ-102 airlift circulators (ALCs). The purpose of the ALC operation is to support portions of the operational test procedure (OTP) for Project W-030 (OTP-W030-001) and to perform functional test in support of Project W-151. Project W-030 is the 241-A-702 ventilation upgrade project (241-AZ-702) and Project W-151 is the 241-AZ-101 Mixer Pump Test. The functional tests will check the operability of the tank 241-AZ-101 ALCs. Process Memo's No.2E98-082 and No.2E99-001 (LMHC 1999a, LMHC 1999b) direct the operation of the ALCs and the Industrial Hygiene monitoring respectively. A series of tests will be conducted in which the ALCs in tanks 241-AZ-101 and 241-AZ-102 will be operated at different air flow rates. Vapor samples will be obtained to determine constituents that may be present in the tank headspace during ALC operation at tanks 241-AZ-101 and 241-AZ-102 as the waste is disturbed. During the testing, vapor samples will be obtained from the headspace of tanks 241-AZ-101 and 241-AZ-102 via the unused port on the standard hydrogen monitoring system (SHMS). Results will be used to provide the waste feed delivery program with environmental air permitting data for tank waste disturbing activities. Because of radiological concerns, the samples will be filtered for particulates. It is recognized that this may remove some organic compounds.

  13. SAMPLING OIL-WATER MIXTURES AT OHMSETT (OIL AND HAZARDOUS MATERIALS SIMULATED ENVIRONMENTAL TEST TANK)

    EPA Science Inventory

    The report describes procedures developed at the Oil and Hazardous Material Simulated Environmental Test Tank (OHMSETT) for sampling oil and water mixtures. Two procedures for sampling in containers are discussed: grab and stratified sampling. Both of these techniques require str...

  14. RESULTS OF INITIAL ANALYSES OF THE MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect

    Peters, T.; Fink, S.

    2012-01-31

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Salt (Macro)Batch 5 for the Integrated Salt Disposition Project (ISDP). This document reports the initial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. This report describes the laboratory results of Salt (Macro)Batch 5 preliminary samples from Tank 21H. These results will be used by Tank Farm Engineering for their blend calculations. This work was specified by Technical Task Request (TTR) and by Task Technical and Quality Assurance Plan (TTQAP).

  15. Tank 241-AZ-101 and Tank 241-AZ-102 Airlift Circulator Operation Vapor Sampling and Analysis Plan

    SciTech Connect

    TEMPLETON, A.M.

    1999-12-07

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of the tank 241-AZ-101 and 241-AZ-102 airlift circulators (ALCs) and during the initial operation (''bump'') of the tank 241-AZ-101 mixer pumps. The purpose of the ALC operation is to support portions of the operational test procedure (OTP) for Project W-030 (OTP-W030-001) and to perform functional test in support of Project W-151. Project W-030 is the 241-A-702 ventilation upgrade project (241-142-702) and Project W-151 is the 241-AZ-101 Mixer Pump Test. The functional tests will check the operability of the tank 241-AZ-101 ALCs. Process Memo's No. 2E98-082 and No. 2E99-001 (LMHC 1999a, LMHC 1999b) direct the operation of the ALCs and the Industrial Hygiene monitoring respectively. A series of tests will be conducted in which the ALCs in tanks 241-AZ-101 and 241-AZ-102 will be operated at different air flow rates. Vapor samples will be obtained to determine constituents that may be present in the tank headspace during ALC operation at tanks 241-AZ-101 and 241-AZ-102 as the waste is disturbed. During the testing, vapor samples will be obtained from the headspace of tanks 241-AZ-101 and 241-AZ-102 via the unused port on the standard hydrogen monitoring system (SHMS). In addition the last two vapor samples will be collected from the headspace of tank 241-AZ-101 during the operation of the mixer pumps. Each mixer pump will be operated for approximately 5 minutes. Results will be used to provide the waste feed delivery program with environmental air permitting data for tank waste disturbing activities. Because of radiological concerns, the samples will be filtered for particulates. It is recognized that this may remove some organic compounds. The following sections provide the general methodology and procedures to be used in the preparation, retrieval

  16. Headspace vapor characterization of Hanford Waste Tank 241-S-108: Results from samples collected on December 6, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; McVeety, B.D.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-S-108 (Tank S-108) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5086. Samples were collected by WHC on December 6, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  17. Headspace vapor characterization of Hanford Waste Tank 241-A-103: Results from samples collected on November 9, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Evans, J.C.; Thomas, B.L.; Pool, K.H.; Olsen, K.B.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-A-103 (Tank A-103) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5073. Samples were collected by WHC on November 9, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  18. Headspace vapor characterization of Hanford Waste Tank SX-102: Results from samples collected on July 19, 1995. Tank Vapor Characterization Project

    SciTech Connect

    McVeety, B.D.; Evans, J.C.; Clauss, T.W.; Pool, K.H.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-102 (Tank SX-102) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed under the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5046. Samples were collected by WHC on July 19, 1995, using the vapor sampling system (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  19. Headspace vapor characterization of Hanford Waste Tank 241-T-110: Results from samples collected on August 31, 1995. Tank Vapor Characterization Project

    SciTech Connect

    McVeety, B.D.; Thomas, B.L.; Evans, J.C.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-T-110 (Tank T-110) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5056. Samples were collected by WHC on August 31, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  20. Thermal modeling of core sampling in flammable gas waste tanks. Part 1: Push-mode sampling

    SciTech Connect

    Unal, C.; Stroh, K.; Pasamehmetoglu, K.O.

    1997-08-01

    The radioactive waste stored in underground storage tanks at Hanford site is routinely being sampled for waste characterization purposes. The push- and rotary-mode core sampling is one of the sampling methods employed. The waste includes mixtures of sodium nitrate and sodium nitrite with organic compounds that can produce violent exothermic reactions if heated above 160 C during core sampling. A self-propagating waste reaction would produce very high temperatures that eventually result in failure of the tank and radioactive material releases to environment. A two-dimensional thermal model based on a lumped finite volume analysis method is developed. The enthalpy of each node is calculated from the first law of thermodynamics. A flash temperature and effective contact area concept were introduced to account the interface temperature rise. No maximum temperature rise exceeding the critical value of 60 C was found in the cases studied for normal operating conditions. Several accident conditions are also examined. In these cases it was found that the maximum drill bit temperature remained below the critical reaction temperature as long as a 30 scfm purge flow is provided the push-mode drill bit during sampling in rotary mode. The failure to provide purge flow resulted in exceeding the limiting temperatures in a relatively short time.

  1. Sampling and analysis of the inactive waste tanks TH-2, WC-1, and WC-15

    SciTech Connect

    Autrey, J.W.; Keller, J.M.; Griest, W.H.; Botts, J.L.; Schenley, R.L.; Sipe, M.A.

    1992-02-01

    Thirty-eight inactive liquid low-level radioactive waste tanks are currently managed by the Environmental Restoration Program of Oak Ridge National Laboratory. The contents of these tanks are to be characterized in preparation for future corrective actions and remediation activities as part of compliance with the pending Federal Facility Agreement for the Oak Ridge Reservation. Twenty-nine of these tanks were sampled and analyzed in 1989. Three of the tanks (TH-2, WC-1, and WC-15) were not accessible from the surface and thus were not sampled until 1990. This report presents the sampling and analytical results of that campaign. All three tanks in this report had negligible regulatory organic compounds in the samples that were collected. There were no US Environmental Protection Agency (EPA) Target Compound List (TCL) constituents for volatile organics detected in any of the aqueous samples. The only semivolatile organics detected were 2-chlorophenol (52 {mu}g/L) in tank TH-2 and dichloroethane (14--15 {mu}g/L) and diethyl either (15--17 {mu}g/L) in tank WC-15. A thin oil layer was discovered floating on top of the aqueous contents in tank WC-15. The analysis of the oil layer detected no volatile organics and showed only one EPA TCL constituent, di-n-butylphthalate, at 1900 {mu}g/L. Low levels of Resource Conservation and Recovery Act (RCRA) metals were observed in the samples from tank TH-2, but only the mercury level exceeded the RCRA limit. Samples from tank WC-1 had elevated levels of the RCRA metals barium, chromium, and lead. There were also finely suspended particles in one of the samples from tank WC-1, which was filtered and analyzed separately. This solid fines have levels of transuranium elements {sup 238}Pu and {sup 241}Am high enough to classified as transuranic waste.

  2. Waste compatibility safety issues and final results for tank 241-SY-102 grab samples

    SciTech Connect

    Nuzum, J.L.

    1997-08-14

    Three grab samples (2SY-96-1, 2SY-96-2, and 2SY-96-3) were taken from Riser 1A of Tank 241-SY 102 on January 14, 1997, and received by 222-S Laboratory on January 14, 1997. These samples were analyzed in accordance with Compatibility Grab Sampling and Analysis Plan (TSAP) and Data Quality Objectives for Tank Farm Waste Compatibility Program (DQO) in support of the Waste Compatibility Program. No notifications were required based on sample results. Acetone analysis was not performed in accordance with Cancellation of Acetone Analysis for Tank 241-SY-102 Grab Samples.

  3. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES

    SciTech Connect

    Peters, T.; Fink, S.

    2012-04-24

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

  4. Tools for Inspecting and Sampling Waste in Underground Radioactive Storage Tanks with Small Access Riser Openings

    SciTech Connect

    Nance, T.A.

    1998-12-17

    Underground storage tanks with 2 inches to 3 inches diameter access ports at the Department of Energy's Savannah River Site have been used to store radioactive solvents and sludge. In order to close these tanks, the contents of the tanks need to first be quantified in terms of volume and chemical and radioactive characteristics. To provide information on the volume of waste contained within the tanks, a small remote inspection system was needed. This inspection system was designed to provide lighting and provide pan and tilt capabilities in an inexpensive package with zoom abilities and color video. This system also needed to be utilized inside of a plastic tent built over the access port to contain any contamination exiting from the port. This system had to be build to travel into the small port opening, through the riser pipe, into the tank evacuated space, and out of the riser pipe and access port with no possibility of being caught and blocking the access riser. Long thin plates were found in many access riser pipes that blocked the inspection system from penetrating into the tank interiors. Retrieval tools to clear the plates from the tanks using developed sampling devices while providing safe containment for the samples. This paper will discuss the inspection systems, tools for clearing access pipes, and solvent sampling tools developed to evaluate the tank contents of the underground solvent storage tanks.

  5. Tank 241-C-106 sampling data requirements developed through the data quality objectives (DQO) process

    SciTech Connect

    Wang, O.S.; Bell, K.E.; Anderson, C.M.; Peffers, M.S.; Pulsipher, B.A.; Scott, J.L.

    1994-01-01

    The rate of heat generation for tank 241-C-106 at the Hanford Site is estimated at more then 100,000 Btu/h. The heat is generated primarily from the radioactive decay of {sup 90}Sr waste that was inadvertently transferred into the tank in the late 1960s. If proper tank cooling is not maintained for this tank, heat-induced structural damage to the tank`s concrete shell could result in the release of nuclear waste to the environment. Because of high-heat concerns in January 1991, tank 241-C-106 was designated as a Watch List tank and deemed as a Priority 1 safety issue. Waste Tank Safety Program (WTSP) is responsible for the resolution of this safety issue. Although forced cooling is effective for short term, the long-term resolution for tank cooling is waste retrieval. Single-shell Tank Retrieval Project (Retrieval) is responsible for the safe retrieval and transfer of radioactive waste from tank 241-C-106 to a selected double-shell tank. This data quality objective (DQO) study is an effort to determine engineering and design data needs for WTSP and assist Retrieval in designing contingency action retrieval systems. The 7-step DQO process is a tool developed by the Environmental Protection Agency with a goal of identifying needs and reducing costs. This report discusses the results of two DQO efforts for WTSP and Retrieval. The key data needs to support WTSP are thermal conductivity, permeability, and heat load profile. For the Retrieval support, there are nine and three data needs identified, respectively, for retrieval engineering system design and HVAC system design. The updated schedule to drill two core samples using rotary mode is set for March 1994. The analysis of the sample is expected to be completed by September 1994.

  6. Tank 241-AX-104 upper vadose zone cone penetrometer demonstration sampling and analysis plan

    SciTech Connect

    FIELD, J.G.

    1999-02-02

    This sampling and analysis plan (SAP) is the primary document describing field and laboratory activities and requirements for the tank 241-AX-104 upper vadose zone cone penetrometer (CP) demonstration. It is written in accordance with Hanford Tank Initiative Tank 241-AX-104 Upper Vadose Zone Demonstration Data Quality Objective (Banning 1999). This technology demonstration, to be conducted at tank 241-AX-104, is being performed by the Hanford Tanks Initiative (HTI) Project as a part of Tank Waste Remediation System (TWRS) Retrieval Program (EM-30) and the Office of Science and Technology (EM-50) Tanks Focus Area. Sample results obtained as part of this demonstration will provide additional information for subsequent revisions to the Retrieval Performance Evaluation (RPE) report (Jacobs 1998). The RPE Report is the result of an evaluation of a single tank farm (AX Tank Farm) used as the basis for demonstrating a methodology for developing the data and analyses necessary to support making tank waste retrieval decisions within the context of tank farm closure requirements. The RPE includes a study of vadose zone contaminant transport mechanisms, including analysis of projected tank leak characteristics, hydrogeologic characteristics of tank farm soils, and the observed distribution of contaminants in the vadose zone in the tank farms. With limited characterization information available, large uncertainties exist as to the nature and extent of contaminants that may exist in the upper vadose zone in the AX Tank Farm. Traditionally, data has been collected from soils in the vadose zone through the installation of boreholes and wells. Soil samples are collected as the bore hole is advanced and samples are screened on site and/or sent to a laboratory for analysis. Some in-situ geophysical methods of contaminant analysis can be used to evaluate radionuclide levels in the soils adjacent to an existing borehole. However, geophysical methods require compensation for well

  7. Results of Hg speciation testing on tanks 30, 32, and 37 depth samples

    SciTech Connect

    Bannochie, C. J.

    2015-11-30

    The Savannah River National Laboratory (SRNL) was tasked with preparing and shipping samples for Hg speciation by Eurofins Frontier Global Sciences, Inc. in Seattle, WA on behalf of the Savannah River Remediation (SRR) Mercury Task Team. The twelfth shipment of samples was designated to include 3H evaporator system Tank 30, 32, and 37 depth samples. The Tank 30 depth sample (HTF-30-15-70) was taken at 190 inches from the tank bottom and the Tank 32 depth sample (HTF-32-15-68) was taken at 89 inches from the tank bottom and both were shipped to SRNL on June 29, 2015 in an 80 mL stainless steel dip bottles. The Tank 37 surface sample (HTF-37-15-94) was taken around 253.4 inches from the tank bottom and shipped to SRNL on July 21, 2015 in an 80 mL stainless steel dip bottle. All samples were placed in the SRNL Shielded Cells and left unopened until intermediate dilutions were made on July 24, 2015 using 1.00 mL of sample diluted to 100.00 mL with deionized H2O. A 30 mL Teflon® bottle was rinsed twice with the diluted tank sample and then filled leaving as little headspace as possible. It was immediately removed from the Shielded Cells and transferred to refrigerated storage where it remained at 4 °C until final dilutions were made on October 20. A second portion of the cells diluted tank sample was poured into a shielded polyethylene bottle and transferred to Analytical Development for radiochemical analysis data needed for Hazardous Material Transportation calculations.

  8. Results for the second quarter 2014 tank 50 WAC slurry sample chemical and radionuclide contaminants

    SciTech Connect

    Bannochie, C.

    2014-09-04

    This report details the chemical and radionuclide contaminant results for the characterization of the 2014 Second Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

  9. Results For The Fourth Quarter 2014 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants

    SciTech Connect

    Crawford, C.

    2015-09-30

    This report details the chemical and radionuclide contaminant results for the characterization of the Calendar Year (CY) 2014 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

  10. Results For The Third Quarter 2013 Tank 50 WAC Slurry Sample

    SciTech Connect

    Bannochie, Christopher J.

    2013-11-26

    This report details the chemical and radionuclide contaminant results for the characterization of the 2013 Third Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

  11. Results For The Second Quarter 2013 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants

    SciTech Connect

    Bannochie, Christopher J.

    2013-07-31

    This report details the chemical and radionuclide contaminant results for the characterization of the 2013 Second Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by Saltstone Facility Engineering (SFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

  12. Results for the Third Quarter 2012 Tank 50 WAC Slurry Sample: Chemical and Radionuclide Contaminants

    SciTech Connect

    Bannochie, C. J.

    2012-10-26

    This report details the chemical and radionuclide contaminant results for the characterization of the 2012 Third Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

  13. Tank vapor sampling and analysis data package for tank 241-C-106 waste retrieval sluicing system process test phase III

    SciTech Connect

    LOCKREM, L.L.

    1999-08-13

    This data package presents sampling data and analytical results from the March 28, 1999, vapor sampling of Hanford Site single-shell tank 241-C-106 during active sluicing. Samples were obtained from the 296-C-006 ventilation system stack and ambient air at several locations. Characterization Project Operations (CPO) was responsible for the collection of all SUMMATM canister samples. The Special Analytical Support (SAS) vapor team was responsible for the collection of all triple sorbent trap (TST), sorbent tube train (STT), polyurethane foam (PUF), and particulate filter samples collected at the 296-C-006 stack. The SAS vapor team used the non-electrical vapor sampling (NEVS) system to collect samples of the air, gases, and vapors from the 296-C-006 stack. The SAS vapor team collected and analyzed these samples for Lockheed Martin Hanford Corporation (LMHC) and Tank Waste Remediation System (TWRS) in accordance with the sampling and analytical requirements specified in the Waste Retrieval Sluicing System Vapor Sampling and Analysis Plan (SAP) for Evaluation of Organic Emissions, Process Test Phase III, HNF-4212, Rev. 0-A, (LMHC, 1999). All samples were stored in a secured Radioactive Materials Area (RMA) until the samples were radiologically released and received by SAS for analysis. The Waste Sampling and Characterization Facility (WSCF) performed the radiological analyses. The samples were received on April 5, 1999.

  14. Underground radioactive waste tank remote inspection and sampling

    SciTech Connect

    Bzorgi, F.M.; Kelsey, A.P.; Van Hoesen, S.D.; Wiles, C.O.

    1996-04-01

    Characterization is a critical step in the remediation of contaminated materials and facilities. Severe physical- and radiological-access restrictions made the task of characterizing the World War II-era underground radioactive storage tanks at the Oak Ridge National Laboratory (ORNL) particularly challenging. The innovative and inexpensive tank characterization system (TCS) developed to meet this challenge at ORNL is worthy of consideration for use in similar remediation projects. The TCS is a floating system that uses the existing water in the tank as a platform that supports instruments and samplers mounted on a floating boom. TCS operators feed the unit into an existing port of the tank to be characterized. Once inserted, the system`s position is controlled by rotation and by insertion and withdrawal of the boom. The major components of the TCS system include the following: (1) boom support system that consists of a boom support structure and a floating boom, (2) video camera and lights, (3) sludge grab sampler, (4) wall chip sampler, and (5) sonar depth finder. This simple design allows access to all parts of a tank. Moreover, the use of off-the-shelf components keeps the system inexpensive and minimizes maintenance costs. The TCS proved invaluable in negotiating the hazards of ORNL`s Gunite and Associated Tanks, which typically contain a layer of radioactive sludge, have only one to three access ports that are usually only 12- or 24-in. in diameter, and range from 12 to 50 ft in diameter. This paper reviews both the successes and the difficulties encountered in using the TCS for treatability studies at ORNL and discusses the prospects for its wider application in remediation activities.

  15. Analyses of Surface and Variable Depth Samples from Tank 43H

    SciTech Connect

    Wilmarth, W.R.

    2001-05-15

    Researchers analyzed surface and variable depth samples from the feed tank, Tank 43H, for the 242-16H High Level Waste Evaporator. These analyses support the root cause analysis for the formation of solids in the 2H Evaporator Pot.

  16. SAMPLE RESULTS FROM THE INTERIM SALT DISPOSITION PROGRAM MACROBATCH 8 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect

    Peters, T. B.; Washington, A. L.

    2015-01-13

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub- Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D{sub (Cs)}) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

  17. ACTUAL-WASTE TESTS OF ENHANCED CHEMICAL CLEANING FOR RETRIEVAL OF SRS HLW SLUDGE TANK HEELS AND DECOMPOSITION OF OXALIC ACID

    SciTech Connect

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

    2012-01-12

    Savannah River National Laboratory conducted a series of tests on the Enhanced Chemical Cleaning (ECC) process using actual Savannah River Site waste material from Tanks 5F and 12H. Testing involved sludge dissolution with 2 wt% oxalic acid, the decomposition of the oxalates by ozonolysis (with and without the aid of ultraviolet light), the evaporation of water from the product, and tracking the concentrations of key components throughout the process. During ECC actual waste testing, the process was successful in decomposing oxalate to below the target levels without causing substantial physical or chemical changes in the product sludge.

  18. Tank 12H Acidic Chemical Cleaning Sample Analysis And Material Balance

    SciTech Connect

    Martino, C. J.; Reboul, S. H.; Wiersma, B. J.; Coleman, C. J.

    2013-11-08

    A process of Bulk Oxalic Acid (BOA) chemical cleaning was performed for Tank 12H during June and July of 2013 to remove all or a portion of the approximately 4400 gallon sludge heel. Three strikes of oxalic acid (nominally 4 wt% or 2 wt%) were used at 55°C and tank volumes of 96- to 140-thousand gallons. This report details the sample analysis of a scrape sample taken prior to BOA cleaning and dip samples taken during BOA cleaning. It also documents a rudimentary material balance for the Tank 12H cleaning results.

  19. Results of initial analyses of the salt (macro) batch 9 tank 21H qualification samples

    SciTech Connect

    Peters, T. B.

    2015-10-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics or observations, such as floating solids, the presence of large amount of solids, or unusual colors. Further results on the chemistry and other tests will be issued in the future.

  20. Results Of Initial Analyses Of The Salt (Macro) Batch 9 Tank 21H Qualification Samples

    SciTech Connect

    Peters, T.

    2015-10-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics. Further results on the chemistry and other tests will be issued in the future.

  1. Solvent Hold Tank Sample Results for MCU-15-556-557-558. March 2015 Monthly Sample

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2015-05-04

    Savannah River National Laboratory (SRNL) received one set of Solvent Hold Tank (SHT) samples (MCU-15-556, MCU-15-557, and MCU-15-558), pulled on 03/16/2015 for analysis. The samples were combined and analyzed for composition. Analysis of the composite sample MCU-15-556-557-558 indicated a low concentration (~ 78 % of nominal) of the suppressor (TiDG) and concentrations of the extractant (MaxCalix), and of the modifier (CS-7SB) in the solvent that were slightly lower than nominal. This analysis confirms the addition of TiDG, MaxCalix, and modifier to the solvent in February 2015. Based on the current monthly sample, the levels of TiDG, MaxCalix, and modifier are sufficient for continuing operation without adding a trim at this time. No impurities above the 1000 ppm level were found in this solvent by the Semi-Volatile Organic Analysis (SVOA). However, the p-nut vials that delivered the samples contained small (1 mm) droplets of oxidized modifier and amides (as detected by the FTIR analysis). In addition, up to 21 microgram of mercury per gram of solvent (or 17.4 µg/mL) was detected in this sample. The laboratory will continue to monitor the quality of the solvent in particular for any new impurities or degradation of the solvent components.

  2. Organic Tank Safety Project: development of a method to measure the equilibrium water content of Hanford organic tank wastes and demonstration of method on actual waste

    SciTech Connect

    Scheele, R.D.; Bredt, P.R.; Sell, R.L.

    1996-09-01

    Some of Hanford`s underground waste storage tanks contain Organic- bearing high level wastes that are high priority safety issues because of potentially hazardous chemical reactions of organics with inorganic oxidants in these wastes such as nitrates and nitrites. To ensure continued safe storage of these wastes, Westinghouse Hanford Company has placed affected tanks on the Organic Watch List and manages them under special rules. Because water content has been identified as the most efficient agent for preventing a propagating reaction and is an integral part of the criteria developed to ensure continued safe storage of Hanford`s organic-bearing radioactive tank wastes, as part of the Organic Tank Safety Program the Pacific Northwest National Laboratory developed and demonstrated a simple and easily implemented procedure to determine the equilibrium water content of these potentially reactive wastes exposed to the range of water vapor pressures that might be experienced during the wastes` future storage. This work focused on the equilibrium water content and did not investigate the various factors such as @ ventilation, tank surface area, and waste porosity that control the rate that the waste would come into equilibrium, with either the average Hanford water partial pressure 5.5 torr or other possible water partial pressures.

  3. Tank 241-B-103 headspace gas and vapor characterization: Results for homogeneity samples collected on October 16, 1996. Tank vapor characterization project

    SciTech Connect

    Olsen, K.B.; Pool, K.H.; Evans, J.C.

    1997-06-01

    This report presents the results of analyses of samples taken from the headspace of waste storage tank 241-B-103 (Tank B-103) at the Hanford Site in Washington State. Samples were collected to determine the homogeneity of selected inorganic and organic headspace constituents. Two risers (Riser 2 and Riser 7) were sampled at three different elevations (Bottom, Middle, and Top) within the tank. Tank headspace samples were collected by SGN Eurisys Service Corporation (SESC) and were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL.

  4. Test plan for evaluating the performance of the in-tank fluidic sampling system

    SciTech Connect

    BOGER, R.M.

    1999-02-17

    The PHMC will provide Low Activity Wastes (LAW) tank wastes for final treatment by a privatization contractor from double-shell feed tanks, 241-AP-102 and 241-AP-104, Concerns about the inability of the baseline ''grab'' sampling to provide large volume samples within time constraints has led to the development of a conceptual sampling system that would be deployed in a feed tank riser, This sampling system will provide large volume, representative samples without the environmental, radiation exposure, and sample volume impacts of the current base-line ''grab'' sampling method. This test plan identifies ''proof-of-principle'' cold tests for the conceptual sampling system using simulant materials. The need for additional testing was identified as a result of completing tests described in the revision test plan document, Revision 1 outlines tests that will evaluate the performance and ability to provide samples that are representative of a tanks' content within a 95 percent confidence interval, to recovery from plugging, to sample supernatant wastes with over 25 wt% solids content, and to evaluate the impact of sampling at different heights within the feed tank. The test plan also identifies operating parameters that will optimize the performance of the sampling system.

  5. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect

    Peters, T. B.; Washington, A. L. II

    2013-08-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

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

    SciTech Connect

    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.

    2009-02-13

    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.

  7. SCANNING ELECTRON MICROSCOPY AND X-RAY DIFFRACTION ANALYSIS OF TANK 18 SAMPLES

    SciTech Connect

    Hay, M.; O'Rourke, P.; Ajo, H.

    2012-03-08

    The F-Area Tank Farm (FTF) Performance Assessment (PA) utilizes waste speciation in the waste release model used in the FTF fate and transport modeling. The waste release modeling associated with the residual plutonium in Tank 18 has been identified as a primary contributor to the Tank 18 dose uncertainty. In order to reduce the uncertainty related to plutonium in Tank 18, a better understanding of the plutonium speciation in the Tank 18 waste (including the oxidation state and stoichiometry) is desired. Savannah River National Laboratory (SRNL) utilized Scanning Electron Microscopy (SEM) and X-ray Diffraction (XRD) to analyze Tank 18 samples to provide information on the speciation of plutonium in the waste material. XRD analysis of the Tank 18 samples did not identify any plutonium mineral phases in the samples. These indicates the crystalline mineral phases of plutonium are below the detection limits of the XRD method or that the plutonium phase(s) lack long range order and are present as amorphous or microcrystalline solids. SEM analysis of the Tank 18 samples did locate particles containing plutonium. The plutonium was found as small particles, usually <1 {micro}m but ranging up to several micrometers in diameter, associated with particles of an iron matrix and at low concentration in other elemental matrices. This suggests the plutonium has an affinity for the iron matrix. Qualitatively, the particles of plutonium found in the SEM analysis do not appear to account for all of the plutonium in the sample based on concentrations determined from the chemical analysis of the Tank 18 samples. This suggests that plutonium is also distributed throughout the solids in low concentrations.

  8. Solvent Hold Tank Sample Results For MCU-15-750-751-752-: June Monthly Sample

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2015-10-07

    Savannah River National Laboratory (SRNL) received one set of Solvent Hold Tank (SHT) samples (MCU-15-750, MCU-15-751, and MCU-15-752), pulled on 06/22/2015 for analysis. The samples were combined and analyzed for composition. Analysis of the composite sample MCU-15-750-751-752 indicated a low concentration (~ 49 % of nominal) of the suppressor (TiDG) and slightly lower than nominal concentrations of the extractant (MaxCalix), and of the modifier (Cs-7SB) in the solvent. This analysis confirms the addition of TiDG, MaxCalix, and modifier to the solvent in February 2015. Based on the current monthly sample, the levels of TiDG, MaxCalix, and modifier are sufficient for continuing operation without adding a trim at this time but it is recommended that an addition of TiDG, modifier and Isopar™L should be made in the near future. No impurities above the 1000 ppm level were found in this solvent by the Semi-Volatile Organic Analysis (SVOA). No impurities were observed in the Hydrogen Nuclear Magnetic Resonance (HNMR). In addition, up to 13.9 micrograms of mercury per gram of solvent (or 11.5 µg/mL) was detected in this sample. The laboratory will continue to monitor the quality of the solvent in particular for any new impurities or degradation of the solvent components.

  9. STATISTICAL SAMPLING FOR IN-SERVICE INSPECTION OF LIQUID WASTE TANKS AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Harris, S.; Baxter, L.

    2011-04-07

    Savannah River Remediation, LLC (SRR) is implementing a statistical sampling strategy for In-Service Inspection (ISI) of Liquid Waste (LW) Tanks at the United States Department of Energy's Savannah River Site (SRS) in Aiken, South Carolina. As a component of SRS's corrosion control program, the ISI program assesses tank wall structural integrity through the use of ultrasonic testing (UT). The statistical strategy for ISI is based on the random sampling of a number of vertically oriented unit areas, called strips, within each tank. The number of strips to inspect was determined so as to attain, over time, a high probability of observing at least one of the worst 5% in terms of pitting and corrosion across all tanks. The probability estimation to determine the number of strips to inspect was performed using the hypergeometric distribution. Statistical tolerance limits for pit depth and corrosion rates were calculated by fitting the lognormal distribution to the data. In addition to the strip sampling strategy, a single strip within each tank was identified to serve as the baseline for a longitudinal assessment of the tank safe operational life. The statistical sampling strategy enables the ISI program to develop individual profiles of LW tank wall structural integrity that collectively provide a high confidence in their safety and integrity over operational lifetimes.

  10. Solvent Hold Tank Sample Results For MCU-15-710-711-712: June 2015 Monthly Sample

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2015-10-07

    Savannah River National Laboratory (SRNL) received one set of Solvent Hold Tank (SHT) samples (MCU-15-710, MCU-15-711, and MCU-15-712), pulled on 06/15/2015 for analysis. The samples were combined and analyzed for composition. Analysis of the composite sample MCU-15-710-711-712 indicated a low concentration (~ 55 % of nominal) of the suppressor (TiDG) and concentrations of the extractant (MaxCalix), and of the modifier (Cs-7SB) in the solvent that were slightly lower than nominal. This analysis confirms the addition of TiDG, MaxCalix, and modifier (92 % of nominal) to the solvent in February 2015. Based on the current monthly sample, the levels of TiDG, MaxCalix, and modifier were sufficient when this solvent sample was collected from MCU. A higher cesium concentration (9.3 E6 dpm/mL) was observed in this sample relative to recent samples. In the past, this level of cesium appeared to correlate with upsets in the MCU operation. It is not known at this time the reason for the higher cesium level in this solvent. No impurities above the 1000 ppm level were found in this solvent by the Semi-Volatile Organic Analysis (SVOA). In addition, the sample contains up to 10.4 micrograms of mercury per gram of solvent (or 8.7 µg/mL). A relatively large cesium concentration (9.3 E 6 dpm/mL) was measured in this solvent and it may indicate poor cesium stripping. The laboratory will continue to monitor the quality of the solvent in particular for any new impurities or degradation of the solvent components.

  11. CRUCIBLE TESTING OF TANK 48 RADIOACTIVE WASTE SAMPLE USING FBSR TECHNOLOGY FOR ORGANIC DESTRUCTION

    SciTech Connect

    Hammond, C; William Pepper, W

    2008-09-19

    The purpose of crucible scale testing with actual radioactive Tank 48H material was to duplicate the test results that had been previously performed on simulant Tank 48H material. The earlier crucible scale testing using simulants was successful in demonstrating that bench scale crucible tests produce results that are indicative of actual Fluidized Bed Steam Reforming (FBSR) pilot scale tests. Thus, comparison of the results using radioactive Tank 48H feed to those reported earlier with simulants would then provide proof that the radioactive tank waste behaves in a similar manner to the simulant. Demonstration of similar behavior for the actual radioactive Tank 48H slurry to the simulant is important as a preliminary or preparation step for the more complex bench-scale steam reformer unit that is planned for radioactive application in the Savannah River National Laboratory (SRNL) Shielded Cells Facility (SCF) later in 2008. The goals of this crucible-scale testing were to show 99% destruction of tetraphenylborate and to demonstrate that the final solid product produced is sodium carbonate. Testing protocol was repeated using the specifications of earlier simulant crucible scale testing, that is sealed high purity alumina crucibles containing a pre-carbonated and evaporated Tank 48H material. Sealing of the crucibles was accomplished by using an inorganic 'nepheline' sealant. The sealed crucibles were heat-treated at 650 C under constant argon flow to inert the system. Final product REDOX measurements were performed to establish the REDuction/OXidation (REDOX) state of known amounts of added iron species in the final product. These REDOX measurements confirm the processing conditions (pyrolysis occurring at low oxygen fugacity) of the sealed crucible environment which is the environment actually achieved in the fluidized bed steam reformer process. Solid product dissolution in water was used to measure soluble cations and anions, and to investigate insoluble

  12. CRUCIBLE TESTING OF TANK 48H RADIOACTIVEWASTE SAMPLE USING FLUIDIZED BED STEAMREFORMING TECHNOLOGY FOR ORGANICDESTRUCTION

    SciTech Connect

    Crawford, C

    2008-07-31

    The purpose of crucible scale testing with actual radioactive Tank 48H material was to duplicate the test results that had been previously performed on simulant Tank 48H material. The earlier crucible scale testing using simulants was successful in demonstrating that bench scale crucible tests produce results that are indicative of actual Fluidized Bed Steam Reforming (FBSR) pilot scale tests. Thus, comparison of the results using radioactive Tank 48H feed to those reported earlier with simulants would then provide proof that the radioactive tank waste behaves in a similar manner to the simulant. Demonstration of similar behavior for the actual radioactive Tank 48H slurry to the simulant is important as a preliminary or preparation step for the more complex bench-scale steam reformer unit that is planned for radioactive application in the Savannah River National Laboratory (SRNL) Shielded Cells Facility (SCF) later in 2008. The goals of this crucible-scale testing were to show 99% destruction of tetraphenylborate and to demonstrate that the final solid product produced is sodium carbonate. Testing protocol was repeated using the specifications of earlier simulant crucible scale testing, that is sealed high purity alumina crucibles containing a pre-carbonated and evaporated Tank 48H material. Sealing of the crucibles was accomplished by using an inorganic 'nepheline' sealant. The sealed crucibles were heat-treated at 650 C under constant argon flow to inert the system. Final product REDOX measurements were performed to establish the REDuction/OXidation (REDOX) state of known amounts of added iron species in the final product. These REDOX measurements confirm the processing conditions (pyrolysis occurring at low oxygen fugacity) of the sealed crucible environment which is the environment actually achieved in the fluidized bed steam reformer process. Solid product dissolution in water was used to measure soluble cations and anions, and to investigate insoluble

  13. Analysis of tank 23H samples in support of salt batch planning

    SciTech Connect

    Hay, M. S.; Coleman, C. J.; Diprete, D. P.

    2015-08-14

    Savannah River Remediation obtained three samples from different heights within Tank 23H. The samples were analyzed by Savannah River National Laboratory to support salt batch planning. The results from the analysis indicate the top two samples from the tank appear similar in composition. The lowest sample from the tank contained significantly more solids and a more concentrated salt solution. The filtered supernate from the bottom sample showed ~60% lower Sr-90 and Pu-238 concentrations than the decanted (unfiltered) supernate results which may indicate the presence of some small amount of entrained solid particles in the decanted sample. The mercury concentrations measured in the filtered supernate were fairly low for all three samples ranging from 11.2 to 42.3 mg/L.

  14. Demonstration of the TRUEX process for the treatment of actual high activity tank waste at the INEEL using centrifugal contactors

    SciTech Connect

    Law, J.D.; Brewer, K.N.; Todd, T.A.; Olson, L.G.

    1997-10-01

    The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), formerly reprocessed spent nuclear fuel to recover fissionable uranium. The radioactive raffinates from the solvent extraction uranium recovery processes were converted to granular solids (calcine) in a high temperature fluidized bed. A secondary liquid waste stream was generated during the course of reprocessing, primarily from equipment decontamination between campaigns and solvent wash activities. This acidic tank waste cannot be directly calcined due to the high sodium content and has historically been blended with reprocessing raffinates or non-radioactive aluminum nitrate prior to calcination. Fuel reprocessing activities are no longer being performed at the ICPP, thereby eliminating the option of waste blending to deplete the waste inventory. Currently, approximately 5.7 million liters of high-activity waste are temporarily stored at the ICPP in large underground stainless-steel tanks. The United States Environmental Protection Agency and the Idaho Department of Health and Welfare filed a Notice of Noncompliance in 1992 contending some of the underground waste storage tanks do not meet secondary containment. As part of a 1995 agreement between the State of Idaho, the Department of Energy, and the Department of Navy, the waste must be removed from the tanks by 2012. Treatment of the tank waste inventories by partitioning the radionuclides and immobilizing the resulting high-activity and low-activity waste streams is currently under evaluation. A recent peer review identified the most promising radionuclide separation technologies for evaluation. The Transuranic Extraction-(TRUEX) process was identified as a primary candidate for separation of the actinides from ICPP tank waste.

  15. Characterization of Core Samples from a Hardened Crust Layer in Tank 4F

    SciTech Connect

    Hay, M. L.

    2005-09-28

    Waste removal operations in Tank 4F are scheduled to begin in late 2005 to provide material for Sludge Batch 5. Mining/probing operations to support installation of submersible mixer pumps encountered a hard layer of material at {approx}45'' to 50'' from the bottom of the tank. Attempts at penetrating the hard layer using a manual mining tool in several different risers were not successful. A core-sampling tool was used to obtain samples of the hard crust layer in Tank 4F for characterization. Three 12'' core samples and a dip sample of the supernate near the surface of the hard layer were sent to Savannah River National Laboratory (SRNL) for characterization. X-ray Diffraction (XRD) results for the crystalline solids from both sample FTF-434 and FTF-435 identifies the major component of both samples as Burkeite (Na{sub 6}(CO{sub 3})(SO{sub 4}){sub 2}). All of the other data collected on the crystalline solids from the Tank 4F core samples support this conclusion. The conditions in Tank 4F for the last twenty years have been ideal for Burkeite formation. The tank has been largely undisturbed with a tank temperature consistently above 30 C, a carbonate to sulfate molar ratio in the supernate conducive to Burkeite formation, and slow evaporation of the supernate phase. Thermodynamic modeling and the results of a Burkeite solubility test confirm that a ratio of 1:1:12 for the volumes of Burkeite solids, supernate, and inhibited water will dissolve all of the Burkeite. These ratios could be used to remove the 6'' layer of Burkeite from Tank 4F with no mixing. However, the thermodynamic modeling and the solubility test neglect the sludge layer beneath the Burkeite crust in Tank 4F. Settled sludge in Savannah River Site (SRS) high-level waste tanks usually contains greater than 75% interstitial supernate by volume. If the supernate in the sludge layer should mix into the solution used to dissolve the Burkeite, significantly more inhibited water would be needed to

  16. Solvent Hold Tank Sample Results for MCU-15-661-662-663: April 2015 Monthly Sample

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2015-07-08

    The Savannah River National Lab (SRNL) received one set of Solvent Hold Tank (SHT) samples (MCU-15-661, MCU-15-662, and MCU-15-663 pulled on April 2, 2015) for analysis. The samples were combined and analyzed for composition. Analysis of the composite sample MCU-15-661-662-663 indicated a low concentration (~ 63% of nominal) of the suppressor (TiDG) and a slightly below the nominal concentration (~ 10% below nominal) of the extractant (MaxCalix). The modifier (CS-7SB) level was also 10% below its nominal value while the Isopar™ L level was slightly above its nominal value. This analysis confirms the addition of Isopar™L to the solvent on March 6, 2015. Despite that the values are below target component levels, the current levels of TiDG, CS-7SB and MaxCalix are sufficient for continuing operation without adding a trim at this time until the next monthly sample. No impurities above the 1000 ppm level were found in this solvent. However, the sample was found to contain approximately 18.4 ug/gsolvent mercury. The gamma level increased to 8 E5 dpm/mLsolvent and it represents an order of magnitude increase relative to previous solvent samples. The increase means less cesium is being stripped from the solvent. Further analysis is needed to determine if the recent spike in the gamma measurement is due to external factors such as algae or other material that may impede stripping. The laboratory will continue to monitor the quality of the solvent in particular for any new impurity or degradation of the solvent components.

  17. Analysis of Tank 48H Samples HTF-E-04-049 and HTF-E-04-050

    SciTech Connect

    Lambert, D

    2004-08-23

    Due to the need for additional HLW storage, successful disposition of the material in Tank 48H and return of the tank to routine service are two critically needed activities. As an initial step in the process, SRNL compositionally characterized the components of the Tank 48H slurry. A nominal Tank 48H Tank 48H slurry sample was collected on August 23, 2004 (HTF-E-04-049 and HTF-E-04-050). The August 23, 2004 sample contained approximately 2 Liters of Tank 48H slurry. This document provides the chemical and radiological properties of a Tank 48H slurry sample. A Technical Task Request defines the required analyses. A Task Plan summarized the analyses required and the methods for completing these analyses. The Tank 48H volume was 239,000 gallons (68.2 inches) at the time of the sampling.

  18. Headspace vapor characterization of Hanford Waste Tank 241-BY-108: Results from samples collected January 23, 1996. Tank Vapor Characterization Project

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.L.; Olsen, K.B.

    1996-07-01

    This report describes the results of vapor samples obtained to compare vapor sampling of the tank headspace using the Vapor Sampling System (VSS) and In Situ Vapor Sampling System (ISVS) with and without particulate prefiltration. Samples were collected from the headspace of waste storage tank 241-BY-108 (Tank BY-108) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) was contracted by Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for water, ammonia, permanent gases, total nonmethane hydrocarbons (TNMHCs, also known as TO-12), and organic analytes in samples collected in SUMMA{trademark} canisters and on triple sorbent traps (TSTs) from the tank headspace. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sampling and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Sampling and Analysis Plan for Tank Vapor Sampling Comparison Test{close_quotes}, and the sample jobs were designated S6004, S6005, and S6006. Samples were collected by WHC on January 23, 1996, using the VSS, a truck-based sampling method using a heated probe; and the ISVS with and without particulate prefiltration.

  19. Headspace vapor characterization of Hanford Waste Tank 241-S-102: Results from samples collected on January 26, 1996. Tank Vapor Characterization Project

    SciTech Connect

    Evans, J.C.; Thomas, B.L.; Pool, K.H.

    1996-07-01

    This report describes the results of vapor samples obtained to compare vapor sampling of the tank headspace using the Vapor Sampling System (VSS) and In Situ Vapor Sampling System (ISVS) with and without particulate prefiltration. Samples were collected from the headspace of waste storage tank 241-S-102 (Tank S-102) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) was contracted by Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for water, ammonia, permanent gases, total nonmethane hydrocarbons (TNMHCs, also known as TO-12), and organic analytes in samples collected in SUMMA{trademark} canisters and on triple sorbent traps (TSTs) from the tank headspace. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sampling and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Sampling and Analysis Plan for Tank Vapor Sampling Comparison Test{close_quote}, and the sample jobs were designated S6007, S6008, and S6009. Samples were collected by WHC on January 26, 1996, using the VSS, a truck-based sampling method using a heated probe; and the ISVS with and without particulate prefiltration.

  20. RECOMMENDATIONS FOR ASSESSING THE UNCERTAINTY IN TANK 18-F WALL SAMPLES

    SciTech Connect

    Shine, G.

    2010-10-26

    Tank 18-F in the F-Area Tank Farm at the Savannah River Site (SRS) has had measurements taken from its inner vertical sides in order to determine the level of radionuclide and other analyte concentrations attached to the tank walls. In all, three samples have been obtained by drilling shallow holes into the carbon steel walls and consolidating the material. An Upper Wall Sample (Sample ID: Tk 18-1) was formed by combining two drill samples taken at a height of 17 ft above the tank floor, and a Lower Wall Sample (Sample ID: SPD4) was formed by combining two drill samples taken between 10 and 12 ft above the tank floor. A Scale Sample (Sample ID: Tk 18-2) was formed by combining 5 drill samples obtained between 6 and 7 ft above the tank floor. Photographs of the sampled material and a more detailed description of the samples and the concentration results are presented by Hay and others [2009]. The objective of this report is to determine a method and use it to place an upper confidence bound on the concentrations in the wall samples using only the currently available sample information. None of the three wall locations (tank heights) has been measured more than once. For radionuclides, only the variation among the concentrations per unit mass (g) of the wall samples, ignoring locations, or the variation among the concentrations of the floor samples are possibilities for establishing an upper confidence bound. The wall samples and floor samples were examined for comparability by (a) observing whether the wall sample concentrations fell inside the footprints created by prediction intervals for floor sample radionuclide concentrations and (b) whether the variation among the wall samples was approximately the same as the variation among floor samples. Most of the radionuclide concentrations satisfied (a) but the variation among radionuclide concentrations (b) was smaller for the floor samples. Consequently, upper 95% confidence bounds were established separately for

  1. Vapor and gas sampling of single-shell tank 241-S-106 using the in situ vapor sampling system

    SciTech Connect

    Lockrem, L.L.

    1997-08-05

    The Vapor Issue Resolution Program tasked the Vapor Team (VT) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-S-106. This document presents In Situ vapor Sampling System (ISVS) data resulting from the June 13, 1996 sampling of SST 241-S-106. Analytical results will be presented in separate reports issued by the Pacific Northwest National Laboratory (PNNL) which`supplied and analyzed the sample media.

  2. Characterization of Tank 48H Samples for Alpha Activity and Actinide Isotopics

    SciTech Connect

    Hobbs, D.T.; Coleman, C.J.; Hay, M.S.

    1995-12-04

    This document reports the total alpha activity and actinide isotopic results for samples taken from Tank 48H prior to the addition of sodium tetraphenylborate and MST in Batch {number_sign}1 of the ITP process. This information used to determine the quantity of MST for Batch {number_sign}1 of the ITP process and the total actinide content in the tank for dose calculations.

  3. Waste tank vapor project: Vapor space characterization of waste tank 241-BY-104: Results from samples collected on June 24, 1994

    SciTech Connect

    Clauss, T.W.; Ligotke, M.W.; McVeety, B.D.; Pool, K.H.; Lucke, R.B.; Fruchter, J.S.; Goheen, S.C.

    1994-11-01

    This report describes results of the analyses of tank-headspace samples taken from Hanford waste Tank 241-BY-104 (referred to as Tank BY-104) on June 24, 1994. The Pacific Northwest Laboratory (PNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze inorganic and organic samples collected from the tank headspace. The sample job was designated S4019 and was performed by WHC on June 24, 1994 using the vapor sampling system (VSS). The results of the analyses are expected to be used in the determination of safety and toxicological issues related to the tank-headspace gas as described in the WHC report entitled Data Quality Objectives for Generic In-Tank Health and Safety Vapor Issue Resolution, WHC-SD-WM-DQO-002, Rev. 0. Sampling devices, including 16 sorbent trains (for inorganic analyses), and 5 SUMMA{trademark} canisters (for organic analyses), were supplied to the WHC sampling staff on June 20, 1994. Samples were taken (by WHC) on June 24. The samples were returned from the field on June 27. The inorganic samples delivered to PNL on chain-of-custody (COC) 006893 included 16 sorbent trains as described in Tables 2.2, 2.3, and 2.4. Additional inorganic blank spikes were obtained from related sample jobs. SUMMA{trademark} samples delivered to PNL on COC 006896 included one ambient air sample, one ambient-air sample through the sampling system, and three tank-headspace SUMMA{trademark} canister samples. The samples were inspected upon delivery to the 326/23B laboratory and logged into PNL laboratory record book 55408. Custody of the sorbent trains was transferred to PNL personnel performing the inorganic analysis and stored at refrigerated ({le}10{degrees}C) temperature until the time of analysis. Access to the 326/23B laboratory is limited to PNL personnel working on the waste-tank safety program.

  4. Waste Tank Organic Safety Project: Analysis of liquid samples from Hanford waste tank 241-C-103

    SciTech Connect

    Pool, K.H.; Bean, R.M.

    1994-03-01

    A suite of physical and chemical analyses has been performed in support of activities directed toward the resolution of an Unreviewed Safety Question concerning the potential for a floating organic layer in Hanford waste tank 241-C-103 to sustain a pool fire. The analysis program was the result of a Data Quality Objectives exercise conducted jointly with staff from Westinghouse Hanford Company and Pacific Northwest Laboratory (PNL). The organic layer has been analyzed for flash point, organic composition including volatile organics, inorganic anions and cations, radionuclides, and other physical and chemical parameters needed for a safety assessment leading to the resolution of the Unreviewed Safety Question. The aqueous layer underlying the floating organic material was also analyzed for inorganic, organic, and radionuclide composition, as well as other physical and chemical properties. This work was conducted to PNL Quality Assurance impact level III standards (Good Laboratory Practices).

  5. FY2001 Tank Characterization Technical Sampling Basis & Waste Information Requirements Document

    SciTech Connect

    ADAMS, M.R.

    2000-08-02

    The Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document (TSB-WIRD) has the following purposes: (1) To identify and integrate sampling and analysis needs for fiscal year (FY) 2001 and beyond. (2) To describe the overall drivers that require characterization information and to document their source. (3) To describe the process for identifying, prioritizing, and weighting issues that require characterization information to resolve. (4) To define the method for determining sampling priorities and to present the sampling priorities on a tank-by-tank basis. (5) To define how the characterization program is going to satisfy the drivers, close issues, and report progress. (6)To describe deliverables and acceptance criteria for characterization deliverables.

  6. RESULTS OF ANALYSES OF THE MACROBATCH 4 TANK 49H CONFIRMATORY SAMPLE

    SciTech Connect

    Peters, T.; Fink, S.

    2012-01-31

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 49H in support of qualification of Salt (Macro)Batch 4 for the Integrated Salt Disposition Project (ISDP). This document reports the results of the analyses of the confirmatory sample of Tank 49H. All sample results either agree with expectations based on prior analyses or are considered trivial enough not to warrant concern. No issues with the projected Salt Batch 4 strategy are identified. This report describes the laboratory results of Salt (Macro)Batch 4 confirmatory sample. These results will be used by Tank Farm Engineering for their blend calculations. This work was specified by Technical Task Request (TTR) and by Task Technical and Quality Assurance Plan (TTQAP).

  7. Tank Vapor Sampling and Analysis Data Package for Tank 241-Z-361 Sampled 09/22/1999 and 09/271999 During Sludge Core Removal

    SciTech Connect

    VISWANATH, R.S.

    1999-12-29

    This data package presents sampling data and analytical results from the September 22 and 27, 1999, headspace vapor sampling of Hanford Site Tank 241-2-361 during sludge core removal. The Lockheed Martin Hanford Corporation (LMHC) sampling team collected the samples and Waste Management Laboratory (WML) analyzed the samples in accordance with the requirements specified in the 241-2361 Sludge Characterization Sampling and Analysis Plan, (SAP), HNF-4371, Rev. 1, (Babcock and Wilcox Hanford Corporation, 1999). Six SUMMA{trademark} canister samples were collected on each day (1 ambient field blank and 5 tank vapor samples collected when each core segment was removed). The samples were radiologically released on September 28 and October 4, 1999, and received at the laboratory on September 29 and October 6, 1999. Target analytes were not detected at concentrations greater than their notification limits as specified in the SAP. Analytical results for the target analytes and tentatively identified compounds (TICs) are presented in Section 2.2.2 starting on page 2B-7. Three compounds identified for analysis in the SAP were analyzed as TICs. The discussion of this modification is presented in Section 2.2.1.2.

  8. Thermal modeling of core sampling in flammable gas waste tanks. Part 2: Rotary-mode sampling

    SciTech Connect

    Unal, C.; Poston, D.; Pasamehmetoglu, K.O.; Witwer, K.S.

    1997-08-01

    The radioactive waste stored in underground storage tanks at Hanford site includes mixtures of sodium nitrate and sodium nitrite with organic compounds. The waste can produce undesired violent exothermic reactions when heated locally during the rotary-mode sampling. Experiments are performed varying the downward force at a maximum rotational speed of 55 rpm and minimum nitrogen purge flow of 30 scfm. The rotary drill bit teeth-face temperatures are measured. The waste is simulated with a low thermal conductivity hard material, pumice blocks. A torque meter is used to determine the energy provided to the drill string. The exhaust air-chip temperature as well as drill string and drill bit temperatures and other key operating parameters were recorded. A two-dimensional thermal model is developed. The safe operating conditions were determined for normal operating conditions. A downward force of 750 at 55 rpm and 30 scfm nitrogen purge flow was found to yield acceptable substrate temperatures. The model predicted experimental results reasonably well. Therefore, it could be used to simulate abnormal conditions to develop procedures for safe operations.

  9. Characterization, Leaching, and Filtration Testing for Bismuth Phosphate Sludge (Group 1) and Bismuth Phosphate Saltcake (Group 2) Actual Waste Sample Composites

    SciTech Connect

    Lumetta, Gregg J.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn; Edwards, Matthew K.; Fiskum, Sandra K.; Hallen, Richard T.; Jagoda, Lynette K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Sinkov, Sergey I.; Snow, Lanee A.

    2009-02-19

    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.() The test 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 waste-testing program included homogenizing the samples by group, characterizing the solids and aqueous phases, and performing parametric leaching tests. Two of the eight defined groups—bismuth phosphate sludge (Group 1) and bismuth phosphate saltcake (Group 2)—are the subjects of this report. The Group 1 waste was anticipated to be high in phosphorus and was implicitly assumed to be present as BiPO4 (however, results presented here indicate that the phosphate in Group 1 is actually present as amorphous iron(III) phosphate). The Group 2 waste was also anticipated to be high in phosphorus, but because of the relatively low bismuth content and higher aluminum content, it was anticipated that the Group 2 waste would contain a mixture of gibbsite, sodium phosphate, and aluminum phosphate. Thus, the focus of the Group 1 testing was on determining the behavior of P removal during caustic leaching, and the focus of the Group 2 testing was on the removal of both P and Al. 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.

  10. C-104 Solid Phase Characterization of Sample 4C-13-1 From Tank 241-C-104 Closure Sampling Event

    SciTech Connect

    Cooke, Gary A.; Pestovich, John A.

    2013-06-12

    One solid grab sample from closure sampling in Riser 7 of tank 214-C-I04 (C-I04) was examined to determine the solid phases that were present. The sample was analyzed using X-ray diffraction (XRD) and scanning electron microscopy (SEM). The purpose of this analysis was to see if the presence of hydrated phases could provide a possible explanation for the high moisture content obtained from thermogravimetric analysis (TGA).

  11. Characterization of the SRNL-Washed tank 51 sludge batch 9 qualification sample

    SciTech Connect

    Pareizs, J. M.

    2016-01-01

    Savannah River National Laboratory (SRNL) personnel have been requested to qualify the next sludge batch (Sludge Batch 9 – SB9) for processing at the Defense Waste Processing Facility (DWPF). To accomplish this task, Savannah River Remediation (SRR) sent SRNL a 3-L sample of Tank 51H slurry to be characterized, washed, and then used in a lab-scale demonstration of the DWPF flowsheet (after combining with Tank 40H sludge). SRNL has washed the Tank 51H sample per the Tank Farm washing strategy as of October 20, 2015. A part of the qualification process is extensive radionuclide and chemical characterization of the SRNL-washed Tank 51H slurry. This report documents the chemical characterization of the washed slurry; radiological characterization is in progress and will be documented in a separate report. The analytical results of this characterization are comparable to the Tank Farm projections. Therefore, it is recommended that SRNL use this washed slurry for the ongoing SB9 qualification activities.

  12. Tank 214-AW-105, grab samples, analytical results for the finalreport

    SciTech Connect

    Esch, R.A.

    1997-02-20

    This document is the final report for tank 241-AW-105 grab samples. Twenty grabs samples were collected from risers 10A and 15A on August 20 and 21, 1996, of which eight were designated for the K Basin sludge compatibility and mixing studies. This document presents the analytical results for the remaining twelve samples. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DO). The results for the previous sampling of this tank were reported in WHC-SD-WM-DP-149, Rev. 0, 60-Day Waste Compatibility Safety Issue and Final Results for Tank 241-A W-105, Grab Samples 5A W-95-1, 5A W-95-2 and 5A W-95-3. Three supernate samples exceeded the TOC notification limit (30,000 microg C/g dry weight). Appropriate notifications were made. No immediate notifications were required for any other analyte. The TSAP requested analyses for polychlorinated biphenyls (PCB) for all liquids and centrifuged solid subsamples. The PCB analysis of the liquid samples has been delayed and will be presented in a revision to this document.

  13. Analysis of Tank 35H Samples in Support of Salt Batch Planning

    SciTech Connect

    Hay, M. S.; Coleman, C. J.; Diprete, D. P.

    2015-04-30

    Savannah River Remediation obtained three samples from different heights within Tank 35H. The samples were analyzed by Savannah River National Laboratory to support Salt Batch planning. The results from the analysis indicate the compositions of the three samples show increasing concentrations for most analytes going from HTF-35-15-17 through HTF-35-15-19 corresponding to successively deeper sampling locations. The data indicate some stratification within the tank. The plutonium and Sr-90 concentrations measured in the filtered samples were slightly lower than in the decanted (unfiltered) samples. The difference in the results for the filtered and unfiltered samples likely lies within the expected uncertainty for the measurement, but may indicate that filtration removed a small amount of suspended material from the samples.

  14. Task Technical and Quality Assurance Plan for the Characterization of Tank 25F Saltcake Core Samples

    SciTech Connect

    Martino, C

    2005-08-15

    The Department of Energy (DOE) recognizes the need for the characterization of High-Level Waste (HLW) saltcake in the Savannah River Site (SRS) F- and H-area tank farms to support upcoming salt processing activities. As part of the enhanced characterization efforts, Tank 25F will be sampled and the samples analyzed at the Savannah River National Laboratory (SRNL). This Task Technical and Quality Assurance Plan documents the planned activities for the physical, chemical, and radiological analysis of the Tank 25F saltcake core samples. This plan does not cover other characterization activities that do not involve core sample analysis and it does not address issues regarding sampling or sample transportation. The objectives of this report are: (1) Provide information useful in projecting the composition of dissolved salt batches by quantifying important components (such as actinides, {sup 137}Cs, and {sup 90}Sr) on a per batch basis. This will assist in process selection for the treatment of salt batches and provide data for the validation of dissolution modeling. (2) Determine the properties of the heel resulting from dissolution of the bulk saltcake. Also note tendencies toward post-mixing precipitation. (3) Provide a basis for determining the number of samples needed for the characterization of future saltcake tanks. Gather information useful towards performing characterization in a manner that is more cost and time effective.

  15. Double Shell Tank (DST) Ventilation System Vapor Sampling and Analysis Plan

    SciTech Connect

    SASAKI, L.M.

    2000-06-08

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples from the primary ventilation systems of the AN, AP, AW, and AY/AZ tank farms. Sampling will be performed in accordance with Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis (Air DQO) (Mulkey 1999). The sampling will verify if current air emission estimates used in the permit application are correct and provide information for future air permit applications. Vapor samples will be obtained from tank farm ventilation systems, downstream from the tanks and upstream of any filtration. Samples taken in support of the DQO will consist of SUMMA{trademark} canisters, triple sorbent traps (TSTs), sorbent tube trains (STTs), polyurethane foam (PUF) samples. Particulate filter samples and tritium traps will be taken for radiation screening to allow the release of the samples for analysis. The following sections provide the general methodology and procedures to be used in the preparation, retrieval, transport, analysis, and reporting of results from the vapor samples.

  16. Tank 241-AZ-102 Privatization Push Mode Core Sampling and Analysis Plan

    SciTech Connect

    RASMUSSEN, J.H.

    1999-08-02

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for samples obtained from tank 241-AZ-102. The purpose of this sampling event is to obtain information about the characteristics of the contents of 241-AZ-102 required to satisfy the Data Quality Objectives For TWRS Privatization Phase I: Confirm Tank TIS An Appropriate Feed Source For High-Level Waste Feed Batch X(HLW DQO) (Nguyen 1999a), Data Quality Objectives For TWRS Privatization Phase 1: Confirm Tank TIS An Appropriate Feed Source For Low-Activity Waste Feed Batch X (LAW DQO) (Nguyen 1999b), Low Activity Waste and High Level Waste Feed Data Quality Objectives (L&H DQO) (Patello et al. 1999) and Characterization Data Needs for Development, Design, and Operation of Retrieval Equipment Developed through the Data Quality Objective Process (Equipment DQO) (Bloom 1996). The Tank Characterization Technical Sampling Basis document (Brown et al. 1998) indicates that these issues, except the Equipment DQO apply to tank 241-AZ-102 for this sampling event. The Equipment DQO is applied for shear strength measurements of the solids segments only. Poppiti (1999) requires additional americium-241 analyses of the sludge segments. Brown et al. (1998) also identify safety screening, regulatory issues and provision of samples to the Privatization Contractor(s) as applicable issues for this tank. However, these issues will not be addressed via this sampling event. Reynolds et al. (1999) concluded that information from previous sampling events was sufficient to satisfy the safety screening requirements for tank 241 -AZ-102. Push mode core samples will be obtained from risers 15C and 24A to provide sufficient material for the chemical analyses and tests required to satisfy these data quality objectives. The 222-S Laboratory will extrude core samples, composite the liquids and solids, perform chemical analyses

  17. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford waste tank 241-S-101: Results from samples collected on 06/06/96

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-S-101. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained. Analyte concentrations were based on analytical results and sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed.

  18. TANK 26F SUPERNATANT AND 2F EVAPORATOR EDUCTOR PUMP SAMPLE CHARACTERIZATION RESULTS

    SciTech Connect

    King, W.; Hay, M.; Coleman, C.

    2011-08-23

    In an effort to understand the reasons for system plugging problems in the SRS 2F evaporator, supernatant samples were retrieved from the evaporator feed tank (Tank 26F) and solids were collected from the evaporator eductor feed pump for characterization. The variable depth supernatant samples were retrieved from Tank 26F in early December of 2010 and samples were provided to SRNL and the F/H Area laboratories for analysis. Inspection and analysis of the samples at SRNL was initiated in early March of 2011. During the interim period, samples were frequently exposed to temperatures as low as 12 C with daily temperature fluctuations as high as 10 C. The temperature at the time of sample collection from the waste tank was 51 C. Upon opening the supernatant bottles at SRNL, many brown solids were observed in both of the Tank 26F supernatant samples. In contrast, no solids were observed in the supernatant samples sent to the F/H Area laboratories, where the analysis was completed within a few days after receipt. Based on these results, it is believed that the original Tank 26F supernatant samples did not contain solids, but solids formed during the interim period while samples were stored at ambient temperature in the SRNL shielded cells without direct climate control. Many insoluble solids (>11 wt. % for one sample) were observed in the Tank 26F supernatant samples after three months of storage at SRNL which would not dissolve in the supernatant solution in two days at 51 C. Characterization of these solids along with the eductor pump solids revealed the presence of sodium oxalate and clarkeite (uranyl oxyhydroxide) as major crystalline phases. Sodium nitrate was the dominant crystalline phase present in the unwashed Eductor Pump solids. Crystalline sodium nitrate may have formed during the drying of the solids after filtration or may have been formed in the Tank 26F supernatant during storage since the solution was found to be very concentrated (9-12 M Na

  19. Results For The First Quarter 2012 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminant Results

    SciTech Connect

    Bannochie, C. J.

    2012-07-16

    This report details the chemical and radionuclide contaminant results for the characterization of the 2012 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this memorandum: The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted; The reported detection limit for {sup 94}Nb is above the requested limit but below the estimated limit; {sup 247}Cm and {sup 249}Cf are above the requested limits. However, they are below the limits established; The reported detection limit for Norpar 13 is greater than the limit from the WAC; The reported detection limit for Isopar L is greater than the limit from WAC; Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples; The values reported in this report are the concentrations in the sub-sample as detected by the instrument, however, the results may not accurately represent the concentrations of the analytes in Tank 50; The low insoluble solids content increases the measurement uncertainty for insoluble species.

  20. Tank vapor characterization project - Tank 241-U-112 headspace gas and vapor characterization: Results for homogeneity samples collected on December 6, 1996

    SciTech Connect

    Sklarew, D.S.; Pool, K.H.; Evans, J.C.; Hayes, J.C.

    1997-09-01

    This report presents the results of analyses of samples taken from the headspace of waste storage tank 241-U-112 (Tank U-112) at the Hanford Site in Washington State. Samples were collected to determine the homogeneity of selected inorganic and organic headspace constitutents. Two risers (Riser 3 and Riser 6) were sampled at three different elevations (Bottom, Middle, and Top) within the tank. Tank headspace samples were collected by SGN Eurisys Service Corporation (SESC) and were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Ammonia was determined to be above the immediate notification limit specified by the sampling and analysis plan.

  1. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, Caustic Wash Tank And Caustic Storage Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 6 Operations

    SciTech Connect

    Peters, T. B.

    2014-01-02

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Caustic Storage Tank (CST) samples from the Interim Salt Disposition Project (ISDP) Salt Batch (“Macrobatch”) 6 have been analyzed for 238Pu, 90Sr, 137Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The Pu, Sr, and Cs results from the current Macrobatch 6 samples are similar to those from comparable samples in previous Macrobatch 5. In addition the SEHT and DSSHT heel samples (i.e. ‘preliminary’) have been analyzed and reported to meet NGS Demonstration Plan requirements. From a bulk chemical point of view, the ICPES results do not vary considerably between this and the previous samples. The titanium results in the DSSHT samples continue to indicate the presence of Ti, when the feed material does not have detectable levels. This most likely indicates that leaching of Ti from MST has increased in ARP at the higher free hydroxide concentrations in the current feed.

  2. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, Caustic Wash Tank And Caustic Storage Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 6 Operations

    SciTech Connect

    Peters, T. B.

    2013-10-01

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Caustic Storage Tank (CST) samples from several of the ''microbatches'' of Integrated Salt Disposition Project (ISDP) Salt Batch (''Macrobatch'') 6 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The results from the current microbatch samples are similar to those from comparable samples in Macrobatch 5. From a bulk chemical point of view, the ICPES results do not vary considerably between this and the previous macrobatch. The titanium results in the DSSHT samples continue to indicate the presence of Ti, when the feed material does not have detectable levels. This most likely indicates that leaching of Ti from MST in ARP continues to occur. Both the CST and CWT samples indicate that the target Free OH value of 0.03 has been surpassed. While at this time there is no indication that this has caused an operational problem, the CST should be adjusted into specification. The {sup 137}Cs results from the SRNL as well as F/H lab data indicate a potential decline in cesium decontamination factor. Further samples will be carefully monitored to investigate this.

  3. Results Of Initial Analyses Of The Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect

    Peters, T. B.; Washington, A. L. II

    2013-07-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Salt (Macro) Batch 7 for the Interim Salt Disposition Program (ISDP) through ARP/MCU. This document reports the initial results of the analyses of samples of Tank 21H. Further results on the chemistry and other tests will be issued in the future. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. Based upon a SRNL settling test, the solids should settle well within the months-long settling period to be employed in Tank 21H. However, SRNL recommends analyzing the solids to provide input to OLI modeling in order to evaluate the impacts of these solids to present and future salt batches.

  4. RESULTS FOR THE FOURTH QUARTER 2010 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M

    2011-02-22

    This report details the chemical and radionuclide contaminant results for the characterization of the 2010 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limits for {sup 94}Nb, {sup 247}Cm and {sup 249}Cf are above the requested limits from Reference 2. However, they are below the limits established in Reference 3. (3) There is an estimated concentration of trimethylbenzene (2.25 mg/L). This is not a WAC analyte, but it is the first time this organic compound has been detected in a quarterly WAC sample from Tank 50. (4) The reported detection limit for Norpar 13 is greater than the limit from Table 4 and Attachment 8.2 of the WAC. (5) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC. (6) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately represent the concentrations of the analytes in Tank 50.

  5. Results For The First Quarter 2013 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants

    SciTech Connect

    Bannochie, C. J.

    2013-05-14

    This report details the chemical and radionuclide contaminant results for the characterization of the 2013 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: SRR WAC targets or limits were met for all analyzed chemical and radioactive contaminates unless noted in this section; {sup 59}Ni, {sup 94}Nb, {sup 247}Cm, {sup 249}Cf, and {sup 251}Cf are above the requested SRR target concentrations. However, they are below the detection limits established by SRNL; Norpar 13 and Isopar L have higher detection limits compared with the Saltstone WAC. The data provided in this report is based upon the concentrations in the sub-sample, and due to the limited solubility in aqueous solution, may not represent the concentrations of the analytes in Tank 50; and, The low insoluble solids content increases the measurement uncertainty for insoluble species.

  6. Sampling and Analysis Plan for Tank 241-AP-108 Waste in Support of Evaporator Campaign 2000-1

    SciTech Connect

    RASMUSSEN, J.H.

    2000-02-28

    This Tank Sampling and Analysis Plan (TSAP) identifies sample collection, laboratory analysis, quality assurance/quality control (QA/QC), and reporting objectives for the characterization of tank 241-AP-108 waste. Technical bases for these objectives are specified in the 242-A Evaporator Data Quality Objectives (Bowman 2000 and Von Bargen 1998) and 108-AP Tank Sampling Requirements in Support of Evaporator Campaign 2000-1 (Le 2000). Evaporator campaign 2000-1 will process waste from tank 241-AP-108 in addition to that from tank 241-AP-107. Characterization results will be used to support the evaporator campaign currently planned for early fiscal year 2000. No other needs (or issues) requiring data for this tank waste apply to this sampling event.

  7. Strontium and Actinides Removal from Savannah River Site Actual Waste Samples by Freshly Precipitated Manganese Oxide

    SciTech Connect

    Barnes, M.J.

    2003-10-30

    The authors investigated the performance of freshly precipitated manganese oxide and monosodium titanate (MST) for the removal of strontium (Sr) and actinides from actual high-level waste. Manganese oxide precipitation occurs upon addition of a reductant such as formate (HCO2-) or peroxide (H2O2) to a waste solution containing permanganate (MnO4-). Tests described in this document address the capability of manganese oxide treatment to remove Rs, Pu, and Np from actual high-level waste containing elevated concentrations of Pu. Additionally, tests investigate MST (using two unique batches) performance with the same waste for direct comparison to the manganese oxide performance.

  8. Sampling and Analysis Plan for Flammable Gases in Inactive Miscellaneous Underground Storage Tanks

    SciTech Connect

    NGUYEN, D.M.

    2000-02-01

    This sampling and analysis plan (SAP) identifies the field measurements for a screening of flammable gases in the vapor space of the inactive miscellaneous underground storage tanks (IMUSTs) currently assigned to the River Protection Project (RPP). If a measurement exceeds 25% of the lower flammability limit (LFL), vapor grab samples will be collected for laboratory analysis. This SAP also specifies the sample collection, laboratory analysis, quality assurance/quality control (QA/QC), and reporting objectives for grab sampling. Technical bases for the sampling objectives are provided in the Tank Safety Screening Data Quality Objectives (Dukelow et al 1995). The screening data will be used to determine if additional data are needed to support closure of a flammable gas unreviewed safety question for these facilities.

  9. Sampling and analyses plan for tank 103 at the 219-S waste handling facility

    SciTech Connect

    FOWLER, K.D.

    1999-06-23

    This document describes the sampling and analysis activities associated with taking a Resource Conservation and Recovery Act (RCRA) protocol sample of the waste from Tank 103 at the 21 9-S Waste Handling Facility treatment storage, andlor disposal (TSD) unit at the 2224 Laboratory complex. This sampling and analyses is required based on negotiations between the State of Washington Department of Ecology (Ecology) and the Department of Energy, Richland Operations, (RL) in letters concerning the TPA Change Form M-32-98-01. In a letter from George H. Sanders, RL to Moses N. Jaraysi, Ecology, dated January 28,1999, it was noted that ''Prior to the Tank 103 waste inventory transfer, a RCRA protocol sample of the waste will be obtained and tested for the constituents contained on the Part A, Form 3 Permit Application for the 219-S Waste Handling Facility.'' In the April 2, 1999 letter, from Brenda L. Becher-Khaleel, Ecology to James, E. Rasmussen, RL, and William O. Adair, FDH, Ecology states that the purpose of these analyses is to provide information and justification for leaving Tank 103 in an isolated condition in the 2194 TSD unit until facility closure. The data may also be used at some future date in making decisions regarding closure methodology for Tank 103. Ecology also notes that As Low As Reasonably Achievable (ALARA) concerns may force deviations from some SW-846 protocol. Every effort will be made to accommodate requirements as specified. Deviations from SW-846 will be documented in accordance with HASQARD.

  10. Analysis of Copper in the In-Tank Precipitation Process Caustic Samples

    SciTech Connect

    Tovo, L.L.; Boyce, W.T.

    1996-12-12

    Inductively Coupled Plasma Emission Spectroscopy (ICPES) and Inductively Coupled Plasma Mass Spectrometry (ICPMS) procedures for measuring Cu in In-Tank Precipitation (ITP) caustic samples have been tested and implemented in the Analytical Development Section at the Savannah River Technology Center.

  11. Sampling and analysis plan for site assessment during the closure or replacement of nonradioactive underground storage tanks

    SciTech Connect

    Gitt, M.J.

    1990-08-01

    The Tank Management Program is responsible for closure or replacement of nonradioactive underground storage tanks throughout the Idaho National Engineering Laboratory (INEL). A Sampling and Analysis Plan (SAP) has been developed that complies with EPA regulations and with INEL Tank Removal Procedures for sampling activities associated with site assessment during these closure or replacement activities. The SAP will ensure that all data are valid, and it also will function as a Quality Assurance Project Plan. 18 refs., 8 figs., 11 tabs.

  12. Headspace vapor characterization of Hanford Waste Tank 241-U-112: Results from samples collected on 7/09/96

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-112 at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company.

  13. Waste compatibility safety issues and final results for tank 241-T-110 push mode samples

    SciTech Connect

    Nuzum, J.L.

    1997-05-15

    This document is the final laboratory report for Tank 241-T-110. Push mode core segments were removed from risers 2 and 6 between January 29, 1997, and February 7, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-T-110 Push Mode Core Sampling and analysis Plan (TSAP) and Safety Screening Data Quality Objective (DQO). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DSC) analyses exceeded the notification limits stated in DQO.

  14. Results For The Fourth Quarter 2012 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants

    SciTech Connect

    Bannochie, C. J.

    2013-02-05

    This report details the chemical and radionuclide contaminant results for the characterization of the 2012 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC).Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: The concentration of the reported chemical and radioactive contaminants were less than their respective WAC Limits and Targets, unless noted in this section; Norpar 13 and Isopar L have higher detection limits compared with the Saltstone WAC. The data provided in this report is based upon the concentrations in the sub-sample, and due to the limited solubility in aqueous solution, may not represent the concentrations of the analytes in Tank 50; Diisooctyl adipate (or diisooctyl hexanedioate) and 5-methyl-3-hexanol, plasticizers, were measured at 1.30E+00 mg/L and 3.00E+00 mg/L, respectively, in one of two replicate measurements conducted on an at-depth sample. The organic analysis of the at-depth sample was conducted at the request of SRR. These analytes were below the detection limits for the surface sample; and, The low insoluble solids content increases the measurement uncertainty for insoluble species.

  15. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Tank 241-S-107: Results from samples collected on 06/18/96

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-S-107 (Tank S-107) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National. Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  16. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank U-204, Results from samples collected on August 8, 1995

    SciTech Connect

    Clauss, T.W.; Evans, J.C.; McVeety, B.D.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Ligotke, M.W.

    1995-11-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-204 (Tank U-204) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank-farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the results is listed. Detailed descriptions of the analytical results appear in the text.

  17. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank 241-S-109: Results from samples collected on 06/04/96

    SciTech Connect

    Pool, K.H.; Thomas, B.L.; Evans, J.C.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-S-109 (Tank S-109) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  18. Tool for sampling oil from electric distribution transformer tanks for PCB contamination

    SciTech Connect

    Canfield, M.H.

    1992-07-21

    This patent describes a tool for sampling oil from an electric distribution transformer tank of the type which includes a ground lug nut containing an interiorly threaded hollow shaft rigidly attached to a wall of the tank. It comprises a threaded body portion adapted for threadable insertion into nut shaft, punch means attached to the body portion for punching a hole in the tank wall as the body portion is threadably advanced in the lug nut shaft, a wrenchable fitting for rotating the body portion to advance and retract the body portion in the lug nut shaft, and shaft means defined by the punch means and body portion extending between a first opening on the punch means and a second opening on the body portion for providing an oil flow path between the openings upon application of a suction through the second opening.

  19. Tank vapor characterization project. Headspace vapor characterization of Hanford waste tank 241-BY-108: Second comparison study results from samples collected on 3/28/96

    SciTech Connect

    Thomas, B.L.; Pool, K.H.; Evans, J.C.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of waste storage tank 241-BY-108 (Tank BY-108) at the Hanford Site in Washington State. The results described in this report is the second in a series comparing vapor sampling of the tank headspace using the Vapor Sampling System (VSS) and In Situ Vapor Sampling (ISVS) system without high efficiency particulate air (HEPA) prefiltration. The results include air concentrations of water (H{sub 2}O) and ammonia (NH{sub 3}), permanent gases, total non-methane organic compounds (TO-12), and individual organic analytes collected in SUMMA{trademark} canisters and on triple sorbent traps (TSTs). Samples were collected by Westinghouse Hanford Company (WHC) and analyzed by Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volume measurements provided by WHC.

  20. Tank vapor characterization project: Headspace vapor characterization of Hanford Waste Tank 241-S-102: Second comparison study results from samples collected on 04/04/96

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.J.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of waste storage tank 241-S-102 (Tank S-102) at the Hanford Site in Washington State. The results described in this report is the second in a series comparing vapor sampling of the tank headspace using the Vapor Sampling System (VSS) and In Situ Vapor Sampling (ISVS) system without high efficiency particulate air (HEPA) prefiltration. The results include air concentrations of water (H{sub 2}O) and ammonia (NH{sub 3}), permanent gases, total non-methane organic compounds (TO-12), and individual organic analytes collected in SUMMA{trademark} canisters and on triple sorbent traps (TSTs). Samples were collected by Westinghouse Hanford Company (WHC) and analyzed by Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volume measurements provided by WHC.

  1. Tank vapor characterization project - headspace vapor characterization of Hanford Waste Tank 241-C-107: Second comparison study results from samples collected on 3/26/96

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of waste storage tank 241-C-107 (Tank C-107) at the Hanford Site in Washington State. The results described in this report is the second in a series comparing vapor sampling of the tank headspace using the Vapor Sampling System (VSS) and In Situ Vapor Sampling (ISVS) system without high efficiency particulate air (HEPA) prefiltration. The results include air concentrations of water (H{sub 2}O) and ammonia (NH{sub 3}), permanent gases, total non-methane organic compounds (TO-12), and individual organic analytes collected in SUMMA{trademark} canisters and on triple sorbent traps (TSTs). Samples were collected by Westinghouse Hanford Company (WHC) and analyzed by Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volume measurements provided by WHC.

  2. Tank Vapor Characterization Project -- Headspace vapor characterization of Hanford waste Tank 241-C-107: Results from samples collected on 01/17/96

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1996-07-01

    This report describes the analytical results of vapor samples taken from the headspace of waste storage tank 241-C-107 (Tank C-107) at the Hanford Site in Washington State. The results described in this report were obtained to compare vapor sampling of the tank headspace using the Vapor Sampling System (VSS) and In Situ Vapor Sampling (ISVS) system with and without high efficiency particulate air (HEPA) prefiltration. The results include air concentrations of water (H{sub 2}O) and ammonia (NH{sub 3}), permanent gases, total non-methane hydrocarbons (TO-12), and individual organic analytes collected in SUMMA{trademark} canisters and on triple sorbent traps (TSTs). Samples were collected by Westinghouse Hanford Company (WHC) and analyzed by Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volume measurements provided by WHC.

  3. Vapor space characterization of waste Tank 241-BY-111: Results from samples collected on November 15, 1994

    SciTech Connect

    Lucke, R.B.; Ligotke, M.W.; McVeety, B.D.

    1995-06-01

    This report describes results of the analyses of tank-headspace samples taken from the Hanford waste Tank 241-BY-111 (referred to as Tank By-111). Pacific Northwest Laboratory (PNL) contracted with Westinghouse Hanford company (WHC) to provide sampling devices and to analyze inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The target analytes for TO- 14 compounds were extended to include 14 analytes identified by the Toxicological Review Panel for Tank C-103 and reported by Mahlum et al. (1994). Program management included these analytes for future tank analyses as identified in the fiscal year work plan. This plan is attached to a letter dated 9/30/94 and addressed to Mr. T.J. Kelly of WHC. The plan also requires PNL to analyze for the permanent gases as shown in Table 3.7. The sample job was designated S4083, and samples wee collected by WHC on November 16, 1994, using the vapor sampling system (VSS). The results of the analyses are expected to be used to estimate the potential toxicity of tank-headspace gas as described in Data Quality Objectives for Generic In-Tank Health and Safety Vapor Issue Resolution, WHC-SD-WM-DQO-002, Rev. 0.

  4. RESULTS FOR THE SECOND QUARTER 2010 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.; Bibler, N.

    2010-08-04

    This report details the chemical and radionuclide contaminant results for the characterization of the 2010 Second Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC).1 Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limits for {sup 94}Nb and {sup 144}Ce are above both the established and requested limits from References 4 and 6. (3) The reported detection limits for {sup 247}Cm and {sup 249}Cf are above the requested limits from Reference 4. However, they are below the limits established in Reference 6. (4) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC. (5) A measurable concentration of Norpar 13 is present in the sample. The reported concentration is greater than the requested limit from Table 4 and Attachment 8.2 of the WAC. (6) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately represent the concentrations of the analytes in Tank 50. (7) The detection limit for isopropanol has been lowered from 0.5 mg/L to 0.25 mg/L{sup 7}. This revised limit now satisfies the limit in Table 4 of the WAC.

  5. RESULTS FOR THE FOURTH QUARTER 2013 TANK 50 WAC SLURRY SAMPLE CHEMICAL AND RADIONUCLIDE CONTAMINANTS

    SciTech Connect

    Bannochie, C.

    2014-04-01

    This report details the chemical and radionuclide contaminant results for the characterization of the 2013 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report:  SRR WAC targets or limits were met for all analyzed chemical and radioactive contaminants unless noted in this section.  {sup 59}Ni, {sup 94}Nb, {sup 247}Cm, {sup 249}Cf, and {sup 251}Cf are above the requested SRR target concentrations. However, they are below the detection limits established by SRNL.  Norpar 13 and Isopar L have higher detection limits compared with the Saltstone WAC. The data provided in this report is based upon the concentrations in the sub-sample, and due to the limited solubility of these materials in aqueous solution, may not represent the concentrations of the analytes in Tank 50.  The low insoluble solids content increases the measurement uncertainty for insoluble species. The semivolatile organic analysis (SVOA) method employed in the measurement of Norpar 13 and tributyl phosphate (TBP) has resulted in the erroneous reporting of a variety of small chain alcohols, including 4-methyl-3-hexanol and 5-methyl-3-hexanol, in previous quarterly sample reports. It has now been determined that these alcohols are an artifact of the sample preparation. Further work is being conducted in SRNL to delineate the conditions that produce these alcohols, and these findings will be reported separately.

  6. 12 CFR Appendix M3 to Part 226 - Sample Calculations of Generic Repayment Estimates and Actual Repayment Disclosures

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 12 Banks and Banking 3 2010-01-01 2010-01-01 false Sample Calculations of Generic Repayment Estimates and Actual Repayment Disclosures M3 Appendix M3 to Part 226 Banks and Banking FEDERAL RESERVE SYSTEM (CONTINUED) BOARD OF GOVERNORS OF THE FEDERAL RESERVE SYSTEM TRUTH IN LENDING (REGULATION Z)...

  7. Sampling and analysis of the inactive waste tanks TH-2, WC-1, and WC-15. Environmental Restoration Program

    SciTech Connect

    Autrey, J.W.; Keller, J.M.; Griest, W.H.; Botts, J.L.; Schenley, R.L.; Sipe, M.A.

    1992-02-01

    Thirty-eight inactive liquid low-level radioactive waste tanks are currently managed by the Environmental Restoration Program of Oak Ridge National Laboratory. The contents of these tanks are to be characterized in preparation for future corrective actions and remediation activities as part of compliance with the pending Federal Facility Agreement for the Oak Ridge Reservation. Twenty-nine of these tanks were sampled and analyzed in 1989. Three of the tanks (TH-2, WC-1, and WC-15) were not accessible from the surface and thus were not sampled until 1990. This report presents the sampling and analytical results of that campaign. All three tanks in this report had negligible regulatory organic compounds in the samples that were collected. There were no US Environmental Protection Agency (EPA) Target Compound List (TCL) constituents for volatile organics detected in any of the aqueous samples. The only semivolatile organics detected were 2-chlorophenol (52 {mu}g/L) in tank TH-2 and dichloroethane (14--15 {mu}g/L) and diethyl either (15--17 {mu}g/L) in tank WC-15. A thin oil layer was discovered floating on top of the aqueous contents in tank WC-15. The analysis of the oil layer detected no volatile organics and showed only one EPA TCL constituent, di-n-butylphthalate, at 1900 {mu}g/L. Low levels of Resource Conservation and Recovery Act (RCRA) metals were observed in the samples from tank TH-2, but only the mercury level exceeded the RCRA limit. Samples from tank WC-1 had elevated levels of the RCRA metals barium, chromium, and lead. There were also finely suspended particles in one of the samples from tank WC-1, which was filtered and analyzed separately. This solid fines have levels of transuranium elements {sup 238}Pu and {sup 241}Am high enough to classified as transuranic waste.

  8. Review of Analytes of Concern and Sample Methods for Closure of DOE High Level Waste Storage Tanks

    SciTech Connect

    Thomas, T.R.

    2002-05-06

    Sampling residual waste after tank cleaning and analysis for analytes of concern to support closure and cleaning targets of large underground tanks used for storage of legacy high level radioactive waste (HLW) at Department of Energy (DOE) sites has been underway since about 1995. The DOE Tanks Focus Area (TFA) has been working with DOE tank sites to develop new sampling plans, and sampling methods for assessment of residual waste inventories. This paper discusses regulatory analytes of concern, sampling plans, and sampling methods that support closure and cleaning target activities for large storage tanks at the Hanford Site, the Savannah River Site (SRS), the Idaho National Engineering and Environmental Laboratory (INEEL), and the West Valley Demonstration Project (WVDP).

  9. Review of Analytes of Concern and Sample Methods for Closure of DOE High Level Waste Storage Tanks

    SciTech Connect

    Thomas, Thomas Russell

    2002-08-01

    Sampling residual waste after tank cleaning and analysis for analytes of concern to support closure and cleaning targets of large underground tanks used for storage of legacy high level radioactive waste (HLW) at Department of Energy (DOE) sites has been underway since about 1995. The DOE Tanks Focus Area (TFA) has been working with DOE tank sites to develop new sampling plans, and sampling methods for assessment of residual waste inventories. This paper discusses regulatory analytes of concern, sampling plans, and sampling methods that support closure and cleaning target activities for large storage tanks at the Hanford Site, the Savannah River Site (SRS), the Idaho National Engineering and Environmental Laboratory (INEEL), and the West Valley Demonstration Project (WVDP).

  10. Comparison of vapor sampling system (VSS) and in situ vapor sampling (ISVS) methods on Tanks C-107, BY-108, and S-102. Revision 1

    SciTech Connect

    Huckaby, J.L.; Edwards, J.A.; Evans, J.C.

    1996-08-01

    This report discusses comparison tests for two methods of collecting vapor samples from the Hanford Site high-level radioactive waste tank headspaces. The two sampling methods compared are the truck-mounted vapor sampling system (VSS) and the cart-mounted in-situ vapor sampling (ISVS). Three tanks were sampled by both the VSS and ISVS methods from the same access risers within the same 8-hour period. These tanks have diverse headspace compositions and they represent the highest known level of several key vapor analytes.

  11. Tank 241-SY-102 January 2000 Compatibility Grab Samples Analytical Results for the Final Report [SEC 1 and 2

    SciTech Connect

    BELL, K.E.

    2000-05-11

    This document is the format IV, final report for the tank 241-SY-102 (SY-102) grab samples taken in January 2000 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank SY-102 samples were performed as directed in Comparability Grab Sampling and Analysis Plan for Fiscal Year 2000 (Sasaki 1999). No notification limits were exceeded. Preliminary data on samples 2SY-99-5, -6, and -7 were reported in ''Format II Report on Tank 241-SY-102 Waste Compatibility Grab Samples Taken in January 2000'' (Lockrem 2000). The data presented here represent the final results.

  12. Vapor space sampling of ferrocyanide tanks, Hanford Site, Richland, Washington. Environmental Assessment

    SciTech Connect

    Not Available

    1991-07-01

    Environmental assessment (EA), to assess environmental impacts associated with tank vapor space (dome) gas sampling of 24 Hanford Site single-shell waste tanks that contain ferrocyanide-nitrate compounds to determine whether or not the tanks contain flammable or toxic gases. The proposed action would be conducted using non-sparking materials, sparkless tools, and a portable containment shelter (greenhouse) and plastic ground cover. DOE needs to take this action to help define the required controls to prevent or mitigate the potential for an accident during future, more intrusive sampling of these tanks. Based on the evaluation in the EA (which examined the environmental impacts of the proposed action and reasonable alternatives), DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an Environmental Impact Statement is not required, and the Department is issuing this Finding of No Significant Impact (FONSI).

  13. Vapor space characterization of waste tank 241-BY-107: Results from samples collected on 10/26/94

    SciTech Connect

    Clauss, T.W.; Ligotke, M.W.; Pool, K.H.

    1995-10-01

    This report describes results of the analyses of tank-headspace samples taken from the Hanford waste Tank 241-BY-107 (referred to as Tank BY-107). Pacific Northwest Laboratory (PNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and to analyze inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The organic analytes for TO-14 compounds were extended to include 15 analytes identified by the Toxicological Review Panel for Tank C-103 and reported in Toxicological Evaluation of Analytes from Tank 241-C-103 PAE-10189. While these analytes are only of toxicological concern for Tank C-103, program management included these analytes for future tank analyses as identified in the fiscal year work plan. This plan is attached to a letter dated 9/30/94 and addressed to Mr. T. J. Kelly of WHC. The plan also requires PNL to analyze for the permanent gases as shown in Table 3.5. The sample job was designated S4077, and samples were collected by WHC on October 26, 1994, using the vapor sampling system (VSS). Sampling devices, including six sorbent trains (for inorganic analyses), and six SUMMA{trademark} canisters (for organic analyses) were supplied to the WHC sampling staff on October 24. Samples were taken (by WHC) from the tank headspace on October 26 and were returned to PNL from the field on November 8. Inorganic (sorbent trap) samples were delivered to PNL on chain of custody (COC) 008071. The SUMMA{trademark} canisters were delivered on COC 008070. Three SUMMA{trademark} canister samples were stored at the PNL 326/23B laboratory pending further instruction from WHC to send them to the Oregon Graduate Institute (OGI) for analysis.

  14. Evidence That Certain Waste Tank Headspace Vapor Samples Were Contaminated by Semivolatile Polymer Additives

    SciTech Connect

    Huckaby, James L.

    2006-02-09

    Vapor samples collected from the headspaces of the Hanford Site high-level radioactive waste tanks in 1994 and 1995 using the Vapor Sampling System (VSS) were reported to contain trace levels of phthalates, antioxidants, and certain other industrial chemicals that did not have a logical origin in the waste. This report examines the evidence these chemicals were sampling artifacts (contamination) and identifies the chemicals reported as headspace constituents that may instead have been contaminants. Specific recommendations are given regarding the marking of certain chemicals as suspect on the basis they were sampling manifold contaminants.

  15. RESULTS FOR THE FIRST QUARTER 2010 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.; Bibler, N.

    2010-05-05

    This report details the chemical and radionuclide contaminant results for the characterization of the 2010 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC. (3) The reported detection limits for {sup 59}Ni and {sup 94}Nb are above the requested limits from Reference 4. However, they are each below the limits established in Reference 6. (4) The reported detection limit for isopropanol is greater than the requested limit from Table 4 of the WAC. (5) The reported detection limits for 247Cm and 249Cf are above the requested limits from Reference 4. However, they are below the limits established in Reference 6. (6) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately represent the concentrations of the analytes in Tank 50.

  16. RESULTS FOR THE FIRST QUARTER 2012 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Bannochie, C.

    2012-06-06

    This report details the chemical and radionuclide contaminant results for the characterization of the 2012 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this memorandum: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section; (2) The reported detection limit for {sup 94}Nb is above the requested limit from Reference 2 but below the estimated limit in Reference 3; (3) {sup 247}Cm and {sup 249}Cf are above the requested limits from Reference 2. however, they are below the limits established in Reference 3; (4) The reported detection limit for Norpar 13 is greater than the limit from Table 4 and Attachment 8.2 of the WAC; (5) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC; (6) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples, the values reported in this report are the concentrations in the sub-sample as detected by the instrument; however, the results may not accurately represent the concentrations of the analytes in Tank 50; and (7) The low insoluble solids content increases the measurement uncertainty for insoluble species.

  17. RESULTS FOR THE THIRD QUARTER 2010 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.; Bibler, N.

    2010-12-09

    This report details the chemical and radionuclide contaminant results for the characterization of the 2010 Third Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (i) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (ii) The reported detection limits for {sup 94}Nb, {sup 247}Cm and {sup 249}Cf are above the requested limits from Reference 4. However, they are below the limits established in Reference 3. (iii) The reported detection limit for {sup 242m}Am is greater than the requested limit from Attachment 8.4 of the WAC. (iv) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC. (v) The reported concentration of Isopropanol is greater than the limit from Table 4 of the WAC. (vi) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately represent the concentrations of the analytes in Tank 50.

  18. Initial Investigation of Waste Feed Delivery Tank Mixing and Sampling Issues

    SciTech Connect

    Fort, James A.; Bamberger, Judith A.; Meyer, Perry A.; Stewart, Charles W.

    2007-10-01

    The Hanford tank farms contractor will deliver waste to the Waste Treatment Plant (WTP) from a staging double-shell tank. The WTP broadly classifies waste it receives in terms of “Envelopes,” each with different limiting properties and composition ranges. Envelope A, B, and C wastes are liquids that can include up to 4% entrained solids that can be pumped directly from the staging DST without mixing. Envelope D waste contains insoluble solids and must be mixed before transfer. The mixing and sampling issues lie within Envelope D solid-liquid slurries. The question is how effectively these slurries are mixed and how representative the grab samples are that are taken immediately after mixing. This report summarizes the current state of knowledge concerning jet mixing of wastes in underground storage tanks. Waste feed sampling requirements are listed, and their apparent assumption of uniformity by lack of a requirement for sample representativeness is cited as a significant issue. The case is made that there is not an adequate technical basis to provide such a sampling regimen because not enough is known about what can be achieved in mixing and distribution of solids by use of the baseline submersible mixing pump system. A combined mixing-sampling test program is recommended to fill this gap. Historical Pacific Northwest National Laboratory project and tank farms contractor documents are used to make this case. A substantial investment and progress are being made to understand mixing issues at the WTP. A summary of the key WTP activities relevant to this project is presented in this report. The relevant aspects of the WTP mixing work, together with a previously developed scaled test strategy for determining solids suspension with submerged mixer pumps (discussed in Section 3) provide a solid foundation for developing a path forward.

  19. Sampling and Analysis Plan for the Gunite and Associated Tanks Treatability Study, wall coring and scraping in Tanks W-3 and W-4 (North Tank Farm), Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-08-01

    This plan documents the procedures for collecting and analyzing wall core and wall scraping samples from Tanks W-3 and W-4 in the North Tank Farm. This is in support of the Comprehensive Environmental Response, Compensation, and Liability Act Treatability Study of the Gunite and Associated Tanks at ORNL. The sampling and analysis will be in concert with sludge retrieval and sluicing of the tanks. Wall scraping and wall core samples will be collected from each quadrant in each tank by using a scraping sampler and a coring drill deployed by the Houdini robot vehicle. Each sample will be labeled, transported to the Radioactive Materials Analytical Laboratory and analyzed for physical/radiological characteristics, including total activity, gross alpha, gross beta, radioactive Sr + Cs, and other alpha and gamma emitting radionuclides. The Data Quality Objectives process, based on US EPA guidance (EPA QA/G-4, Sept. 1994), was applied to identify the objectives of this sampling and analysis. Results of the analysis will be used to validate predictions of a Sr concrete diffusion model, estimate the amount of radioactivity remaining in the tank shells, provide information to correlate with measurements taken by the Gunite Tank Isotope Mapping Probe and the Characterization End Effector, and estimate the performance of the wall cleaning system.

  20. Tank waste remediation system (TWRS) privatization contractor samples waste envelope D material 241-C-106

    SciTech Connect

    Esch, R.A.

    1997-04-14

    This report represents the Final Analytical Report on Tank Waste Remediation System (TWRS) Privatization Contractor Samples for Waste Envelope D. All work was conducted in accordance with ''Addendum 1 of the Letter of Instruction (LOI) for TWRS Privatization Contractor Samples Addressing Waste Envelope D Materials - Revision 0, Revision 1, and Revision 2.'' (Jones 1996, Wiemers 1996a, Wiemers 1996b) Tank 241-C-1 06 (C-106) was selected by TWRS Privatization for the Part 1A Envelope D high-level waste demonstration. Twenty bottles of Tank C-106 material were collected by Westinghouse Hanford Company using a grab sampling technique and transferred to the 325 building for processing by the Pacific Northwest National Laboratory (PNNL). At the 325 building, the contents of the twenty bottles were combined into a single Initial Composite Material. This composite was subsampled for the laboratory-scale screening test and characterization testing, and the remainder was transferred to the 324 building for bench-scale preparation of the Privatization Contractor samples.

  1. Results Of Routine Strip Effluent Hold Tank And Decontaminated Salt Solution Hold Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 5 Operations

    SciTech Connect

    Peters, T. B.; Fondeur, F. F.

    2013-04-30

    Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the ''microbatches'' of Integrated Salt Disposition Project (ISDP) Salt Batch (''Macrobatch'') 5 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The results indicate good decontamination performance within process design expectations. While the data set is sparse, the results of this set and the previous set of results for Macrobatch 4 samples indicate generally consistent operations. The DSSHT samples show continued presence of titanium, likely from leaching of the monosodium titanate in the Actinide Removal process (ARP).

  2. CHARACTERIZATION AND EVALUATION OF CAUSTIC WASH TANK AND SOLVENT HOLD TANK SAMPLES FROM MCU FROM AUGUST TO SEPTEMBER 2011

    SciTech Connect

    Fondeur, F.; Fink, S.

    2012-08-01

    During processing of Salt Batches 3 and 4 in the Modular Caustic-Side Solvent Extraction Unit (MCU), the decontamination efficiency for cesium declined from historical values and from expectations based on laboratory testing. This report documents efforts to analyze samples of solvent and process solutions from MCU in an attempt to understand the cause of the reduced performance and to recommend mitigations. CWT Solutions from MCU from the time period of variable decontamination factor (DF) performance which covers from April 2011 to September 2011 (during processing of Salt Batch 4) were examined for impurities using chromatography and spectroscopy. The results indicate that impurities were found to be of two types: aromatic containing impurities most likely from Modifier degradation and aliphatic type impurities most likely from Isopar{reg_sign} L and tri-n-octylamine (TOA) degradation. Caustic washing the Solvent Hold Tank (SHT) solution with 1M NaOH improved its extraction ability as determined from {sup 22}Na uptake tests. Evidence from this work showed that pH variance in the aqueous solutions within the range of 1M nitric acid to 1.91M NaOH that contacted the solvent samples does not influence the analytical determination of the TOA concentration by GC-MS.

  3. Polychlorinated biphenyls (PCB) analysis report for solid sample from 219S tank 104

    SciTech Connect

    Ross, G.A.

    1998-03-27

    A sample of solids was obtained from tank 104 of 219S via a peristaltic pump equipped with a stainless steel tube and Norprenel tubing (Phthalate free). The sample obtained in a glass jar with Teflon 2 lid, was analyzed for PCBs as Aroclor mixtures. A soxhlet extraction procedure was used to extract the Aroclors from the sample. Analysis was performed using dual column confirmation gas chromatography/electron capture detection (GC/ECD). The extraction method closely follows SW-846 method 3540C and the analysis follows SW-846 method.

  4. Analysis of sampling plan options for tank 16H from the perspective of statistical uncertainty

    SciTech Connect

    Shine, E. P.

    2013-02-28

    This report develops a concentration variability model for Tank 16H in order to compare candidate sampling plans for assessing the concentrations of analytes in the residual material in the annulus and on the floor of the primary vessel. A concentration variability model is used to compare candidate sampling plans based on the expected upper 95% confidence limit (UCL95) for the mean. The result is expressed as a rank order of candidate sampling plans from lowest to highest expected UCL95, with the lowest being the most desirable from an uncertainty perspective.

  5. Evaporator Feed Qualification Analysis Of Tank 38H And 43H Samples: January 2010 Through April 2013

    SciTech Connect

    Martino, C. J.; Coleman, C. J.

    2013-08-21

    This report provides the results of analyses that focused on the chemical species that pertain to the sodium aluminosilicate formation potential for archived Tank 38H and 43H subsurface samples from January 2010 through April 2013. Analyses included warm acid strike preparation followed by analysis of silicon, aluminum, and sodium and water dilution preparation followed by analysis for anions. The Tank 43H and 38H supernatant liquid silicon measurements for the January 2010 through April 2013 time period exhibit a slight increasing trend. Over this time period, the silicon concentration in the Tank 43H and Tank 38H samples averaged 179 mg/L and 235 mg/L, respectively. Comparison of Tank 43H sample results from 2005 through April 2013 to the previously developed process control models indicates that the current formation of sodium aluminosilicate in the 2H system is due to the seeded direct precipitation of cancrinite and sodalite.

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

    SciTech Connect

    Pareizs, J.; Hay, M.

    2011-02-22

    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

  7. Engineering Task Plan for Development and Fabrication and Deployment of Nested Fixed Depth Fluidic Sampling and At Tank Analysis Systems

    SciTech Connect

    BOGER, R.M.

    2000-10-30

    This engineering task plan identifies the resources, responsibilities, and schedules for the development and deployment of a mobile, variable depth sampling system and an at-tank analysis system. The mobile, variable depth sampling system concept was developed after a cost assessment indicated a high cost for multiple deployments of the nested, fixed-depth sampling system. The sampling will provide double-shell tank (DST) staging tank waste samples for assuring the readiness of the waste for shipment to the LAW/HLW plant for treatment and immobilization. The at-tank analysis system will provide ''real-time'' assessments of the samples' chemical and physical properties. These systems support the Hanford Phase 1B vitrification project.

  8. Organic analysis of ambient samples collected near Tank 241-C-103: Results from samples collected on May 12, 1994

    SciTech Connect

    Clauss, T.W.; Ligotke, M.W.; McVeety, B.D.; Lucke, R.B.; Young, J.S.; McCulloch, M.; Fruchter, J.S.; Goheen, S.C.

    1995-06-01

    This report describes organic analyses results from ambient samples collected both upwind and through the vapor sampling system (VSS) near Hanford waste storage Tank 241-C-103 (referred to as Tank C-103). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed. Quantitative results were obtained for organic compounds. Five organic tentatively identified compounds (TICS) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, we looked for the 40 standard TO-14 analytes. We observed 39. Of these, only one was observed above the 2-ppbv calibrated instrument detection limit. Dichloromethane was above the detection limits using both methods, but the result from the TO-14 method is traceable to a standard gas mixture and is considered more accurate. Organic analytes were found only in the sample collected through the VSS, suggesting that these compounds were residual contamination from a previous sampling job. Detailed descriptions of the results appear in the text.

  9. Characterization and Leach Testing for REDOX Sludge and S-Saltcake Actual Waste Sample Composites

    SciTech Connect

    Fiskum, Sandra K.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Hubler, Timothy L.; Jagoda, Lynette K.; Jenson, Evan D.; Kozelisky, Anne E.; Lumetta, Gregg J.; MacFarlan, Paul J.; McNamara, Bruce K.; Peterson, Reid A.; Sinkov, Sergey I.; Snow, Lanee A.; Swoboda, Robert G.

    2008-07-10

    This report describes processing and analysis results of boehmite waste type (Group 5) and insoluble high Cr waste type (Group 6). The sample selection, compositing, subdivision, physical and chemical characterization are described. Extensive batch leach testing was conducted to define kinetics and leach factors of selected analytes as functions of NaOH concentration and temperature. Testing supports issue M-12 resolution for the Waste Treatment Plant.

  10. Tank Farm WM-182 and WM 183 Heel Slurry Samples PSD Results

    SciTech Connect

    Batcheller, Thomas Aquinas

    2000-09-01

    Particle size distribution (PSD) analysis of INTEC Tank Farm WM-182 and WM-183 heel slurry samples were performed using a modified Horiba LA-300 PSD analyzer at the RAL facility. There were two types of testing performed: typical PSD analysis, and setting rate testing. Although the heel slurry samples were obtained from two separate vessels, the particle size distribution results were quite similar. The slurry solids were from approximately a minimum particle size of 0.5 mm to a maximum of 230 mm-with about 90% of the material between 2-to-133 mm, and the cumulative 50% value at approximately 20 mm. This testing also revealed that high frequency sonication with an ultrasonic element may break-up larger particles in the WM-182 and WM-183 tank from heel slurries. This finding represents useful information regarding ultimate tank heel waste processing. Settling rate testing results were also fairly consistent with material from both vessels in that it appears that most of the mass of solids settle to an agglomerated, yet easily redispersed layer at the bottom. A dispersed and suspended material remained in the "clear" layer above the settled layer after about one-half an hour of settling time. This material had a statistical mode of approximately 5 mm and a maximum particle size of 30 mm.

  11. Tank Farm WM-182 and WM-183 Heel Slurry Samples PSD Results

    SciTech Connect

    Batcheller, T.A.; Huestis, G.M.

    2000-08-31

    Particle size distribution (PSD) analysis of INTEC Tank Farm WM-182 and WM-183 heel slurry samples were performed using a modified Horiba LA-300 PSD analyzer at the RAL facility. There were two types of testing performed: typical PSD analysis, and setting rate testing. Although the heel slurry samples were obtained from two separate vessels, the particle size distribution results were quite similar. The slurry solids were from approximately a minimum particle size of 0.5 mm to a maximum of 230 mm with about 90% of the material between 2-to-133 mm, and the cumulative 50% value at approximately 20 mm. This testing also revealed that high frequency sonication with an ultrasonic element may break-up larger particles in the WM-182 and WM-183 tank from heel slurries. This finding represents useful information regarding ultimate tank heel waste processing. Settling rate testing results were also fairly consistent with material from both vessels in that it appears that most of the mass of solids settle to an agglomerated, yet easily redispersed layer at the bottom. A dispersed and suspended material remained in the ''clear'' layer above the settled layer after about one-half an hour of settling time. This material had a statistical mode of approximately 5 mm and a maximum particle size of 30 mm.

  12. Polychlorinated biphenyls (PCB) analysis report for solid sample from 219S tank 101

    SciTech Connect

    Diaz, L.A.

    1998-02-04

    One waste sample that was obtained with solids from tank 101 of 219S via a peristaltic pump equipped with a stainless steel tube and Norprene tubing (Phthalate free) was obtained in a glass jar with teflon lid was analyzed (with duplicate, matrix spike, and matrix spike duplicate) for PCBs as Aroclor mixtures by the Inorganic/Organic Chemistry Group. A soxhlet extraction procedure was used for extraction of the Aroclors from the sample. Analysis was performed using dual column confirmation gas chromatography/electron capture detection (GC/ECD). Results are presented.

  13. Waste Tank Vapor Program: Vapor space characterization of Waste Tank 241-T-107. Results from samples collected on January 18, 1995

    SciTech Connect

    Pool, K.H.; Lucke, R.B.; McVeety, B.D.

    1995-06-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-T-107 (referred to as Tank T-107). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, I was observed above the 5-ppbv reporting cutoff. Six organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The estimated concentration of all 7 organic analytes observed in the tank headspace are listed in Table I and account for approximately 100% of the total organic components in Tank T-107. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected in the tank-headspace samples.

  14. Tank 241-BX-104 third temporal study: Headspace gas and vapor characterization results from samples collected on February 6, 1997. Tank vapor characterization project

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Hayes, J.C.

    1997-09-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BX-104 (Tank BX-104) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Service Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. Ammonia was determined to be above the immediate notification limit specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BX-104 headspace, determined to be present at approximately 0.178 % of its lower flammability limit (LFL). Total headspace flammability was estimated to be <0.458% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  15. Tank vapor characterization project: Tank 241-BX-104 fifth temporal study: Headspace gas and vapor characterization results from samples collected on June 10, 1997

    SciTech Connect

    Hayes, J.C.; Pool, K.H.; Evans, J.C.; Olsen, K.B.

    1997-07-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BX-104 (Tank BX-104) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Service Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. Ammonia was determined to be above the immediate notification limit specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BX-104 headspace, determined to be present at approximately 0.270% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <0.675% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  16. Tank 241-BY-108 fifth temporal study: Headspace gas and vapor characterization results from samples collected on January 30, 1997. Tank vapor characterization project

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Olsen, K.B.

    1997-09-01

    This report presents the results from analyses of samples taken from tile headspace of waste storage tank 241-B-108 (Tank BY - 108) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Services Corporation (SESC) and analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. Ammonia was determined to be above the immediate notification limit of 150 ppm specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BY-108 headspace, determined to be present at approximately 0.888% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <1.979% of tile LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  17. Tank Vapor Characterization Project: Tank 241-S-102 fourth temporal study: Headspace gas and vapor characterization results from samples collected on December 19, 1996

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Olsen, K.B.; Hayes, J.C.

    1997-08-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-S-102 (Tank S-102) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Service Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. Ammonia was determined to be above the immediate notification limit of 150 ppm as specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank S-102 headspace, determined to be present at approximately 2.410% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <2.973% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <2.973% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  18. Tank vapor characterization project: Tank 241-BY-101 headspace gas and vapor characterization results from samples collected on August 29, 1996

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.

    1997-08-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BY-101 (Tank BY-101) at the Hanford Site in Washington State. Tank headspace samples collected by Westinghouse Hanford Company (WHC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by WHC. No analytes were determined to be above the immediate notification limits specified by the sampling and analysis plan (SAP). Total non-methane organic compounds (TNMOCs) were the principal flammable constituent of the Tank By-101 headspace, determined to be present at approximately 0.136% of the LFL. Averaged measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  19. Tank Vapor Characterization Project: Tank 241-BX-111 headspace gas and vapor characterization results from samples collected on August 27, 1996

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.L.; Sklarew, D.S. Edwards, J.A.

    1997-08-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BX-111 (Tank BX-111) at the Hanford Site in Washington State. Tank headspace samples collected by Westinghouse Hanford Company (WHC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by WHC. No analytes were determined to be above the immediate notification limits specified by the sampling and analysis plan (SAP). Ammonia was the principal flammable constituent of the Tank BX-111 headspace, determined to be present at approximately 0.042 of its lower flammability limit (LFL). Total headspace flammability was estimated to be <0.157% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  20. Tank 241-C-107 fifth temporal study: Headspace gas and vapor characterization results from samples collected on February 7, 1997. Tank vapor characterization project

    SciTech Connect

    Hayes, J.C.; Pool, K.H.; Evans, J.C.

    1997-08-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-C-107 (Tank C-107) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Services Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. No analytes were determined to be above the immediate notification limits specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank C-107 headspace, determined to be present at approximately 3.233% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <3.342% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  1. Tank 241-BX-104 fourth temporal study: Headspace gas and vapor characterization results from samples collected on April 7, 1997. Tank vapor characterization project

    SciTech Connect

    Mitroshkov, A.V.; Hayes, J.C.; Evans, J.C.

    1997-09-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BX-04 (Tank BX-104) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Service Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. Ammonia was determined to be above the immediate notification limit specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BX-104 headspace, determined to be present at approximately 0.208% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <0.536% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  2. RESULTS FOR THE FOURTH QUARTER TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.; Bibler, N.

    2010-01-27

    The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low-level waste (LLW) streams from the Effluent Treatment Project (ETP), H-Canyon, the DDA (Deliquification, Dissolution, and Adjustment) process, and the decontaminated salt solution product from the Actinide Removal Process/Modular Caustic Side Solvent Extraction (CSSX) Unit (ARP/MCU) process are stored in Tank 50 until the LLW can be transferred to the Saltstone Facility for treatment and disposal. The LLW must meet the specified waste acceptance criteria (WAC) before it is processed into saltstone. The specific chemical and radionuclide contaminants and their respective WAC limits are listed in the current Saltstone WAC. SRS Liquid Waste Operations (LWO) requested that Savannah River National Laboratory (SRNL) perform quarterly analysis on saltstone samples. The concentrations of chemical and radionuclide contaminants are measured to ensure the saltstone produced during each quarter is in compliance with the current WAC. This report documents the concentrations of chemical and radionuclide contaminants for the 2009 Fourth Quarter samples collected from Tank 50 on October 2, 2009 and discusses those results in further detail than the previously issued results report. This report details the chemical and radionuclide contaminant results for the characterization of the 2009 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results

  3. Sampling and Analysis for Tank 241-AW-104 Waste in Support of Evaporator Campaign 2001-1

    SciTech Connect

    MCKINNEY, S.G.

    2000-05-23

    This Tank Sampling and Analysis Plan (TSAP) identifies sample collection, laboratory analysis, quality assurance/quality control (QA/QC), and reporting objectives for the characterization of tank 241-AW-104 waste. Technical bases for these objectives are specified in the 242-A Evaporator Data Quality Objectives (Bowman 2000a and Von Bargen 1998), 242-A Evaporator Quality Assurance Project Plan (Bowman 1998 and Bowman 2000b), Tank 241-AW-104 Sampling Requirements in Support of Evaporator Campaign 2000-1 (Le 2000). Characterization results will be used to support the evaporator campaign currently planned for early fiscal year 2001. No other needs (or issues) requiring data for this tank waste apply to this sampling event.

  4. Tank Vapor Characterization Project: Tank 241-BX-102 headspace gas and vapor characterization results from samples collected on July 31, 1996

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.L.; Olsen, K.B. Edwards, J.A.

    1997-08-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BX-102 (Tank BX-102) at the Hanford Site in Washington State. Tank headspace samples collected by Westinghouse Hanford Company (WHC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured volumes provided by WHC. No analytes were determined to be above the immediate notification limits specified by the sampling and and analysis plan. Ammonia and TNMOCs were the principal flammable constituents of the Tank BX-102 headspace, each determined to be present at approximately 0.002% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <0.107% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  5. RESULTS FOR THE FIRST QUARTER 2009 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.; Diprete, C.; Bibler, N.

    2009-10-06

    This report details the chemical and radionuclide contaminant results for the characterization of the 2009 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the chemical and radioactive contaminants were all less than their respective WAC Targets or Limits except for Am-242m. (2) The radionuclide Am-242m was not detected; however, its detection limit is above the WAC Target given in Attachment 8.4. The higher detection limit was expected based on current analytical capabilities as stated in the Task Technical and Quality Assurance Plan (TTQAP). (3) The reported detection limit of isopropanol was lower than its WAC Limit for accident analysis but higher than its WAC concentration given in Table 4 for vault flammability. The higher detection limit was expected based on current analytical capabilities and is documented in the Task Technical and Quality Assurance Plan (TTQAP). (4) The reported detection limit for Isopar L is lower than its WAC limit for accident analysis in Appendix 8.1 but higher than its WAC concentration given in Table 3 in reference to vault flammability. The higher detection limit was expected based on current analytical capabilities as stated in the Task Technical and Quality Assurance Plan (TTQAP). (5) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately

  6. RESULTS FOR THE FIRST QUARTER 2011 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.

    2011-06-15

    This report details the chemical and radionuclide contaminant results for the characterization of the 2011 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section; (2) The reported detection limit for {sup 59}Ni is above both the requested limits from Reference 2 and the established limits in Reference 3; (3) The reported detection limit for {sup 94}Nb is above the requested limit from Reference 2; however, it is below the established limits in Reference 3. This is a change from previously reported results; (4) The reported concentration of {sup 242m}Am is above the target in Listed in Attachment 8.4 of the Saltstone WAC. This is a change from the previously reported results; (5) {sup 247}Cm and {sup 249}Cf are above the requested limits from Reference 2. However, they are below the limits established in Reference 3; (6) The reported detection limit for Norpar 13 is greater than the limit from Table 4 and Attachment 8.2 of the WAC; (7) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC; and (8) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the instrument; however, the results may not accurately represent the concentrations of the analytes in Tank

  7. Tank 41H Post-Dissolution Saltcake Core and Supernate SampleAnalysis

    SciTech Connect

    MARTINO, CHRISTOPHERJ

    2004-07-07

    This report provides analyses of the samples from Tank 41H. The characterization also includes supernate samples pulled from the surface (347 inch) and 250 inch levels of the salt supernate. The three saltcake samples (HTF-E-03-145, 146, and 147) were filled to nearly their capacity with saltcake and free liquid, with an average saltcake bulk density of 2.06 g/cm3. The undrained saltcake from the bottom of the middle sample (HTF-E-03-146) had a water content of 4.1 percentage weight, a 137Cs activity of 0.14 Ci per gallon of saltcake, and an alpha content of 1.4E+4 pCi/g. The undrained saltcake from the bottom of the bottom sample (HTF-E-03-147) had a water content of 8.5 percentage weight, a 137Cs activity of 0.17 Ci per gallon of saltcake, and an alpha content of 3.0E+4 pCi/g. Interstitial liquid drained from the middle sample (HTF-E-03-146) had a density of 1.43 g/cm3, a soluble solids content of 45.4 percentage weight, a 137Cs activity of 0.78 Ci per gallon of interstitial liquid, a nd an alpha content of 1.1E+4 pCi/mL. An analysis of material from the top of the top sample (HTF-E-03-145) is provided in support of Nuclear Criticality Safety Evaluations. The as-received saltcake and the residual insoluble solids had a uranium-235 enrichment of approximately 12.2 per cent. Characterization focused on providing information on fissile radionuclides, potential neutron poisons, and other potential diluents. Supernate samples pulled from the surface and from the 250 in. levels of the C1 and C3 risers yielded information on the vertical and lateral tank supernate homogeneity. The 137Cs content of these Tank 41H samples averaged 0.56 Ci/gal for the C3 riser and 0.65 Ci/gal for the C1 riser. The 238Pu content of the four unfiltered samples ranged from 1.41E+4 pCi/mL to 2.21E+4 pCi/mL. Scanning electron microscopy of saltcake from sample HTF-E-03-146 revealed several features consistent with mineral dissolution: sub-rounded appearance of grains, lack of coatings by

  8. ELECTROCHEMICAL CORROSION TEST RESULTS FOR TANK 241-SY-102 SUPERNATE GRAB SAMPLES

    SciTech Connect

    DUNCAN JB

    2007-04-09

    This report describes the electrochemical corrosion scans and conditions for testing of SY-102 supernatant samples taken December 2004. The testing was performed because the tank was under a Justification for Continued Operation allowing the supernatant composition to be outside the chemistry limits of Administrative Control 5.16, 'Corrosion Mitigation program'. A new electrochemical working electrode of A516 Grade 60 carbon steel was used for each scan; all scans were measured against a saturated calomel electrode, with carbon counter electrodes, and all scans were carried out at 50 C. The samples were scanned twice, once as received and once sparged with argon to deoxygenate the sample. For those scans conducted after argon purging, the corrosion rates ranged from 0.012 to 0.019 mpy. A test for stress corrosion cracking was carried out on one sample (2SY-04-07) with negative results.

  9. Do-It-Yourself device for recovery of cryopreserved samples accidentally dropped into cryogenic storage tanks.

    PubMed

    Mehta, Rohini; Baranova, Ancha; Birerdinc, Aybike

    2012-01-01

    Liquid nitrogen is colorless, odorless, extremely cold (-196 °C) liquid kept under pressure. It is commonly used as a cryogenic fluid for long term storage of biological materials such as blood, cells and tissues (1,2). The cryogenic nature of liquid nitrogen, while ideal for sample preservation, can cause rapid freezing of live tissues on contact - known as 'cryogenic burn' (2), which may lead to severe frostbite in persons closely involved in storage and retrieval of samples from Dewars. Additionally, as liquid nitrogen evaporates it reduces the oxygen concentration in the air and might cause asphyxia, especially in confined spaces (2). In laboratories, biological samples are often stored in cryovials or cryoboxes stacked in stainless steel racks within the Dewar tanks (1). These storage racks are provided with a long shaft to prevent boxes from slipping out from the racks and into the bottom of Dewars during routine handling. All too often, however, boxes or vials with precious samples slip out and sink to the bottom of liquid nitrogen filled tank. In such cases, samples could be tediously retrieved after transferring the liquid nitrogen into a spare container or discarding it. The boxes and vials can then be relatively safely recovered from emptied Dewar. However, the cryogenic nature of liquid nitrogen and its expansion rate makes sunken sample retrieval hazardous. It is commonly recommended by Safety Offices that sample retrieval be never carried out by a single person. Another alternative is to use commercially available cool grabbers or tongs to pull out the vials (3). However, limited visibility within the dark liquid filled Dewars poses a major limitation in their use. In this article, we describe the construction of a Cryotolerant DIY retrieval device, which makes sample retrieval from Dewar containing cryogenic fluids both safe and easy. PMID:22617806

  10. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank 241-C-204: Results from samples collected on 07/02/96

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; Pool, K.H.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-C-204 (Tank C-204) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples are also listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  11. Vapor space characterization of waste Tank 241-BY-108: Results from in situ sample collected on March 24, 1994. Waste Tank Vapor Project

    SciTech Connect

    McVeety, B.D.; Lucke, R.B.; Clauss, T.W.; Fruchter, J.S.; Goheen, S.C.

    1995-06-01

    This document presents the details of the organic analysis that was performed on samples from the headspace of Hanford waste tank 241-BY-108. The results described were obtained to support the safety and toxicological evaluations. A summary of the results for the organic analytes is included, as well as, a detailed description of the results which appears in the text.

  12. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Tank 241-B-105: Results from samples collected on 07/30/96

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-B-105 (Tank B-105) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples are also listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  13. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank 241-S-103: Results from samples collected on 06/12/96

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-S-103 (Tank S-103) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples are also listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  14. Vapor space characterization of waste tank 241-C-101: Results from samples collected on 9/1/94

    SciTech Connect

    Lucke, R.B.; Clauss, T.W.; Ligotke, M.W.

    1995-11-01

    This report describes results of the analyses of tank-headspace samples taken from the Hanford waste Tank 241-C-101 (referred to as Tank C-101) and the ambient air collected - 30 ft upwind near the tank and through the VSS near the tank. Pacific Northwest Laboratory (PNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and to analyze inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The sample job was designated S4056, and samples were collected by WHC on September 1, 1994, using the vapor sampling system (VSS). The samples were inspected upon delivery to the 326/23B laboratory and logged into PNL record book 55408 before implementation of PNL Technical Procedure PNL-TVP-07. Custody of the sorbent traps was transferred to PNL personnel performing the inorganic analysis and stored at refrigerated ({le} 10{degrees}C) temperature until the time of analysis. The canisters were stored in the 326/23B laboratory at ambient (25{degrees}C) temperature until the time of the analysis. Access to the 326/23B laboratory is limited to PNL personnel working on the waste-tank safety program. Analyses described in this report were performed at PNL in the 300 area of the Hanford Reservation. Analytical methods that were used are described in the text. In summary, sorbent traps for inorganic analyses containing sample materials were either weighed (for water analysis) or desorbed with the appropriate aqueous solutions (for NH{sub 3}, NO{sub 2}, and NO analyses). The aqueous extracts were analyzed either by selective electrode or by ion chromatography (IC). Organic analyses were performed using cryogenic preconcentration followed by gas chromatography/mass spectrometry (GC/MS).

  15. Vapor space characterization of waste tank 241-C-109: Results from samples collected on 8/10/94

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Ligotke, M.W.

    1995-06-01

    This report describes results of the analyses of tank-headspace samples taken from the Hanford waste Tank 241-C-109 (referred to as Tank C-109). Pacific Northwest Laboratory (PNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and to analyze inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The sample job was designated S4053, and samples were collected by WHC on August 10, 1994, using the vapor sampling system (VSS). Sampling devices, including six sorbent trains (for inorganic analyses) and five SUMMA{sup {trademark}} canisters (for organic analyses) were supplied to the WHC sampling staff on August 8. Samples were taken (by WHC) from the tank headspace on August 10 and were returned to PNL from the field on August 12. The samples were inspected upon delivery to the 326/23B laboratory and logged into PNL record book 55408 before implementation of PNL Technical Procedure PNL-TVP-07. Custody of the sorbent traps was transferred to PNL personnel performing the inorganic analysis and stored at refrigerated ({<=}10{degrees}C) temperature until the time of analysis. The canister was stored in the 326/23B laboratory at ambient (25{degrees}C) temperature until time of analysis. Access to the 326/23B laboratory is limited to PNL personnel working on the waste-tank safety program. Analyses described in this report were performed at PNL in the 300 area of the Hanford Reservation. Analytical methods that were used are described in the text. In summary, sorbent traps for inorganic analyses containing sample materials were either weighed (for water analysis) or desorbed with the appropriate aqueous solutions (for ammonia (NH{sub 3}) or nitrite (NO{sub 2}) analyses). The aqueous extracts were analyzed either by selective electrode or by ion chromatography (IC). Organic analyses were performed using cryogenic preconcentration followed by gas chromatography/mass spectrometry (GC/MS).

  16. Headspace vapor characterization of Hanford waste Tank 241-C-201: Results from samples collected on 06/19/96

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-C-201 (Tank C-201) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary, of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. Detailed descriptions of the analytical results appear in the appendices.

  17. Headspace vapor characterization of Hanford waste tank 241-B-107: Results from samples collected on 7/23/96

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-B-107 (Tank B-107) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwestern National Laboratory (PNNL). A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples are also listed in the same table. Detailed descriptions of the analytical results appear in the appendices.

  18. Headspace vapor characterization of Hanford waste tank 241-S-106: Results from samples collected on 06/13/96

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-S-106 (Tank S-106) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples are also listed in the same table. Detailed descriptions of the analytical results appear in the appendices.

  19. Underground storage tanks 200W-FS-34 and 200W-FS-35 excavated soil field sample plan

    SciTech Connect

    Lucas, J.G.

    1994-09-07

    This plan outlines the process that will be used to collect samples from soil excavated during removal of underground storage tanks 200W-FS-34 and 200W-FS-35. The samples will be analyzed to determine if gasoline and diesel fuel are present in the soil at levels above action levels specified by the Washington State Department of Ecology. On April 15, 1992, the underground storage tanks were removed and soil samples were collected at each former tank location and from around the associated piping. Soil was excavated from the site until field instrumentation indicated that the former tank sites were clean in the judgment of the field team leader. Field monitoring consisted of using an organic vapor monitor to survey soil shaken in a plastic bag. Monitoring indicated that petroleum contamination ranged from 40 to 800 ppm.

  20. Analysis of tank 7 surface supernatant sample (FTF-7-15-26) in support of corrosion control program

    SciTech Connect

    Oji, L. N

    2015-10-01

    This report provides the results of analyses on Savannah River Site Tank 7 surface supernatant liquid sample in support of the Corrosion Control Program (CCP). The measured nitrate, nitrite and free-hydroxide concentrations for the Tank 7 surface sample averaged, 3.74E-01 ± 1.88E-03, 4.17E-01 ± 9.01E-03 and 0.602 ± 0.005 M, respectively. The Tank 7 surface cesium-137, sodium and silicon concentrations were, respectively, 3.99E+08, ± 3.25E+06 dpm/mL, 2.78 M and <3.10 mg/L. The measured aluminum concentration in the Tank 7 surface sample averaged 0.11 M.

  1. 45-Day safety screening for Tank 241-B-102 auger samples, riser 1

    SciTech Connect

    Bell, K.E.

    1994-12-01

    This is the 45-Day report for the fiscal year 1994 Tank 241-B-102 auger sampling characterization effort. Only one of the two planned auger samples was received by the 222-S Laboratory, however it was decided to begin the 45-day clock and issue a report based on receipt of the first auger sample. Included are copies of the differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA) scans as requested. Also included is a copy of any immediate notification documentation, chain of custody forms, the hot cell work plan, extruded segment [auger] description sheets, and total alpha data. The TGA percent moisture results are below the safety criteria limit of 17% in a subsample taken approximately five minutes after extrusion and a second subsample taken from the lower half of the auger. Verbal and written notifications were made as prescribed. The DSC analysis of all subsamples indicates the presence of fraction exotherms, however the results are a factor of two or more below the notification limit of 523 Joules/gram (J/g). Total alpha results are all below the detection limit. In some cases, the tank characterization plan (TCP) accuracy and precision criteria are not met. If a re-run was not performed when a TCP quality control limit was not met, then reasons for not performing the re-run are provided.

  2. Chemical Characterization of an Envelope C Sample from Hanford Tank 241-AN-102

    SciTech Connect

    Hay, M.S.

    2000-08-23

    An approximately 14.25 L sample from Hanford waste tank 241-AN-102 was received at the Savannah River Technology Center (SRTC) and chemically characterized. Prior to characterization the sample was diluted to {approximately}6 M sodium concentration. The filtered supernatant liquid, the total dried solids of the diluted sample, and the washed insoluble solids obtained from filtration of the diluted sample were analyzed. A mass balance calculation of the three fractions of the sample analyzed indicate the analytical results appear relatively self-consistent for major components of the sample. However, some inconsistency was observed between results were more than one method of determination was employed and for species present in low concentrations. An analysis of the organic complexants appears to be consistent with the TOC result. Some evidence was found to indicate the possible contamination of the first shipment of 241-AN-102 samples received at SRTC with Cm244 and possibly Am241 and plutonium isotopes. The comparison to previous analyses of samples from 241-AN-102 indicates general agreement with the current analytical results. The comparison of the solids analysis showed large deviations attributed to differences in obtaining the solids from the bulk sample.

  3. Level sensor replacement/sampling of Tank 241-SY-101 at the Hanford Site

    SciTech Connect

    Not Available

    1990-01-01

    The US Department of Energy (DOE) is responsible for management and storage of waste accumulated from the processing of defense reactor irradiated fuels for plutonium recovery at the Hanford Site. DOE is proposing to remove three level detectors from Tank 241-SY-101 and analyze the waste that is presently encrusted on the detectors. The proposed sampling is less intrusive than core sampling and will provide data regarding characterization of the crust to support future core sampling. The purpose of this environmental assessment (EA) is to provide information about the proposed action such that a decision can be made on whether a Finding of No Significant Impact should be issued or an environmental impact statement should be prepared. Therefore, this EA evaluates the proposed action and the no action alternative, in keeping with requirements of the National Environmental Policy Act of 1969 (NEPA) and regulations of the Council on Environmental Quality, Title 40, Code of Federal Regulations, parts 1500--1508. 6 refs.

  4. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-13-1403/1404/1405/1406/1407/1408: QUARTERLY SAMPLE FROM SEPTEMBER 2013

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2013-11-20

    Savannah River National Laboratory (SRNL) analyzed solvent samples from the Modular Caustic-Side Solvent Extraction Unit (MCU) in support of continuing operations. A quarterly analysis of the solvent is required to maintain solvent composition within specifications. Analytical results of the analyses of Solvent Hold Tank (SHT) samples MCU-13-1403, MCU-13-1404, MCU-13-1405, MCU-13-1406, MCU-13-1407, and MCU-13-1408 received on September 17, 2013 are reported. This sample was taken after the addition of the Next Generation Solvent (NGS) cocktail to produce a NGS-MCU blended solvent. The results show that the solvent contains a slight excess of Isopar L and a deficit concentration of modifier and TiDG when compared to the target composition. Addition of TiDG trim is recommended. SRNL also analyzed the SHT sample for {sup 137}Cs content and determined the measured value is within tolerance and that the value has returned to levels observed in 2011. In contrast to what was observed in the heel prior to adding the NGS cocktail, no organic impurities were detected in these solvent samples.

  5. Headspace vapor characterization of Hanford waste tank 241-B-202: Results from samples collected on 7/18/96

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-B-202 (Tank B-202) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. Detailed descriptions of the analytical results appear in the appendices.

  6. Characterization and Dessolution Test results for the January 2005 DWPF Off Gas Condensate Tank Samples (U)

    SciTech Connect

    Fellinger, T

    2005-04-08

    The Off Gas Condensate Tank (OGCT) at the Defense Waste Processing Facility (DWPF) collects the condensate from the off-gas system of the melter. The condensate stream contains entrained solids that collect in the OGCT. Water from the OGCT is re-circulated to the Steam Atomized Scrubber and quencher and may provide a mechanism for re-introducing the particulates into the off-gas system. These particulates are thought to be responsible for plugging the downstream High Efficiency Mist Eliminator filters. Therefore, the OGCT needs to be periodically cleaned to remove the build-up of entrained solids. Currently, the OGCT is cleaned by adding nominally 12 wt% nitric acid with agitation to slurry the solids from the tank. Samples from the OGCT were sent to the Savannah River National Lab (SRNL) for characterization and to conduct tests to determine the optimum nitric acid concentration and residence time to allow more effective cleaning of the OGCT. This report summarizes the chemical and radionuclide results and the results from the nitric acid dissolution testing at 50% and 12% obtained for the OGCT sample.

  7. RESULTS FOR THE FOURTH QUARTER 2011 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Bannochie, C.

    2012-01-31

    The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low-level waste (LLW) streams from the Effluent Treatment Project (ETP), H-Canyon, and the decontaminated salt solution product from the Actinide Removal Process/Modular Caustic Side Solvent Extraction (CSSX) Unit (ARP/MCU) process are stored in Tank 50 until the LLW can be transferred to the Saltstone Facility for treatment and disposal. The LLW must meet the specified waste acceptance criteria (WAC) before it is processed into saltstone. The specific chemical and radionuclide contaminants and their respective WAC limits are in the current Saltstone WAC. Waste Solidification Engineering (WSE) requested that Savannah River National Laboratory (SRNL) perform quarterly analysis on saltstone samples. The concentrations of chemical and radionuclide contaminants are measured to ensure the saltstone produced during each quarter is in compliance with the current WAC. This report documents the concentrations of chemical and radionuclide contaminants for the 2011 Fourth Quarter samples collected from Tank 50 on October 12, 2011 and discusses those results in further detail than the previously issued results report.

  8. RESULTS FOR THE THIRD QUARTER 2011 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.

    2011-10-20

    The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low-level waste (LLW) streams from the Effluent Treatment Project (ETP), H-Canyon, and the decontaminated salt solution product from the Actinide Removal Process/Modular Caustic Side Solvent Extraction (CSSX) Unit (ARP/MCU) process are stored in Tank 50 until the LLW can be transferred to the Saltstone Facility for treatment and disposal. The LLW must meet the specified waste acceptance criteria (WAC) before it is processed into saltstone. The specific chemical and radionuclide contaminants and their respective WAC limits are in the current Saltstone WAC. Waste Solidification Engineering (WSE) requested that Savannah River National Laboratory (SRNL) perform quarterly analysis on saltstone samples. The concentrations of chemical and radionuclide contaminants are measured to ensure the saltstone produced during each quarter is in compliance with the current WAC. This report documents the concentrations of chemical and radionuclide contaminants for the 2011 Third Quarter samples collected from Tank 50 on July 7, 2011 and discusses those results in further detail than the previously issued results report.

  9. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample

    SciTech Connect

    Washington, A. L. II; Peters, T. B.

    2013-09-19

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

  10. Tank vapor characterization project. Headspace vapor characterization of Hanford waste Tank SX-101: Results from samples collected on 07/21/95

    SciTech Connect

    Evans, J.C.; Clauss, T.W.; McVeety, B.D.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1996-05-01

    Results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank-farm operations. They include air concentrations of inorganic and organic analytes and grouped compounds from samples. The vapor concentrations are based either on whole-volume samples or on sorbent traps exposed to sample flow. No immediate notifications were needed because analytical results indicated no specific analytes exceeded notification levels. Summary of results: NH3, 3.8 ppmv; NO2, 0.10 ppmv; NO, 0.13 ppm; H2O, 11.8 mg/L; CO2, 338 ppmv; CO, <25 ppmv; CH4, <25 ppmv; H2, <25 ppmv; N20, <25 ppmv; hydrocarbons, 0.98 mg/m{sup 3}; methanol, 0.060 ppmv; acetone, 0.033 ppmv; trichlorofluoromethane, 0.023 ppmv; and acetone, 0.034 ppmv.

  11. Tank Vapor Characterization Project: Tank 241-BY-108 temporal study headspace gas and vapor characterization results from samples collected on September 10, 1996

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.; Sklarew, D.S.

    1997-08-01

    This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BY-108 (Tank BY-108) at the Hanford Company (WHC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by WHC. Ammonia was determined to be above the immediate notification limit of 150 ppm specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BY-108 headspace, determined to be present at approximately 1.463% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <2.940% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

  12. SLUDGE BATCH 6 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB6 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect

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

    2010-05-21

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Six (SB6) for processing in the Defense Waste Processing Facility (DWPF). The SB6 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 SB5. The radionuclide concentrations were measured or estimated in the Tank 51 SB6 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry (HTF-51-09-110) taken on October 8, 2009. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under the direction of the Liquid Waste Organization it was then modified by eight washes, nine decants, an addition of Pu from Canyon Tank 16.3, and an addition of NaNO{sub 2}. 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 SB6 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2009-0014. 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 I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task II.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 SB6 will be taken and transferred

  13. Sampling and analysis of radioactive liquid wastes and sludges in the Melton Valley and evaporator facility storage tanks at ORNL

    SciTech Connect

    Sears, M.B.; Botts, J.L.; Ceo, R.N.; Ferrada, J.J.; Griest, W.H.; Keller, J.M.; Schenley, R.L.

    1990-09-01

    The sampling and analysis of the radioactive liquid wastes and sludges in the Melton Valley Storage Tanks (MVSTs), as well as two of the evaporator service facility storage tanks at ORNL, are described. Aqueous samples of the supernatant liquid and composite samples of the sludges were analyzed for major constituents, radionuclides, total organic carbon, and metals listed as hazardous under the Resource Conservation and Recovery Act (RCRA). Liquid samples from five tanks and sludge samples from three tanks were analyzed for organic compounds on the Environmental Protection Agency (EPA) Target Compound List. Estimates were made of the inventory of liquid and sludge phases in the tanks. Descriptions of the sampling and analytical activities and tabulations of the results are included. The report provides data in support of the design of the proposed Waste Handling and Packaging Plant, the Liquid Low-Level Waste Solidification Project, and research and development activities (R D) activities in developing waste management alternatives. 7 refs., 8 figs., 16 tabs.

  14. RESULTS OF ROUTINE STRIP EFFLUENT HOLD TANK AND DECONTAMINATED SALT SOLUTION HOLD TANK SAMPLES FROM MODULAR CAUSTIC-SIDE SOLVENT EXTRACTION UNIT DURING MACROBATCH 3 OPERATIONS

    SciTech Connect

    Peters, T.; Fink, S.

    2011-06-10

    Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the 'microbatches' of Integrated Salt Disposition Project (ISDP) Salt Batch ('Macrobatch') 3 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The results indicate good decontamination performance within process design expectations. While the data set is sparse, the results of this set and the previous set of results for Macrobatch 3 samples indicate consistent operations. However, the Decontamination Factors for plutonium and strontium removal have declined in Macrobatch 3, compared to Macrobatch 2. This may be due to the differences in the Pu concentration or the bulk chemical concentrations in the feed material. SRNL is considering the possible reasons for this decline. The DSSHT samples show continued presence of titanium, likely from leaching of the monosodium titanate in ARP. During operation of the ISDP, quantities of salt waste are processed through the Actinide Removal Process (ARP) and MCU in batches of {approx}3800 gallons. Monosodium titanate (MST) is used in ARP to adsorb actinides and strontium from the salt waste and the waste slurry is then filtered prior to sending the clarified salt solution to MCU. The MCU uses solvent extraction technology to extract cesium from salt waste and concentrate cesium in an acidic aqueous stream (Strip Effluent - SE), leaving a decontaminated caustic salt aqueous stream (Decontaminated Salt Solution - DSS). Sampling occurs in the Decontaminated Salt Solution Hold Tank (DSSHT) and Strip Effluent Hold Tank (SEHT) in the MCU process. The MCU sample plan requires that batches be sampled and analyzed for plutonium and strontium content by Savannah River National Lab (SRNL) to determine MST effectiveness. The cesium measurement is used to monitor cesium removal effectiveness and the inductively coupled plasma emission spectroscopy (ICPES) is

  15. Solid Phase Characterization of Tank 241-C-108 Residual Waste Solids Samples

    SciTech Connect

    Cooke, Gary A.; Pestovich, John A.; Huber, Heinz J.

    2013-05-29

    This report presents the results for solid phase characterization (SPC) of solid samples removed from tank 241-C-108 (C-108) on August 12-13,2012, using the off-riser sampler. Samples were received at the 222-S Laboratory on August 13 and were described and photographed. The SPC analyses that were performed include scanning electron microscopy (SEM) using the ASPEX(R)l scanning electron microscope, X-ray diffraction (XRD) using the Rigaku(R) 2 MiniFlex X-ray diffractometer, and polarized light microscopy (PLM) using the Nikon(R) 3 Eclipse Pol optical microscope. The SEM is equipped with an energy dispersive X-ray spectrometer (EDS) to provide chemical information. Gary A. Cooke conducted the SEM analysis, John A. Pestovich performed the XRD analysis, and Dr. Heinz J. Huber performed the PLM examination. The results of these analyses are presented here.

  16. Vapor space characterization of waste Tank 241-TX-118 (in situ): Results from samples collected on 9/7/94

    SciTech Connect

    Thomas, B.L.; Clauss, T.W.; Ligotke, M.W.; Pool, K.H.; McVeety, B.D.; Olsen, K.B.; Fruchter, J.S.; Goheen, S.C.

    1995-10-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the headspace of the Hanford waste storage Tank 241-TX-118 (referred to as Tank TX-118). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), hydrogen cyanide (CHN), and water (H{sub 2}O). Sampling for sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 13 analytes. Hexane, normally included in the additional analytes, was removed because a calibration standard was not available during analysis of Tank TX-118 SUMMA{trademark} canisters. Of these, 12 were observed above the 5-ppbv reporting cutoff. Fourteen tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 86% of the total organic components in Tank TX-118. Permanent gas analysis was not conducted on the tank-headspace samples. Tank TX-118 is on both the Ferrocyanide and Organic Watch List.

  17. RESULTS FOR THE THIRD QUARTER 2009 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Reigel, M.; Diprete, C.; Bibler, N.

    2009-11-13

    This report details the chemical and radionuclide contaminant results for the characterization of the 2009 Third Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. Recently, a review of the radionuclide inventory in Saltstone Vaults 1 and 4 identified several additional radionuclides, not currently in the WAC, which require quantification ({sup 40}K, {sup 108m}Ag, {sup 133}Ba, {sup 207}Bi, {sup 227}Ac, {sup 228}Ra, {sup 228}Th, {sup 231}Pa, {sup 247}Cm, {sup 249}Cf, {sup 251}Cf). In addition, several of the radionuclides previously reported with minimum detection limits below the requirements listed in the WAC required analysis with reduced detection limits to support future inventory reporting requirements ({sup 22}Na, {sup 26}Al, {sup 59}Ni, {sup 94}Nb, {sup 106}Ru, {sup 144}Ce, {sup 152}Eu, {sup 155}Eu, {sup 226}Ra). This added scope was formally requested in a revision to the standing Technical Task Request for CY2009 Saltstone support and is further discussed in several supporting documents. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants are less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limits for {sup 59}Ni, {sup 94}Nb, {sup 247}Cm, and {sup 249}Cf are above the limits requested by LWO; however, they are below the achievable limits established by Analytical Development (AD). (3) The reported detection limit of isopropanol is lower than its WAC Limit for accident analysis in Appendix 8.1, but higher than its WAC concentration given in

  18. CHARACTERIZATION OF TANK 50 SLURRY FOR SALTSTONE WASTE ACCEPTANCE CRITERIA, APRIL 2007 SAMPLES

    SciTech Connect

    Zeigler, K; Ned Bibler, N; David Diprete, D

    2007-12-07

    This report summarizes the results from the characterization of the second quarter April 2007 sampling of Tank 50H for the Saltstone Waste Acceptance Criteria (WAC). Six one liter samples were taken in polyethylene bottles to analyze for the WAC contaminants and a 200 mL sample was taken in a steel container for analysis of volatile organic compounds. The information from this characterization will be given to Waste Solidification Engineering personnel to qualify the transfer of aqueous waste to the Saltstone Facility. The following conclusions are drawn from the analytical results found in this report: (1) All six of the one liter samples taken in April 2007 from the mixed slurry in Tank 50 have the same compositions within the experimental uncertainty of the analyses. (2) Of the ninety-one process, chemical, and radioactive WAC target or limit contaminants listed in Revision 7 of the 'Waste Acceptance Criteria for Aqueous Waste sent to the Z-Area Saltstone Production Facility', eighty-nine had concentrations that were unequivocally less than the WAC limit or target. (3) The two contaminants whose concentrations could not be shown to be less than their WAC targets were methanol and radioactive Nb-93m. Currently the AD Section of SRNL does not have a method for measuring methanol in caustic solutions. For Nb-93m the results are ambiguous due to possible interferences in the ICP-MS analysis from Zr-93 or Mo-93. (4) Of the six additional chemical and radioactive contaminants requested in the TTR for Saltstone qualification, five were measured or calculated. These were Sb, Be, Tl, along with total beta and gamma. The AD Section does not have a method to measure the 6th contaminant which was the cyanide ion.

  19. Test plan: Laboratory-scale testing of the first core sample from Tank 102-AZ

    SciTech Connect

    Morrey, E.V.

    1996-03-01

    The overall objectives of the Radioactive Process/Product Laboratory Testing (RPPLT), WBS 1.2.2.05.05, are to confirm that simulated HWVP feed and glass are representative of actual radioactive HWVP feed and glass and to provide radioactive leaching and glass composition data to WFQ. This study will provide data from one additional NCAW core sample (102-AZ Core 1) for these purposes.

  20. RESULTS FOR THE SECOND QUARTER 2011 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Eibling, R.

    2011-08-25

    The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low-level waste (LLW) streams from the Effluent Treatment Project (ETP), H-Canyon, the DDA (Deliquification, Dissolution, and Adjustment) process, and the decontaminated salt solution product from the Actinide Removal Process/Modular Caustic Side Solvent Extraction (CSSX) Unit (ARP/MCU) process are stored in Tank 50 until the LLW can be transferred to the Saltstone Facility for treatment and disposal. The LLW must meet the specified waste acceptance criteria (WAC) before it is processed into saltstone. The specific chemical and radionuclide contaminants and their respective WAC limits are listed in the current Saltstone WAC. Waste Solidification Engineering (WSE) requested that Savannah River National Laboratory (SRNL) perform quarterly analysis on saltstone samples. The concentrations of chemical and radionuclide contaminants are measured to ensure the saltstone produced during each quarter is in compliance with the current WAC. This report documents the concentrations of chemical and radionuclide contaminants for the 2011 Second Quarter samples collected from Tank 50 on April 4, 2011 and discusses those results in further detail than the previously issued results report. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limit for {sup 59}Ni is above the requested limit from Reference 2 but below the established limit in Reference 3. (3) The reported detection limit for {sup 94}Nb is above the requested limit from Reference 2; however, it is below the established limits in Reference 3. (4) The reported concentration of

  1. Vapor space characterization of waste tank 241-BY-105 (in situ): Results from samples collected on May 9, 1994

    SciTech Connect

    McVeety, B.D.; Pool, K.H.; Ligotke, M.W.; Clauss, T.W.; Lucke, R.B.; Sharma, A.K.; McCulloch, M.; Fruchter, J.S.; Goheen, S.C.

    1995-05-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the tank headspace of the Hanford waste storage Tank 241-BY-105 (referred to as Tank BY-105). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds NH{sub 3}, NO{sub 2}, NO, HCN, and H{sub 2}O. Sampling for sulfur oxides was not requested. Results of the inorganic samples were affected by sampling errors that led to an undefined uncertainty in sample volume. Consequently, tank-headspace concentrations are estimated only. Thirty-nine tentatively identified organic analytes were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and their quantitation is beyond the scope of this study. In addition, we looked for the 41 standard TO-14 analytes. Of these, only a few were observed above the 2-ppbv detection limit. The 16 organic analytes with the highest estimated concentrations are listed. These 16 analytes account for approximately 68% of the total or organic components in Tank BY-105.

  2. Analytical test results for archived core composite samples from tanks 241-TY-101 and 241-TY-103

    SciTech Connect

    Beck, M.A.

    1993-07-16

    This report describes the analytical tests performed on archived core composite samples form a 1.085 sampling of the 241-TY-101 (101-TY) and 241-TY-103 (103-TY) single shell waste tanks. Both tanks are suspected of containing quantities of ferrocyanide compounds, as a result of process activities in the late 1950`s. Although limited quantities of the composite samples remained, attempts were made to obtain as much analytical information as possible, especially regarding the chemical and thermal properties of the material.

  3. CHARACTERIZATION OF TANK 16H ANNULUS SAMPLES PART II: LEACHING RESULTS

    SciTech Connect

    Hay, M.; Reboul, S.

    2012-06-19

    The closure of Tank 16H will require removal of material from the annulus of the tank. Samples from Tank 16H annulus were characterized and tested to provide information to evaluate various alternatives for removing the annulus waste. The analysis found all four annulus samples to be composed mainly of Si, Na, and Al and lesser amounts of other elements. The XRD data indicate quartz (SiO{sub 2}) and sodium aluminum nitrate silicate hydrate (Na{sub 8}(Al{sub 6}Si{sub 6}O{sub 24})(NO{sub 3}){sub 2}.4H{sub 2}O) as the predominant crystalline mineral phases in the samples. The XRD data also indicate the presence of crystalline sodium nitrate (NaNO{sub 3}), sodium nitrite (NaNO{sub 2}), gibbsite (Al(OH){sub 3}), hydrated sodium bicarbonate (Na{sub 3}H(CO{sub 3}){sub 2}.2H{sub 2}O), and muscovite (KAl{sub 2}(AlSi{sub 3}O{sub 10})(OH){sub 2}). Based on the weight of solids remaining at the end of the test, the water leaching test results indicate 20-35% of the solids dissolved after three contacts with an approximately 3:1 volume of water at 45 C. The chemical analysis of the leachates and the XRD results of the remaining solids indicate sodium salts of nitrate, nitrite, sulfate, and possibly carbonate/bicarbonate make up the majority of the dissolved material. The majority of these salts were dissolved in the first water contact and simply diluted with each subsequent water contact. The water leaching removed large amounts of the uranium in two of the samples and approximately 1/3 of the {sup 99}Tc from all four samples. Most of the other radionuclides analyzed showed low solubility in the water leaching test. The oxalic acid leaching test result indicate approximately 34-47% of the solids in the four annulus samples will dissolve after three contacts with an approximately 3:1 volume of acid to solids at 45 C. The same sodium salts found in the water leaching test comprise the majority of dissolved material in the oxalic acid leaching test. However, the oxalic acid was

  4. SOLID PHASE CHARACTERIZATION OF HEEL SAMPLES FROM TANK 241-C-110

    SciTech Connect

    PAGE JS; COOKE GA; PESTOVICH JA; HUBER HJ

    2011-12-01

    During sluicing operations of tank 241-C-110, a significant amount of solids were unable to be retrieved. These solids (often referred to as the tank 'heel') were sampled in 2010 and chemically and mineralogically analyzed in the 222-S Laboratory. Additionally, dissolution tests were performed to identify the amount of undissolvable material after using multiple water contacts. This report covers the solid phase characterization of six samples from these tests using scanning electron microscopy, polarized light microscopy, and X-ray diffraction. The chemical analyses, particle size distribution analysis, and dissolution test results are reported separately. Two of the samples were from composites created from as-received material - Composite A and Composite B. The main phase in these samples was sodium-fluoride-phosphate hydrate (natrophosphate) - in the X-ray diffraction spectra, this phase was the only phase identifiable. Polarized light microscopy showed the presence of minor amounts of gibbsite and other phases. These phases were identified by scanning electron microscopy - energy dispersive X-ray spectroscopy as sodium aluminosilicates, sodium diuranate, and sodium strontium phosphate hydrate (nastrophite) crystals. The natrophosphate crystals in the scanning electron microscopy analysis showed a variety of erosive and dissolution features from perfectly shaped octahedral to well-rounded appearance. Two samples were from water-washed Composites A and B, with no change in mineralogy compared to the as-received samples. This is not surprising, since the water wash had only a short period of water contact with the material as opposed to the water dissolution tests. The last two samples were residual solids from the water dissolution tests. These tests included multiple additions of water at 15 C and 45 C. The samples were sieved to separate a coarser fraction of > 710 {mu}m and a finer fraction of < 710 {mu}m. These two fractions were analyzed separately. The

  5. Tank 50H Tetraphenylborate Destruction Results

    SciTech Connect

    Peters, T.B.

    2003-10-03

    We conducted several scoping tests with both Tank 50H surrogate materials (KTPB and phenol) as well as with actual Tank 50H solids. These tests examined whether we could destroy the tetraphenylborate in the surrogates or actual Tank 50H material either by use of Fenton's Reagent or by hydrolysis (in Tank 50H conditions at a maximum temperature of 50 degrees C) under a range of conditions. The results of these tests showed that destruction of the solids occurred only under a minority of conditions. (1)Using Fenton's Reagent and KTPB as the Tank 50H surrogate, no reaction occurred at pH ranges greater than 9. (2)Using Fenton's Reagent and phenol as the Tank 50H surrogate, no reaction occurred at a pH of 14. (3)Using Fenton's Reagent and actual Tank 50H slurry, a reaction occurred at a pH of 9.5 in the presence of ECC additives. (4)Using Fenton's Reagent and actual Tank 50H slurry, after a thirty three day period, all attempts at hydrolysis (at pH 14) were too slow to be viable. This happened even in the case of higher temperature (50 degrees C) and added (100 ppm) copper. Tank 50H is scheduled to return to HLW Tank Farm service with capabilities of transferring and receiving salt supernate solutions to and from the Tank Farms and staging feed for the Saltstone Facility. Before returning Tank 50H to Tank Farm service as a non-organic tank, less than 5 kg of TPB must remain in Tank 50H. Recently, camera inspections in Tank 50H revealed two large mounds of solid material, one in the vicinity of the B5 Riser Transfer Pump and the other on the opposite side of the tank. Personnel sampled and analyzed this material to determine its composition. The sample analysis indicated presence of a significant quantity of organics in the solid material. This quantity of organic material exceeds the 5 kg limit for declaring only trace amounts of organic material remain in Tank 50H. Additionally, these large volumes of solids, calculated as approximately 61K gallons, present other

  6. Solvent hold tank sample results for MCU-15-802-803-804-805-806-807 August monthly sample

    SciTech Connect

    Fondeur, F. F.; Jones, D. H.

    2016-01-01

    Savannah River National Laboratory (SRNL) received one set of Solvent Hold Tank (SHT) samples (MCU-15-802-803-804-805-806-807), pulled on 08/31/2015 for analysis. The samples were combined and analyzed for composition. Analysis of the composite sample MCU-15-802-803-804-805-806-807 indicated a low concentration (~ 45 % of nominal) of the suppressor (TiDG) and a slightly lower than nominal concentration of the modifier (Cs-7SB) in the solvent. The extractant (MaxCalix) concentration was at its nominal value. Based on this current monthly sample, the levels of TiDG, MaxCalix, and modifier were sufficient for continuing operation without adding a trim during that time but it is recommended that an addition of TiDG, modifier and Isopar™L should be made in the next few months. This monthly sample’s rheology, as determined by Hydrogen Nuclear Magnetic Resonance (H-NMR), is consistent with the rheology of the standard NGS solvent made in the lab (Scratch solvent 5/14/2014). No impurities above the 1000 ppm level were found in this solvent by the Semi-Volatile Organic Analysis (SVOA). No impurities were observed in the Hydrogen Nuclear Magnetic Resonance (HNMR). In addition, up to 16.7 micrograms of mercury per gram of solvent (or 14 μg/mL) was detected in this sample. The laboratory will continue to monitor the quality of the solvent in particular for any new impurities or degradation of the solvent components.

  7. Vapor space characterization of waste tank 241-TX-105: Results from samples collected on December 20, 1994. Waste Tank Vapor Project

    SciTech Connect

    Klinger, G.S.; Ligotke, M.W.; Lucke, R.B.

    1995-06-01

    This document presents the details of the inorganic and organic analysis that was performed on samples from the headspace of Hanford waste tank 241-TX-105. The results described were obtained to support the safety and toxicological evaluations. A summary of the results for the inorganic and organic analytes is included, as well as, a detailed description of the results which appears in the text.

  8. Vapor space characterization of waste tank 241-TY-101 (in situ): Results from samples collected on August 5, 1994. Waste Tank Vapor Program

    SciTech Connect

    Pool, K.H.; Ligotke, M.W.; McVeety, B.D.; McCulloch, M.; Goheen, S.C.; Clauss, T.W.; Lucke, R.B.; Young, J.S.; Fruchter, J.S.

    1995-07-01

    This document presents the details of the inorganic and organic analysis that was performed on samples from the headspace of Hanford waste tank 241-TY-101. The results described were obtained to support the safety and toxicological evaluations. A summary of the results for the inorganic and organic analytes is included, as well as, a detailed description of the results which appears in the text.

  9. Vapor space characterization of waste tank 241-U-111: Results from samples collected on February 28, 1995. Waste Tank Vapor Program

    SciTech Connect

    Clauss, T.W.; Pool, K.H.; McVeety, B.D.; Bredt, O.P.; Goheen, S.C.; Ligotke, M.W.; Lucke, R.B.; Klinger, G.S.; Fruchter, J.S.

    1995-07-01

    This document presents the details of the inorganic and organic analysis that was performed on samples from the headspace of Hanford waste tank 241-U-111. The results described were obtained to support the safety and toxicological evaluations. A summary of the results for the inorganic and organic analytes is included, as well as, a detailed description of the results which appears in the text.

  10. Vapor space characterization of waste tank 241-C-105: Results from samples collected on 2/16/94

    SciTech Connect

    Clauss, T.W.; Lucke, R.B.; McVeety, B.D.

    1995-06-01

    This report describes results of the analyses of tank-headspace samples taken from the Hanford waste Tank 241-C-105 (referred to as Tank C-105). Pacific Northwest Laboratory (PNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and to analyze inorganic and organic analytes collected from the tank headspace. For organic analyses, six SUMMA{trademark} canisters were delivered to WHC on COC 0061 11 on 2/14/94. At the request of WHC, an additional six SUMMA{trademark} canisters were supplied on COC 005127 on 2/16/94. Samples were collected by WHC from the headspace of Tank C-105 through the VSS on 2/16/94, but only three SUMMA{sup {trademark}} canisters were returned to PNL using COC 0061 11 on 2/18/94. The canisters were stored in the 326/23B laboratory at ambient (25{degrees}C) temperature until the time of the analysis. Analyses described in this report were performed at PNL in the 300 area of the Hanford Reservation. Analytical methods that were used are described in the text. In summary, sorbent traps for inorganic analyses containing sample materials were either weighed (for water analysis) or desorbed with the appropriate aqueous solutions. The aqueous extracts were analyzed either by selective electrode or by ion chromatography (IC). Organic analyses were performed using cryogenic preconcentration followed by gas chromatography/mass spectrometry (GC/MS).

  11. Headspace vapor characterization of Hanford waste tank 241-U-109: Results from samples collected on 8/10/95

    SciTech Connect

    Evans, J.C.; Thomas, B.L.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1996-05-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-109 (Tank U-109) At the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. This tank is on the Hydrogen Waste List. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases and total non-methane hydrocarbons is listed in a table. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples is also listed in the table. Detailed descriptions of the analytical results appear in the text.

  12. Vapor space characterization of waste Tank 241-U-106: Results from samples collected on March 7, 1995. Waste Tank Vapor Program

    SciTech Connect

    Klinger, G.S.; Lucke, R.B.; McVeety, B.D.

    1995-07-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-U-106 (referred to as Tank U-106). The results described here were obtained to support safety and toxicological evaluations. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O) Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. The NH{sub 3} concentration was 16% greater than that determined from an ISS sample obtained in August 1994; the H{sub 2}O concentration was about 10% less. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 5 were observed in two or more canisters above the 5-ppbv reporting cutoff. Eleven organic tentatively identified compounds (TICS) were observed in two or more canisters above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations account for approximately 90% of the total organic components in Tank U-106. Three permanent gases, nitrous oxide (N{sub 2}O), hydrogen (H{sub 2}) and carbon dioxide (COD were also detected.

  13. CHARACTERIZATION AND ALUMINUM DISSOLUTION DEMONSTRATION WITH A 3 LITER TANK 51H SAMPLE

    SciTech Connect

    Hay, M; John Pareizs, J; Cj Bannochie, C; Michael Stone, M; Damon Click, D; Daniel McCabe, D

    2008-02-29

    A 3-liter sludge slurry sample was sent to SRNL for demonstration of a low temperature aluminum dissolution process. The sludge was characterized before and after the aluminum dissolution. Post aluminum dissolution sludge settling and the stability of the decanted supernate were also observed. The characterization of the as-received 3-liter sample of Tank 51H sludge slurry shows a typical high aluminum HM sludge. The XRD analysis of the dried solids indicates Boehmite is the predominant crystalline form of aluminum in the sludge solids. However, amorphous phases of aluminum present in the sludge would not be identified using this analytical technique. The low temperature (55 C) aluminum dissolution process was effective at dissolving aluminum from the sludge. Over the three week test, {approx}42% of the aluminum was dissolved out of the sludge solids. The process appears to be selective for aluminum with no other metals dissolving to any appreciable extent. At the termination of the three week test, the aluminum concentration in the supernate had not leveled off indicating more aluminum could be dissolved from the sludge with longer contact times or higher temperatures. The slow aluminum dissolution rate in the test may indicate the dissolution of the Boehmite form of aluminum however; insufficient kinetic data exists to confirm this hypothesis. The aluminum dissolution process appears to have minimal impact on the settling rate of the post aluminum dissolution sludge. However, limited settling data were generated during the test to quantify the effects. The sludge settling was complete after approximately twelve days. The supernate decanted from the settled sludge after aluminum dissolution appears stable and did not precipitate aluminum over the course of several months. A mixture of the decanted supernate with Tank 11 simulated supernate was also stable with respect to precipitation.

  14. Tank 241-S-111: Tank characterization plan

    SciTech Connect

    Homi, C.S.

    1995-03-07

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, ORNL, and PNL tank vapor program. Scope of this plan is to provide guidance for sampling and analysis of vapor samples from tank 241-S-111 (this tank is on the organic and flammable gas watch list). This tank received Redox plant waste, among other wastes.

  15. Vapor space characterization of Waste Tank 241-U-106 (in situ): Results from samples collected on 8/25/94

    SciTech Connect

    Ligotke, M.W.; Lucke, R.B.; Pool, K.H.

    1995-10-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the headspace of the Hanford waste storage Tank 241-U-106 (referred to as Tank U-106). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not performed. In addition, the authors looked for the 39 TO-14 compounds plus an additional 14 target analytes. Of these, six were observed above the 5-ppbv reporting cutoff. Ten organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv in two or more of the three samples collected and are reported with concentrations that are semiquantitative estimates based on internal standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 89% of the total organic components in Tank U-106. Methyl isocyanate, a compound of possible concern in Tank U-106, was not detected. Tank U-106 is on the Organic Watch List.

  16. Vapor space characterization of Waste Tank 241-U-107: Results from samples collected on 2/17/95

    SciTech Connect

    McVeety, B.D.; Clauss, T.W.; Ligotke, M.W.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-U-107 (referred to as Tank U-107). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 10 were observed above the 5-ppbv reporting cutoff. Sixteen organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv, and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 88% of the total organic components in Tank U-107. Nitrous oxide (N{sub 2}O) was the only permanent gas detected in the tank-headspace samples. Tank U-107 is on the Organic and the Hydrogen Watch Lists.

  17. Vapor space characterization of waste Tank 241-SX-103: Results from samples collected on 3/23/95

    SciTech Connect

    Ligotke, M.W.; Clauss, T.W.; Pool, K.H.; McVeety, B.D.; Klinger, G.S.; Olsen, K.B.; Bredt, O.P.; Fruchter, J.S.; Goheen, S.C.

    1995-11-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage tank 241-SX-103 (referred to as Tank SX-103). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, two were observed above the 5-ppbv reporting cutoff. Two tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The four organic analytes identified are listed in Table 1 and account for approximately 100% of the total organic components in Tank SX-103. Carbon dioxide (CO{sub 2}) was the only permanent gas detected in the tank-headspace samples. Tank SX-103 is on the Hydrogen Watch List.

  18. Vapor space characterization of Waste Tank 241-U-105: Results from samples collected on 2/24/95

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Ligotke, M.W.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-U-105 (referred to as Tank U-105). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, six were observed above the 5-ppbv reporting cutoff. Three tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. All nine of the organic analytes identified are listed in Table 1 and account for 100% of the total organic components in Tank U-105. Nitrous oxide (N{sub 2}O) was the only permanent gas detected in the tank-headspace sample. Tank U-105 is on the Hydrogen Watch List.

  19. Vapor space characterization of Waste Tank 241-TY-104: Results from samples collected on 4/27/95

    SciTech Connect

    Klinger, G.S.; Olsen, K.B.; Clauss, T.W.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-TY-104 (referred to as Tank TY-104). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 8 were observed above the 5-ppbv reporting cutoff. Five tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 94% of the total organic components in Tank TY-104. Nitrous oxide (N{sub 2}O) was the only permanent gas detected in the tank-headspace samples. Tank TY-104 is on the Ferrocyanide Watch List.

  20. Mycobacterium avium subsp. paratuberculosis detection in individual and bulk tank milk samples from bovine herds and caprine flocks.

    PubMed

    Favila-Humara, Lucía C; Chávez-Gris, Gilberto G; Carrillo-Casas, Erika M; Hernández-Castro, Rigoberto

    2010-04-01

    Paratuberculosis, or Johne's disease, is caused by Mycobacterium avium subsp. paratuberculosis (Map), and it generates great economic losses for the dairy industry worldwide. In humans, Map has been associated with Crohn's disease. Mexico has unknown paratuberculosis prevalence, and yet, control programs have not been applied. This study aimed to determine the presence of Map in milk samples from seropositive goats and cows and bulk tank milk samples from herds previously designated Map-infected using indirect enzyme-linked immunosorbent assay. Map DNA was detected in 100% of the bulk tank milk samples of 14 bovine herds and 3 caprine flocks using a modified insertion sequence 900 polymerase chain reaction (PCR). Additionally, Map DNA was detected in 100% of the individual milk samples from 10 cows and 8 goats. Further, based on the findings of the experimental insertion sequence 900 PCR assessment, evaluation of bulk tank and individual milk samples through a type-specific PCR was performed, which confirmed our previous findings and revealed that 56.25% cow and 63.63% goat milk had concurrent infections of the C, I, and S types. Out of 14 bulk tank milk samples, 10 had viable mycobacteria. Paratuberculosis was detected at a high frequency in cow and goat milk, which suggests that raw milk ingestion represents a potential risk of Map infection. PMID:19911881

  1. ANALYSIS OF TANK 28F SALTCAKE CORE SAMPLES FTF-456 - 467

    SciTech Connect

    Martino, C; Daniel McCabe, D; Tommy Edwards, T; Ralph Nichols, R

    2007-02-28

    Twelve LM-75 core samplers from Tank 28F sampling were received by SRNL for saltcake characterization. Of these, nine samplers contained mixtures of free liquid and saltcake, two contained only liquid, and one was empty. The saltcake contents generally appeared wet. A summary of the major tasks performed in this work are as follows: (1) Individual saltcake segments were extruded from the samplers and separated into saltcake and free liquid portions. (2) Free liquids were analyzed to estimate the amount of traced drill-string fluid contained in the samples. (3) The saltcake from each individual segment was homogenized, followed by analysis in duplicate. The analysis used more cost-effective and bounding radiochemical analyses rather than using the full Saltstone WAC suite. (4) A composite was created using an approximately equal percentage of each segment's saltcake contents. Supernatant liquid formed upon creation of the composite was decanted prior to use of the composite, but the composite was not drained. (5) A dissolution test was performed on the sample by contacting the composite with water at a 4:1 mass ratio of water to salt. The resulting soluble and insoluble fractions were analyzed. Analysis focused on a large subset of the Saltstone WAC constituents.

  2. Technical assessment of workplace air sampling requirements at tank farm facilities. Revision 1

    SciTech Connect

    Olsen, P.A.

    1994-09-21

    WHC-CM-1-6 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). It was written to implement DOE N 5480.6 ``US Department of Energy Radiological Control Manual`` as it applies to programs at Hanford which are now overseen by WHC. As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. In addition to WHC-CM-1-6, there is HSRCM-1, the ``Hanford Site Radiological Control Manual`` and several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. This document also provides an evaluation of the compliance of Tank Farms` workplace air sampling program to the criteria, standards, and requirements and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance.

  3. Vapor space characterization of waste tank 241-BY-105: Results from samples collected on 7/7/94

    SciTech Connect

    Pool, K.H.; Ligotke, M.W.; Clauss, T.W.; Lucke, R.B.; McVeety, B.D.; McCulloch, M.; Fruchter, J.S.; Goheen, S.C.

    1995-05-01

    This report describes organic and inorganic results from vapors of the Hanford single-shell waste storage Tank 241-BY-105 (referred to as Tank BY-105). The results described here were obtained to support safety and toxicological evaluations. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. Several organic analytes were quantitatively determined, but quantities of non-TO-14 analytes were only estimated. Approximately 40 tentatively identified organic analytes were observed above the detection limit of (ca.) 10 ppb, but standards for most of these were not available at the time of analysis, and their quantitative determination is beyond the scope of this study. The SUMMA{trademark} Canisters were also analyzed for components listed in U.S. Environmental Protection Agency (EPA) compendium Method TO-14. Of these only a few were observed above the 2-ppb detection limits. These are summarized in Table 3.1. Estimated quantitations also determined were of tentatively identified compounds (TICs). A summary of these results shows quantities of all TICs above the concentration of ca. 10 ppb. This consists of more than 40 organic analytes. The 6 organic analytes with the highest estimated concentrations are shown in Table 1. These 6 analytes account for approximately 45% of the total organic components in Tank BY-105. Detailed descriptions of the results appear in the text. Unlike tanks previously studied, normal paraffin hydrocarbons (NPHs) did not contribute significantly to the total organic concentration of the vapor headspace of Tank BY-105. The total concentration of TICs detected in the tank headspace samples was also much lower than that seen in other reported tanks averaging 6.5 Mg/m{sup 3} for all three canisters collected.

  4. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, And Caustic Wash Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 4 Operations

    SciTech Connect

    Peters, T. B.; Fink, S. D.

    2012-10-25

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), and Caustic Wash Tank (CWT) samples from several of the ?microbatches? of Integrated Salt Disposition Project (ISDP) Salt Batch (?Macrobatch?) 4 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by inductively-coupled plasma emission spectroscopy (ICPES). Furthermore, samples from the CWT have been analyzed by a variety of methods to investigate a decline in the decontamination factor (DF) of the cesium observed at MCU. The results indicate good decontamination performance within process design expectations. While the data set is sparse, the results of this set and the previous set of results for Macrobatch 3 samples indicate generally consistent operations. There is no indication of a disruption in plutonium and strontium removal. The average cesium DF and concentration factor (CF) for samples obtained from Macrobatch 4 are slightly lower than for Macrobatch 3, but still well within operating parameters. The DSSHT samples show continued presence of titanium, likely from leaching of the monosodium titanate in Actinide Removal Process (ARP).

  5. Analysis Of Tank 38H (HTF-38-14-6, 7) And Tank 43H (HTF-43-14-8, 9) Samples For Support Of The Enrichment Control And Corrosion Control Programs

    SciTech Connect

    Martino, C. J.

    2014-02-27

    SRNL performed analysis on Tanks 38H and 43H surface and subsurface supernate samples to support ECP and CCP. The U-235 mass divided by the total U mass ranged from 0.0059 to 0.0060. Uranium concentration ranged from 53.1 mg/L in the Tank 43H surface sample to the 85.1 mg/L in the Tank 38H subsurface sample. The U-235/U and uranium concentration are in line with the prior 2H-Evaporator System ECP samples.

  6. Headspace vapor characterization of Hanford waste Tank 241-BX-110: Results from samples collected on 04/30/96

    SciTech Connect

    Evans, J.C.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-BX-110 (Tank BX-110) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples are also listed in the table. Detailed descriptions of the analytical results appear in the appendices.

  7. Vapor space characterization of waste Tank 241-BY-108: Results from samples collected on 10/27/94

    SciTech Connect

    McVeety, B.D.; Clauss, T.W.; Ligotke, M.W.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-BY-108 (referred to as Tank BY-108). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Trends in NH{sub 3} and H{sub 2}O samples indicated a possible sampling problem. Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, the authors looked for the 40 TO-14 compounds plus an additional 15 analytes. Of these, 17 were observed above the 5-ppbv reporting cutoff. Also, eighty-one organic tentatively identified compounds (TICs) were observed above the reporting cutoff (ca.) 10 ppbv, and are reported with concentrations that are semiquantitative estimates based on internal standard response factors. The nine organic analytes with the highest estimated concentrations are listed in Summary Table 1 and account for approximately 48% of the total organic components in the headspace of Tank BY-108. Three permanent gases, hydrogen (H{sub 2}), carbon dioxide (CO{sub 2}), and nitrous oxide (N{sub 2}O) were also detected. Tank BY-108 is on the Ferrocyanide Watch List.

  8. Vapor space characterization of waste Tank 241-BY-103: Results from samples collected on 11/1/94

    SciTech Connect

    McVeety, B.D.; Klinger, G.S.; Clauss, T.W.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-BY-103 (referred to as Tank BY-103). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Trends in NH{sub 3} and H{sub 2}O samples indicated a possible minor sampling problem. Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for target organic analytes, 39 TO-14 compounds, plus an additional 14 analytes. Of these, four were observed above the 5-ppbv reporting cutoff. Fourteen organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv, and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 88% of the total organic components in Tank BY-103. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected in the tank headspace. Carbon monoxide (CO) and carbon dioxide (CO{sub 2}) were detected in the ambient air sample. Tank BY-103 is on the Ferrocyanide Watch List.

  9. CHARACTERIZATION OF A PRECIPITATE REACTOR FEED TANK (PRFT) SAMPLE FROM THE DEFENSE WASTE PROCESSING FACILITY (DWPF)

    SciTech Connect

    Crawford, C.; Bannochie, C.

    2014-05-12

    A sample of from the Defense Waste Processing Facility (DWPF) Precipitate Reactor Feed Tank (PRFT) was pulled and sent to the Savannah River National Laboratory (SRNL) in June of 2013. The PRFT in DWPF receives Actinide Removal Process (ARP)/ Monosodium Titanate (MST) material from the 512-S Facility via the 511-S Facility. This 2.2 L sample was to be used in small-scale DWPF chemical process cell testing in the Shielded Cells Facility of SRNL. A 1L sub-sample portion was characterized to determine the physical properties such as weight percent solids, density, particle size distribution and crystalline phase identification. Further chemical analysis of the PRFT filtrate and dissolved slurry included metals and anions as well as carbon and base analysis. This technical report describes the characterization and analysis of the PRFT sample from DWPF. At SRNL, the 2.2 L PRFT sample was composited from eleven separate samples received from DWPF. The visible solids were observed to be relatively quick settling which allowed for the rinsing of the original shipping vials with PRFT supernate on the same day as compositing. Most analyses were performed in triplicate except for particle size distribution (PSD), X-ray diffraction (XRD), Scanning Electron Microscopy (SEM) and thermogravimetric analysis (TGA). PRFT slurry samples were dissolved using a mixed HNO3/HF acid for subsequent Inductively Coupled Plasma Atomic Emission Spectroscopy (ICPAES) and Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) analyses performed by SRNL Analytical Development (AD). Per the task request for this work, analysis of the PRFT slurry and filtrate for metals, anions, carbon and base were primarily performed to support the planned chemical process cell testing and to provide additional component concentrations in addition to the limited data available from DWPF. Analysis of the insoluble solids portion of the PRFT slurry was aimed at detailed characterization of these solids (TGA, PSD

  10. Tank 241-S-111 08/1999 Compatibility Grab Samples and Analytical Results for the Final Report [SEC 1 and SEC 2

    SciTech Connect

    STEEN, F.H.

    1999-12-01

    This document is the format IV, final report for the tank 241-S-111 (S-111) grab samples taken in August 1999 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank S-111 samples were performed as directed in Compatibility Grab Sampling and Analysis Plan for Fiscal Year 1999 (Sasaki 1999a,b). Any deviations from the instructions provided in the tank sampling and analysis plan (TSAP) were discussed in this narrative. The notification limit for {sup 137}Cs was exceeded on two samples. Results are discussed in Section 5.3.2. No other notification limits were exceeded.

  11. Vapor space characterization of waste Tank 241-B-103: Results from samples collected on 2/8/95

    SciTech Connect

    Ligotke, M.W.; Pool, K.H.; Lucke, R.B.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-B-103 (referred to as Tank B-103). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, five were observed above the 5-ppbv reporting cutoff. Twenty-six organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv, and are reported with concentrations that are semiquantitative estimates based on internal standard response factors. Twenty-three TICs were measured in two or more SUMMA{trademark} canisters. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 66% of the total organic components in Tank BB-103. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected. Tank B-103 is on the Organic Watch List.

  12. Vapor space characterization of Waste Tank 241-TY-104 (in situ): Results from samples collected on 8/5/94

    SciTech Connect

    Ligotke, M.W.; Pool, K.H.; Lucke, R.B.

    1995-10-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the headspace of the Hanford waste storage Tank 241-TY-104 (referred to as Tank TY-104). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not performed. In addition, the authors looked for the 39 TO-14 compounds plus an additional 14 analytes. Of these, eight were observed above the 5-ppbv reporting cutoff. Twenty-four organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 86% of the total organic components in Tank TY-104. Tank TY-104 is on the Ferrocyanide Watch List.

  13. Vapor space characterization of waste Tank 241-SX-106: Results from samples collected on 3/24/95

    SciTech Connect

    Klinger, G.S.; Clauss, T.W.; Litgotke, M.W.

    1995-11-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-SX-106 (referred to as Tank SX-106). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 4 were observed above the 5-ppbv reporting cutoff. Three tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 7 organic analytes identified are listed in Table 1 and account for approximately 100% of the total organic components in Tank SX-106. Carbon dioxide (CO{sub 2}) was the only permanent gas detected. Tank SX-106 is on the Ferrocyanide Watch List.

  14. Vapor space characterization of waste Tank 241-U-103: Results from samples collected on 2/15/95

    SciTech Connect

    Ligotke, M.W.; Pool, K.H.; Clauss, T.W.; McVeety, B.D.; Klinger, G.S.; Olsen, K.B.; Bredt, O.P.; Fruchter, J.S.; Goheen, S.C.

    1995-11-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-U-103 (referred to as Tank U-103). The results described her were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 11 were observed above the 5-ppbv reporting cutoff. Eleven tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 90% of the total organic components in Tank U-103. Two permanent gases, hydrogen (H{sub 2}) and nitrous oxide (N{sub 2}O), were also detected. Tank U-103 is on the Hydrogen Watch List.

  15. Vapor space characterization of Waste Tank 241-S-111: Results from samples collected on 3/21/95

    SciTech Connect

    Klinger, G.S.; Clauss, T.W.; Ligotke, M.W.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-S-111 (referred to as Tank S-111). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, seven were observed above the 5-ppbv reporting cutoff. Five tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 98% of the total organic components in Tank S-111. Two permanent gases, hydrogen (H{sub 2}) and nitrous oxide (N{sub 2}O), were also detected. Tank S-111 is on the Hydrogen Watch List.

  16. Vapor space characterization of waste Tank 241-TY-101: Results from samples collected on 4/6/95

    SciTech Connect

    Klinger, G.S.; Clauss, T.W.; Ligotke, M.W.; Pool, K.H.; McVeety, B.D.; Olsen, K.B.; Bredt, O.P.; Fruchter, J.S.; Goheen, S.C.

    1995-11-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-TY-101 (referred to as Tank TY-101). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Off these, 5 were observed above the 5-ppbv reporting cutoff. One tentatively identified compound (TIC) was observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The six organic analyses identified are listed in Table 1 and account for approximately 100% of the total organic components in Tank TY-101. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected. Tank TY-101 is on the Ferrocyanide Watch List.

  17. Vapor space characterization of waste Tank 241-BY-104 (in situ): Results from samples collected on 4/22/94

    SciTech Connect

    Pool, K.H.; Ligotke, M.W.; Clauss, T.W.; Lucke, R.B.; McVeety, B.D.; Sharma, A.K.; McCulloch, M.; Fruchter, J.S.; Goheen, S.C.

    1995-10-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the space of the Hanford waste storage Tank 241-BY-104 (referred to as Tank BY-104). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds NH{sub 3}, NO{sub 2}, NO, HCN, and H{sub 2}O. Sampling for sulfur oxides was not requested. Several organic compounds were also quantitatively determined. Eighty-nine tentatively identified organic analytes were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semi-quantitative estimates. In addition, the 41 standard TO 14 analytes were sought. Of these, only a few were observed above the 2-ppbv detection limit. The 10 organic analytes with the highest estimated concentrations are listed in Table 1. These 10 analytes account for approximately 48% of the total organic components in the headspace of Tank BY-104. Detailed results appear in the text. Tank BY-104 is on the Ferrocyanide Watch List.

  18. Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

    SciTech Connect

    Brown, G.N.; Bray, L.A.; Carlson, C.D.

    1996-01-01

    Pacific Northwest National Laboratory (Northwest National Laboratory) conducted this study as a joint effort between the ``Develop and Test Sorbents`` task for the Efficient Separations and Processing Cross-Cutting Program (ESP) and the ``Batch Testing of Crystalline Silico-Titanates (CSTs)`` subtask, which is part of the Northwest National Laboratory Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project. The objective of the study is to investigate radionuclide uptake of the newly produced CST materials under a variety of solution conditions and to compare the results obtained for this material with those obtained for other commercial and experimental exchangers.

  19. Analysis of Tank 38H (HTF-38-15-47, 49) and Tank 43H (HTF-43-15-51, 53) surface and subsurface supernatant samples in support of enrichment and corrosion control programs

    SciTech Connect

    Oji, L. N.

    2015-06-30

    This report provides the results of analyses on Tanks 38H and 43H surface and subsurface supernatant liquid samples in support of the Enrichment Control Program (ECP) and the Corrosion Control Program (CCP).

  20. Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    SciTech Connect

    Evans, S.K.

    2002-01-31

    This Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about sampling design, required analyses, and sample collection and handling procedures, is to be used in conjunction with the Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System.

  1. Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    SciTech Connect

    Evans, Susan Kay; Orchard, B. J.

    2002-01-01

    This Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about sampling design, required analyses, and sample collection and handling procedures, is to be used in conjunction with the Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System.

  2. RESULTS FOR THE THIRD QUARTER 2007 TANK 50H WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    SciTech Connect

    Zeigler, K; Ned Bibler, N

    2008-07-11

    The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low activity wastewater streams from the Effluent Treatment Project (ETP), H-Canyon, and the high level waste (HLW) storage tanks, are stored as a mixture in Tank 50H until it can be pumped to the Saltstone Facility for treatment and disposal. Specific waste acceptance criteria (WAC) must be met for the transfer of low-level aqueous waste from Tank 50H to the Saltstone Facility. Low level waste which meets the WAC can be transferred, stored and treated in the Saltstone Production Facility (SPF) for subsequent disposal as saltstone in the Saltstone Disposal Facility (SDF). Waste Solidification Engineering (WSE) has requested through a Technical Task Request (TTR) that the Savannah River National Laboratory (SRNL) measure the concentrations of chemical and radionuclide contaminants listed in the currently approved Saltstone Waste Acceptance Criteria (WAC). A Task Technical and Quality Assurance Plan and Analytical Study Plan has been written for this request. WAC determinations are needed on a quarterly basis for chemical contaminants and every first and third quarter for radioactive contaminants. This memorandum presents the results for the chemical and radionuclide contaminants in the third quarter, from the samples taken from Tank 50 in September, 2007.

  3. Tank 241-C-103 vapor and gas sampling Data Quality Objectives

    SciTech Connect

    Osborne, J.W.; Huckaby, J.L.; Rudolph, T.P.; Hewitt, E.R.; Mahulum, D.D.; Young, J.Y.; Anderson, C.M.

    1994-02-28

    Two problems are addressed in this report: Potential flammability of gases, vapors, and an aerosol in tank 241-C-103 (hereafter identified as C-103) and potential worker health and safety hazards associated with the toxicity of constituents in C-103. Previous work indicated the potential presence of a fog in the tank, and the fuel content of the tank gases, vapors, and aerosol may be too high to permit work in the tank. Ten reports of adverse health effects associated with vapor exposures near C-103 or in C-Farm have been made by workers. Reported symptoms include headaches, burning sensations in nose and throat, nausea, and impaired pulmonary function. Data are needed to identify and quantify constituents of the C-103 headspace to address potential vapor toxicity. When the compounds of toxicological interest in the tank headspace are identified, industry hygienists can assess ``worst-case`` worker exposure levels and focus their industrial hygiene monitoring strategy on these target compounds. Final recommendations on the required level of personal protective equipment will be based on the worker breathing zone levels of these chemicals.

  4. Vapor space characterization of waste tank 241-BY-103 (in situ): Results from samples collected on May 5, 1994

    SciTech Connect

    Ligotke, M.W.; Sharma, A.K.; McVeety, B.D.; Fruchter, J.S.; Pool, K.H.; Lucke, R.B.; McCulloch, M.; Goheen, S.C.

    1995-06-01

    This document presents the details of the inorganic and organic analysis that was performed on samples from the headspace of Hanford waste tank 241-BY-103. The results described were obtained to support the safety and toxicological evaluations. A summary of the results for the inorganic and organic analytes is included, as well as, a detailed description of the results which appears in the text.

  5. Vapor space characterization of waste tank 241-TY-103 (in situ): Results from samples collected on August 5, 1994

    SciTech Connect

    Pool, K.H.; McVeety, B.D.; Clauss, T.W.

    1995-06-01

    This document presents the details of the inorganic and organic analysis that was performed on samples from the headspace of Hanford waste tank 241-TY-103. The results described were obtained to support the safety and toxicological evaluations. A summary of the results for the inorganic and organic analytes is included, as well as, a detailed description of the results which appears in the text.

  6. Results of Fall 1994 sampling of gunite and associated tanks at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-06-01

    This Technical Memorandum, was developed under Work Breakdown Structure 1.4.12.6.1.01.41.12.02. 11 (Activity Data Sheet 3301, ``WAG 1``). This document provides the Environmental Restoration Program with analytical results from liquid and sludge samples from the Gunite and Associated Tanks (GAAT). Information provided in this report forms part of the technical basis for criticality safety, systems safety, engineering design, and waste management as they apply to the GAAT treatability study and remediation.

  7. SLUDGE BATCH 7 PREPARATION TANK 4 AND 12 CHARACTERIZATION

    SciTech Connect

    Bannochie, C.; Click, D.; Pareizs, J.

    2010-05-21

    Samples of PUREX sludge from Tank 4 and HM sludge from Tank 12 were characterized in preparation for Sludge Batch 7 (SB7) formulation in Tank 51. SRNL analyses on Tank 4 and Tank 12 were requested in separate Technical Assistance Requests (TAR). The Tank 4 samples were pulled on January 19, 2010 following slurry operations by F-Tank Farm. The Tank 12 samples were pulled on February 9, 2010 following slurry operations by H-Tank Farm. At the Savannah River National Laboratory (SRNL), two 200 mL dip samples of Tank 4 and two 200 mL dip samples of Tank 12 were received in the SRNL Shielded Cells. Each tank's samples were composited into clean 500 mL polyethylene storage bottles and weighed. The composited Tank 4 sample was 428.27 g and the composited Tank 12 sample was 502.15 g. As expected there are distinct compositional differences between Tank 4 and Tank 12 sludges. The Tank 12 slurry is much higher in Al, Hg, Mn, and Th, and much lower in Fe, Ni, S, and U than the Tank 4 slurry. The Tank 4 sludge definitely makes the more significant contribution of S to any sludge batch blend. This S, like that observed during SB6 washing, is best monitored by looking at the total S measured by digesting the sample and analyzing by inductively coupled plasma - atomic emission spectroscopy (ICPAES). Alternatively, one can measure the soluble S by ICP-AES and adjust the value upward by approximately 15% to have a pretty good estimate of the total S in the slurry. Soluble sulfate measurements by ion chromatography (IC) will be biased considerably lower than the actual total S, the difference being due to the non-sulfate soluble S and the undissolved S. Tank 12 sludge is enriched in U-235, and hence samples transferred into SRNL from the Tank Farm will need to be placed on the reportable special nuclear material inventory and tracked for total U per SRNL procedure requirements.

  8. Evaluation of a gas chromatograph with a novel surface acoustic wave detector (SAW GC) for screening of volatile organic compounds in Hanford waste tank samples

    SciTech Connect

    Lockrem, L.L.

    1998-01-12

    A novel instrument, a gas chromatograph with a Surface Acoustic Wave Detector (SAW GC), was evaluated for the screening of organic compounds in Hanford tank headspace vapors. Calibration data were developed for the most common organic compounds, and the accuracy and precision were measured with a certified standard. The instrument was tested with headspace samples collected from seven Hanford waste tanks.

  9. Flammable gas tank safety program: Data requirements for core sample analysis developed through the Data Quality Objectives (DQO) process. Revision 1

    SciTech Connect

    McDuffie, N.G.; LeClair, M.D.

    1995-04-28

    This document represents the application of the Data Quality Objectives (DQO) process to the Flammable Gas Tank Safety Issue at the Hanford Site. The product of this effort is a list of data required from tank core sample analysis to support resolution of this issue.

  10. Miscellaneous data for the 1996--1997 sampling and analysis campaigns of the MVST, BVEST, and OHF tank complexes

    SciTech Connect

    Giaquinto, J.M.; Keller, J.M.; Mills, T.P.

    1997-07-01

    Starting in 1996 and continuing into 1997, there were several major sampling and analysis campaigns undertaken to characterize the contents of the Active Liquid Low-Level Waste (LLLW) tanks located at ORNL and the Old Hydrofracture Facility (OHF) tanks located in Melton Valley within Waste Area Grouping (WAG) 5. The active LLLW tanks include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data obtained for these campaigns are summarized in three earlier ORNL technical reports. Included in these reports are data which addresses waste processing options, performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP), criticality concerns, and DOT requirements for transporting the waste. Also, included is an evaluation of the waste`s characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS). As part of these campaigns there were also other miscellaneous tests performed and data collected to address important engineering and remediation issues that were not included in the previous reports. These miscellaneous tests are summarized in this report and include (1) fusion preparations for total anion analysis on selected MVST, BVEST, and OHF sludges, (2) settling tests performed on the BVEST and OHF sludges, (3) dried density data for the MVST sludges, (4) particle size analysis on selected BVEST and OHF sludges, and (5) the analysis of hydroxylamine in the BVEST supernates and sludges. Also, the viscosity and flow curves for BVEST waste are restated in this report using apparent viscosity with further detail included about the flow characteristics that were observed.

  11. Tank 241-AP-106, grab samples, 6AP-96-1 through 6AP-96-3 analytical results for the final report

    SciTech Connect

    Esch, R.A., Westinghouse Hanford

    1996-12-11

    This document is the final report for tank 241-AP-106 grab samples. This document presents the analytical results for three samples (6AP-96-1, 6AP-96-2 and 6AP-96-3) taken from riser 1 @ 150{degrees} of tank 241-AP-1 06 on September 12, 1996. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1996) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Fowler, 1995).

  12. Tank 241-AN-101, grab samples, 1AN-98-1, 1AN-98-2 and 1AN-98-3 analytical results for the final report

    SciTech Connect

    FULLER, R.K.

    1999-02-24

    This document is the final report for tank 241-AN-101 grab samples. Three grab samples 1AN-98-1, 1AN-98-2 and 1AN-98-3 were taken from riser 16 of tank 241-AN-101 on April 8, 1998 and received by the 222-S Laboratory on April 9, 1998. Analyses were performed in accordance with the ''Compatability Grab Sampling and Analysis Plan'' (TSAP) and the ''Data Quality Objectives for Tank Farms Waste Compatability Program'' (DQO). The analytical results are presented in the data summary report. No notification limits were exceeded.

  13. Biosafety and containment plan & design for direct sampling of operating effluent decontamination tanks

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Currently, Southeast Poultry Research Laboratory (SEPRL) uses an effluent decontamination system (EDS) that serves as an enhancement, or extra barrier for biocontainment. Wastewater effluent from (A)BSL-3E and (A)BSL-2E laboratories is collected in tanks for thermal inactivation (180°F for 30 minut...

  14. Vapor space characterization of waste Tank 241-C-108: Results from samples collected through the vapor sampling system on 8/5/94

    SciTech Connect

    Lucke, R.B.; Ligotke, M.W.; Pool, K.H.; Clauss, T.W.; Sharma, A.K.; McVeety, B.D.; McCulloch, M.; Fruchter, J.S.; Goheen, S.C.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-C-108 (referred to as Tank C-108). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. Organic compounds were also quantitatively determined. Two organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, the authors looked for the 41 standard TO-14 analytes. Of these, only a few were observed above the 2-ppbv detection limit. The five organic analytes with the highest estimated concentrations are listed in Table 1. The five analytes account for approximately 85% of the total organic components in Tank C-108.

  15. Vapor space characterization of waste Tank 241-C-107: Results from samples collected on 9/29/94

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Ligotke, M.W.

    1995-11-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-C-107 (referred to as Tank C-107). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water vapor (H{sub 2}O). Sampling for sulfur oxides (SO{sub x}) was not requested. Organic compounds were also quantitatively determined. Twenty organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, the authors looked for the 55 TO-14 extended analytes. Of these, 3 were observed above the 5-ppbv detection limit. The 10 organic analytes with the highest estimated concentrations are listed in Summary Table 1 and account for approximately 96% of the total organic components in Tank C-107. Two permanent gases, carbon dioxide and nitrous oxide, were also detected.

  16. Vapor space characterization of waste tank 241-S-102: Results from samples collected on 3/14/95

    SciTech Connect

    Pool, K.H.; McVeety, B.D.; Clauss, T.W.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-S-102 (referred to as Tank S-102). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 11 were observed above the 5-ppbv reporting cutoff. Eleven tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 95% of the total organic components in Tank S-102. Two permanent gases, hydrogen (H{sub 2}) and nitrous oxide (N{sub 2}O), were also detected.

  17. Vapor space characterization of waste tank 241-TX-118: Results from samples collected on 12/16/94

    SciTech Connect

    Lucke, R.B.; Ligotke, M.W.; McVeety, B.D.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-TX-118 (referred to as Tank TX-118). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 3 were observed above the 5-ppbv reporting cutoff. Twenty three organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv, and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 84% of the total organic components in Tank TX-118. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected.

  18. Vapor space characterization of waste tank 241-C-112: Results from samples collected on 8/11/94

    SciTech Connect

    Ligotke, M.W.; McVeety, B.D.; Pool, K.H.

    1995-10-01

    This report describes organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-C-112 (referred to as Tank C-112). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. Organic compounds were also quantitatively determined. Five organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, we looked for the 40 standard TO-14 analytes. None were observed above the 2-ppbv detection limit. The five organic analytes with the highest concentration are listed in Table 1 and account for 100% of the total organic components in Tank C-112.

  19. Vapor space characterization of waste tank 241-BX-104: Results from samples collected on 12/30/94

    SciTech Connect

    Pool, K.H.; Ligotke, M.W.; McVeety, B.D.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-BX-104 (referred to as Tank BX-104). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained. for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SOx) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 13 were observed above the 5-ppbv reporting cutoff. Sixty-six organic tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes, with the highest estimated concentrations are listed in Table 1 and account for approximately 70% of the total organic components in Tank BX-104. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected.

  20. Vapor space characterization of waste tank 241-BY-110: Results for samples collected on 11/11/94

    SciTech Connect

    Clauss, T.W.; Ligotke, M.W.; Pool, K.H.

    1995-06-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-BY-110 (referred to as Tank BY-110). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}, nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, we looked for the 40 TO-14 compounds plus an additional 15 analytes. Of these, 10 were observed above the 5-ppbv reporting cutoff. Forty-six organic tentatively identified compounds (TICS) were observed above the reporting cutoff of (ca.) 10 ppbv, and are reported with concentrations that are semiquantative estimates based on internal standard response factors. The 10 organic analytes with the highest estimated concentrations are listed and account for approximately 78% of the total organic components in Tank BY-110. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected.

  1. Vapor space characterization of waste tank 241-TY-103: Results from samples collected on 4/11/95

    SciTech Connect

    Ligotke, M.W.; Clauss, T.W.; Pool, K.H.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-TY-103 (referred to as Tank TY-103). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. In addition, quantitative results were obtained for the 39 TO-14 compounds plus an additional 14 analytes. Of these, 16 were observed above the 5-ppbv reporting cutoff. Sixteen tentatively identified compounds (TICs) were observed above the reporting cutoff of (ca.) 10 ppbv and are reported with concentrations that are semiquantitative estimates based on internal-standard response factors. The 10 organic analytes with the highest estimated concentrations are listed in Table 1 and account for approximately 95% of the total organic components in Tank TY-103. Two permanent gases, carbon dioxide (CO{sub 2}) and nitrous oxide (N{sub 2}O), were also detected.

  2. Vapor space characterization of waste tank 241-BY-109 (in situ): Results from samples collected on 9/22/94

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Ligotke, M.W.

    1995-06-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the headspace of the Hanford waste storage Tank 241-BY-109 (referred to as Tank BY-109). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Summary Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. Organic compounds were also quantitatively determined. Twenty-three organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, we looked for the 40 standard TO-14 analytes. We observed 38. Of these, only a few were observed above the 2-ppbv calibrated instrument detection limit. The ten organic analytes with the highest estimated concentrations are listed in Summary Table 1. The ten analytes account for approximately 84% of the total organic components in Tank BY-109.

  3. Vapor space characterization of waste Tank 241-C-111 (in situ): Results from samples collected on 6/20/94

    SciTech Connect

    Ligotke, M.W.; Pool, K.H.; Lucke, R.B.; McVeety, B.D.; Clauss, T.W.; McCulloch, M.; Young, J.S.; Fruchter, J.S.; Goheen, S.C.

    1995-10-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the headspace of the Hanford waste storage Tank 241-C-111 (referred to as Tank C-111). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Summary Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), hydrogen cyanide (HCN), and water vapor (H{sub 2}O). Sampling for sulfur oxides was not requested. Organic compounds were quantitatively determined. Five organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, the authors looked for the 40 standard TO-14 analytes and observed 39. None of these compounds were above the 2-ppbv calibrated instrumental detection limit. However, it is believed that the detection of dichlorodifluoromethane and methyl benzene are real at these low concentrations. The five organic analytes with the highest estimated concentrations are listed in Summary Table 1. The five analytes account for approximately 100% of the total organic components in Tank C-111.

  4. Sampling and analysis plan for the gunite and associated tanks interim remedial action, wall coring and scraping at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1998-02-01

    This Sampling and Analysis Plan documents the procedures for collecting and analyzing wall core and wall scraping samples from the Gunite and Associated Tanks. These activities are being conducted to support the Comprehensive Environmental Response, Compensation, and Liability Act at the gunite and associated tanks interim remedial action at Oak Ridge National Laboratory in Oak Ridge, Tennessee. The sampling and analysis activities will be performed in concert with sludge retrieval and sluicing of the tanks. Wall scraping and/or wall core samples will be collected from each quadrant in each tank by using a scraping sampler and/or a coring drill deployed by the Houdini robot vehicle. Each sample will be labeled, transported to the Radioactive Materials Analytical Laboratory, and analyzed for physical and radiological characteristics, including total activity, gross alpha, gross beta, radioactive strontium and cesium, and other alpha- and gamma-emitting radionuclides. The data quality objectives process, based on US Environmental Protection Agency guidance, was applied to identify the objectives of this sampling and analysis. The results of the analysis will be used to (1) validate predictions of a strontium concrete diffusion model, (2) estimate the amount of radioactivity remaining in the tank shells, (3) provide information to correlate with measurements taken by the Gunite Tank Isotope Mapping Probe and the Characterization End Effector, and (4) estimate the performance of the wall cleaning system. This revision eliminates wall-scraping samples from all tanks, except Tank W-3. The Tank W-3 experience indicated that the wall scrapper does not collect sufficient material for analysis.

  5. Waste compatibility and final report for Tank 241-A-101, Grab Samples 1A-96-1, 1A-96-2, and 1A-96-3

    SciTech Connect

    Steen, F.H., Westinghouse Hanford

    1996-07-25

    This document is the final report deliverable for tank 241-A- 101 grab samples. Three grab samples (IA-96-1, IA-96-2 and IA-96-3) were taken from riser 4 of tank 241-A-101. Samples were collected on April 3, 1996 and received by the 222-S Laboratory on April 4, 1996. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO). The samples were subsampled and analyzed in accordance with the TSAP. Two of the three grab samples contained a significant amount of solids and special analyses were requested. None of the samples exceeded notification limits. No similarities in sample appearance were noted; this could be an explanation for the varying analytical results. Quality control issues are discussed in each analytical subheading. The raw data for all analyses are included in this report.

  6. An automated gas exchange tank for determining gas transfer velocities in natural seawater samples

    NASA Astrophysics Data System (ADS)

    Schneider-Zapp, K.; Salter, M. E.; Upstill-Goddard, R. C.

    2014-07-01

    In order to advance understanding of the role of seawater surfactants in the air-sea exchange of climatically active trace gases via suppression of the gas transfer velocity (kw), we constructed a fully automated, closed air-water gas exchange tank and coupled analytical system. The system allows water-side turbulence in the tank to be precisely controlled with an electronically operated baffle. Two coupled gas chromatographs and an integral equilibrator, connected to the tank in a continuous gas-tight system, allow temporal changes in the partial pressures of SF6, CH4 and N2O to be measured simultaneously in the tank water and headspace at multiple turbulence settings, during a typical experimental run of 3.25 h. PC software developed by the authors controls all operations and data acquisition, enabling the optimisation of experimental conditions with high reproducibility. The use of three gases allows three independent estimates of kw for each turbulence setting; these values are subsequently normalised to a constant Schmidt number for direct comparison. The normalised kw estimates show close agreement. Repeated experiments with Milli-Q water demonstrate a typical measurement accuracy of 4% for kw. Experiments with natural seawater show that the system clearly resolves the effects on kw of spatial and temporal trends in natural surfactant activity. The system is an effective tool with which to probe the relationships between kw, surfactant activity and biogeochemical indices of primary productivity, and should assist in providing valuable new insights into the air-sea gas exchange process.

  7. An automated gas exchange tank for determining gas transfer velocities in natural seawater samples

    NASA Astrophysics Data System (ADS)

    Schneider-Zapp, K.; Salter, M. E.; Upstill-Goddard, R. C.

    2014-02-01

    In order to advance understanding of the role of seawater surfactants in the air-sea exchange of climatically active trace gases via suppression of the gas transfer velocity (kw), we constructed a fully automated, closed air-water gas exchange tank and coupled analytical system. The system allows water-side turbulence in the tank to be precisely controlled with an electronically operated baffle. Two coupled gas chromatographs and an integral equilibrator, connected to the tank in a continuous gas-tight system, allow temporal changes in the partial pressures of SF6, CH4 and N2O to be measured simultaneously in the tank water and headspace at multiple turbulence settings, during a typical experimental run of 3.25 h. PC software developed by the authors controls all operations and data acquisition, enabling the optimisation of experimental conditions with high reproducibility. The use of three gases allows three independent estimates of kw for each turbulence setting; these values are subsequently normalised to a constant Schmidt number for direct comparison. The normalised kw estimates show close agreement. Repeated experiments with MilliQ water demonstrate a typical measurement accuracy of 4% for kw. Experiments with natural seawater show that the system clearly resolves the effects on kw of spatial and temporal trends in natural surfactant activity. The system is an effective tool with which to probe the relationships between kw, surfactant activity and biogeochemical indices of primary productivity, and should assist in providing valuable new insights into the air-sea gas exchange process.

  8. Analysis of tank 51H (HTF-51-15-77) subsurface supernatant sample in support of enrichment and corrosion control programs

    SciTech Connect

    Oji, L. N.

    2015-08-18

    This report provides the results of analyses on Tank 51H subsurface supernatant liquid sample in support of the Enrichment Control Program (ECP) and the Corrosion Control Program (CCP).The purpose of the ECP sample taken from Tank 51H in early June was to determine if the later decants would be “acceptable feed” to the 2H and 3H evaporator systems.

  9. Analysis of tank 51H (HTF-51-15-77) subsurface supernatant sample in support of enrichment and corrosion control programs

    SciTech Connect

    Oji, L. N.

    2015-08-18

    This report provides the results of analyses on Tank 51H subsurface supernatant liquid sample in support of the Enrichment Control Program (ECP) and the Corrosion Control Program (CCP). The purpose of the ECP sample taken from Tank 51H in early June was to determine if the later decants would be “acceptable feed” to the 2H and 3H evaporator systems.

  10. Analysis of tank 4 (FTF-4-15-22, 23) surface and subsurface supernatant samples in support of enrichment control, corrosion control and evaporator feed qualification programs

    SciTech Connect

    Oji, L. N.

    2015-09-09

    This report provides the results of analyses on Savannah River Site Tank 4 surface and subsurface supernatant liquid samples in support of the Enrichment Control Program (ECP), the Corrosion Control Program (CCP) and the Evaporator Feed Qualification (EFQ) Program. The purpose of the ECP sample taken from Tank 4 in August 2015 was to determine if the supernatant liquid would be “acceptable feed” to the 2H and 3H evaporator systems.

  11. Vapor space characterization of waste Tank 241-C-109 (in situ): Results from samples collected on 6/23/94

    SciTech Connect

    Clauss, T.W.; Ligotke, M.W.; Pool, K.H.; Lucke, R.B.; McVeety, B.D.; Sharma, A.K.; McCulloch, M.; Fruchter, J.S.; Goheen, S.C.

    1995-10-01

    This report describes organic analyses results from in situ samples obtained from the headspace of the Hanford waste storage Tank 241-C-109 (referred to as Tank C-109). The results described here were obtained to support safety and toxicological evaluations. Organic compounds were quantitatively determined. Thirteen organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, the authors looked for the 40 standard TO-14 analytes. Of these, only one was observed above the 2-ppbv calibrated instrumental detection limit. However, it is believed, even though the values for dichlorodifluoromethane and trichlorofluoromethane are below the instrumental detection limit, they are accurate at these low concentrations. The six analytes account for approximately 100% of the total organic components in Tank C-109. These six organic analytes with the highest estimated concentrations are listed in Summary Table 1. Detailed descriptions of the results appear in the text.

  12. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-13-189, MCU-13-190, AND MCU-13-191: QUARTERLY SAMPLE FROM SEPTEMBER 2013

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2013-10-31

    Savannah River National Laboratory (SRNL) analyzed solvent samples from Modular Caustic-Side Solvent Extraction Unit (MCU) in support of continuing operations. A quarterly analysis of the solvent is required to maintain solvent composition within specifications. Analytical results of the analyses of Solvent Hold Tank (SHT) samples MCU-13-189, MCU-13-190, and MCU-13-191 received on September 4, 2013 are reported. The results show that the solvent (remaining heel in the SHT tank) at MCU contains excess Isopar L and a deficit concentration of modifier and trioctylamine when compared to the standard MCU solvent. As with the previous solvent sample results, these analyses indicate that the solvent does not require Isopar L trimming at this time. Since MCU is switching to NGS, there is no need to add TOA nor modifier. SRNL also analyzed the SHT sample for {{sup 137}Cs content and determined the measured value is within tolerance and the value has returned to levels observed in 2011.

  13. Separation and identification of carboxylic acids in MALT samples from the headspace gases in Hanford tank 103C

    SciTech Connect

    Clauss, S.A.; Lucke, R.B.

    1993-08-01

    Samples of headspace gases from Westinghouse Hanford Company (WHC) waste storage tank 103C were analyzed by gas chromatography/mass spectrometry by Pacific Northwest Laboratory staff. The samples were obtained using a cryo-trap sampler designed by WHC and known as the Mobile Analytical Laboratory Trap (MALT). The samples, which were obtained in September 1989, were available in large amounts (200 mi). The specific targets for this analysis were n-butyric, i-butyric, n-valeric, and i-valeric organic acids. Of the acids targeted, only n-butyric was found, and only trace amounts of it were detected with a detection limit below 1 ppM in the extract. The levels found were so low as to cause difficulty in quantitation. All concentrations reported here are for the methanol extract solutions and not the concentrations in the headspace of tank 103C. To calculate concentrations in the headspace, the MALT sampling volume and the methanol rinse volume must be obtained from the MALT personnel at WHC.

  14. Tank 241-AP-107, grab samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 analytical results for the final report

    SciTech Connect

    Steen, F.H.

    1997-12-22

    This document is the final report for tank 241-AP-107 grab samples. Three grab samples were collected from riser 1 on September 11, 1997. Analyses were performed on samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Nuier, 1997). The analytical results are presented in the data summary report (Table 1). A notification was made to East Tank Farms Operations concerning low hydroxide in the tank and a hydroxide (caustic) demand analysis was requested. The request for sample analysis (RSA) (Attachment 2) received for AP-107 indicated that the samples were polychlorinated biphenyl (PCB) suspects. Therefore, prior to performing the requested analyses, aliquots were made to perform PCB analysis in accordance with the 222-S Laboratory administrative procedure, LAP-101-100. The results of this analysis indicated that no PCBs were present at 50 ppm and analysis proceeded as non-PCB samples. The results and raw data for the PCB analysis will be included in a revision to this document. The sample breakdown diagrams (Attachment 1) are provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed.

  15. Exploratory tests of washing radioactive sludge samples from the Melton Valley and evaporator facility storage tanks at ORNL

    SciTech Connect

    Sears, M.B.; Botts, J.L.; Keller, J.M.

    1991-09-01

    Exploratory tests were initiated to wash radioactive sludge samples from the waste storage tanks at the Oak Ridge National Laboratory (ORNL). The purpose was to provide preliminary information about (1) the anions in the sludge phase that are soluble in water or dilute acid (e.g., the anions in the interstitial liquid) and (2) the solubilities of sludge constituents in water under process conditions. The experiments were terminated before completion due to changing priorities by the Department of Energy (DOE). This memorandum was prepared primarily for documentation purposes and presents the incomplete data. 3 refs., 13 tabs.

  16. Flammable Gas Safety Program: analysis of gas sampling probe locations in the SX-farm flammable gas watchlist tanks

    SciTech Connect

    McLaren, J.M.; Claybrook, S.W.

    1995-09-01

    An analysis was performed to determine the optimum ventilation line up for the AN Tank Farm. The analysis used the postulated maximum historical GRE in tanks AN-103, -104, and -105. Tank AN-104 was found to be limiting. The results of the analysis show that an airflow of 250 cfm through tanks 241-AN-103, -104, and -105 with an airflow of 100 cfm through tanks 241-AN-101, -102, -106, and -107 would be the optimum ventilation lineup.

  17. Analysis of tank 39H (HTF-39-15-61, 62) surface and subsurface supernatant samples in support of corrosion control program

    SciTech Connect

    Oji, L. N.

    2015-08-01

    This report provides the results of analyses on Tanks 39H surface and subsurface supernatant liquid samples in support of the Corrosion Control Program. Analyses included warm acid strike preparation followed by analysis for silicon, aluminum, and sodium and water dilution preparation followed by analysis for anions. Other reported analytical results include analyses results for uranium, Pu-241 and Pu-239. The measured sodium concentration averaged, respectively, 4.28E+00 ± 9.30E-02 M and 4.32E+00 ± 1.076E-01 M in the Tank 39H surface sample and Tank 39H subsurface sample. In general, the nitrate, nitrite, free-OH and specific gravity of the Tank 39H surface and subsurface samples were all about the same in magnitude, respectively, averaging 1.98 M, 0.314 M, 1.26 M and 1.24. The measured silicon concentration for the Tank 39H surface and subsurface samples were, respectively, 3.84E+01± 5.51E+00 and 4.14E+01± 1.17E+00 mg/L. Based on the uranium, Pu-241 and Pu-239 concentrations, the calculated U-235 equivalent is 21.41 wt% for the surface sample and 21.32 wt% for the subsurface sample.

  18. Sampling and analysis of inactive radioactive waste tanks W-17, W-18, WC-5, WC-6, WC-8, and WC-11 through WC-14 at ORNL

    SciTech Connect

    Sears, M.B.; Giaquinto, J.M.; Griest, W.H.; Pack, R.T.; Ross, T.; Schenley, R.L.

    1995-12-01

    The sampling and analysis of nine inactive liquid low-level waste (LLLW) tanks at the Oak Ridge National Laboratory (ORNL) are described-tanks W-17, W-18, WC-5, WC-6, WC-8, and WC-11 through WC-14. Samples of the waste tank liquids and sludges were analyzed to determine (1) the major chemical constituents, (2) the principal radionuclides, (3) metals listed on the US Environmental Protection Agency (EPA) Contract Laboratory Program Inorganic Target Analyte List, (4) organic compounds, and (5) some physical properties. The organic chemical characterization consisted of determinations of the EPA Contract Laboratory Program Target Compound List volatile and semivolatile compounds, pesticides, and polychlorinated biphenyis (PCBs). This report provides data (1) to meet requirements under the Federal Facility Agreement (FFA) for the Oak Ridge Reservation to characterize the contents of LLLW tanks which have been removed from service and (2) to support planning for the treatment and disposal of the wastes.

  19. Vapor Space Characterization of Waste Tank 241-C-111: Results from Samples Collected with the Vapor Sampling System on 9/13/94

    SciTech Connect

    Lucke, R. B.; Ligotke, M. W.; McVeety, B. D.; McCulloch, M.; Goheen, S. C.; Clauss, T. W.; Pool, K. H.; Young, J. S.; Fruchter, J. S.

    1995-05-01

    This report describes inorganic and orgajc analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-C-111 (referred to as Tank C-111). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), and water (H{sub 2}O). Sampling for hydrogen cyanide (HCN) and sulfur oxides (SO{sub x}) was not requested. Organic compounds were quantitatively determined. Six organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, we looked for the 40 standard TO-14 analytes. None were observed above the 2-ppbv calibrated instrument detection limit.

  20. Vapor space characterization of waste Tank 241-BY-107: Results from in situ sample collected on 3/25/94

    SciTech Connect

    Sharma, A.K.; Lucke, R.B.; Clauss, T.W.; McVeety, B.D.; Fruchter, J.S.; Goheen, S.C.

    1995-06-01

    This report describes organic results from vapors of the Hanford single-shell waste storage Tank 241-BY-107 (referred to as Tank BY-107). Samples for selected inorganic compounds were obtained but not anlayzed (Section 2.0). Quantitative results were obtained for several organic analytes, but quantities of analytes not listed in US Environmental Protection Agency (EPA) compendium Method TO-14 were estimated. Approximately 80 tentatively identified organic analytes were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and their quantitative determination is beyond the scope of this study. The SUMMATM canister samples were also analyzed for the 41 organic compounds listed in EPA compendium Method TO-14. Of these, only a few were observed above the 2-ppbv detection limits. These are summarized in Table 3.1. Estimated quantities were determined of tentatively identified compounds (TICs). A summary of these results shows quantities of all TICs above the concentration of ca. 10 ppbv. This consists of more than 80 organic analytes. The 12 organic analytes with the highest estimated concentrations are shown.

  1. Tank 241-AP-106, Grab samples, 6AP-98-1, 6AP-98-2 and 6AP-98-3 Analytical results for the final report

    SciTech Connect

    FULLER, R.K.

    1999-02-23

    This document is the final report for tank 241-AP-106 grab samples. Three grab samples 6AP-98-1, 6AP-98-2 and 6AP-98-3 were taken from riser 1 of tank 241-AP-106 on May 28, 1998 and received by the 222-S Laboratory on May 28, 1998. Analyses were performed in accordance with the ''Compatability Grab Sampling and Analysis Plan'' (TSAP) (Sasaki, 1998) and the ''Data Quality Objectives for Tank Farms Waste Compatability Program (DQO). The analytical results are presented in the data summary report. No notification limits were exceeded. The request for sample analysis received for AP-106 indicated that the samples were polychlorinated biphenyl (PCB) suspects. The results of this analysis indicated that no PCBs were present at the Toxic Substance Control Act (TSCA) regulated limit of 50 ppm. The results and raw data for the PCB analysis are included in this document.

  2. Characterization Of Supernate Samples From High Level Waste Tanks 13H, 30H, 37H, 39H, 45F, 46F and 49H

    SciTech Connect

    Stallings, M. E.; Barnes, M. J.; Peters, T. B.; Diprete, D. P.; Hobbs, D. T.; Fink, S. D.

    2005-06-15

    This document presents work conducted in support of technical needs expressed, in part, by the Engineering, Procurement, and Construction Contractor for the Salt Waste Processing Facility (SWPF). The Department of Energy (DOE) requested that Savannah River National Laboratory (SRNL) analyze and characterize supernate waste from seven selected High Level Waste (HLW) tanks to allow: classification of feed to be sent to the SWPF; verification that SWPF processes will be able to meet Saltstone Waste Acceptance Criteria (WAC); and updating of the Waste Characterization System (WCS) database. This document provides characterization data of samples obtained from Tanks 13H, 30H, 37H, 39H, 45F, 46F, and 49H and discusses results. Characterization of the waste tank samples involved several treatments and analysis at various stages of sample processing. These analytical stages included as-received liquid, post-dilution to 6.44 M sodium (target), post-acid digestion, post-filtration (at 3 filtration pore sizes), and after cesium removal using ammonium molybdophosphate (AMP). All tanks will require cesium removal as well as treatment with Monosodium Titanate (MST) for {sup 90}Sr (Strontium) decontamination. A small filtration effect for 90Sr was observed for six of the seven tank wastes. No filtration effects were observed for Pu (Plutonium), Np (Neptunium), U (Uranium), or Tc (Technetium); {sup 137}Cs (Cesium) concentration is ~E+09 pCi/mL for all the tank wastes. Tank 37H is significantly higher in {sup 90}Sr than the other six tanks. {sup 237}Np in the F-area tanks (45F and 46F) are at least 1 order of magnitude less than the H-Area tank wastes. The data indicate a constant ratio of {sup 99}Tc to Cs in the seven tank wastes. This indicates the Tc remains largely soluble in Savannah River Site (SRS) waste and partitions similarly with Cs. {sup 241}Am (Americium) concentration was low in the seven tank wastes. The majority of data were detection limit values, the largest being

  3. Engineering task plan for determining breathing rates in singleshell tanks using tracer gas

    SciTech Connect

    Andersen, J.A.

    1997-04-02

    The testing of single shell tanks to determine breathing rates. Inert tracer gases helium, and sulfur hexafluoride will be injected into the tanks AX-103, BY-105, C-107 and U-103. Periodic samples will be taken over a three month interval to determine actual headspace breathing rates.

  4. A safety assessment of rotary mode core sampling in flammable gas single shell tanks: Hanford Site, Richland, Washington

    SciTech Connect

    Raymond, R.E.

    1996-04-15

    This safety assessment (SA) addresses each of the required elements associated with the installation, operation, and removal of a rotary-mode core sampling (RMCS) device in flammable-gas single-shell tanks (SSTs). The RMCS operations are needed in order to retrieve waste samples from SSTs with hard layers of waste for which push-mode sampling is not adequate for sampling. In this SA, potential hazards associated with the proposed action were identified and evaluated systematically. Several potential accident cases that could result in radiological or toxicological gas releases were identified and analyzed and their consequences assessed. Administrative controls, procedures and design changes required to eliminate or reduce the potential of hazards were identified. The accidents were analyzed under nine categories, four of which were burn scenarios. In SSTS, burn accidents result in unacceptable consequences because of a potential dome collapse. The accidents in which an aboveground burn propagates into the dome space were shown to be in the ``beyond extremely unlikely`` frequency category. Given the unknown nature of the gas-release behavior in the SSTS, a number of design changes and administrative controls were implemented to achieve these low frequencies. Likewise, drill string fires and dome space fires were shown to be very low frequency accidents by taking credit for the design changes, controls, and available experimental and analytical data. However, a number of Bureau of Mines (BOM) tests must be completed before some of the burn accidents can be dismissed with high confidence. Under the category of waste fires, the possibility of igniting the entrapped gases and the waste itself were analyzed. Experiments are being conducted at the BOM to demonstrate that the drill bit is not capable of igniting the trapped gas in the waste. Laboratory testing and thermal analysis demonstrated that, under normal operating conditions, the drill bit will not create high

  5. Hybrid quantitative simulation on the in-line phase-contrast x-ray imaging of three dimensional samples under actual clinic imaging parameters

    SciTech Connect

    Yu Hong; Han Shensheng; Ding Jianhui; Jiang Zhaoxia; Peng Weijun

    2009-07-06

    A hybrid model combining Monte Carlo method with diffraction theory of wave optics has been developed and applied to quantitatively simulate the in-line diffractive phase-contrast x-ray imaging of three dimensional tissue samples under actual clinic imaging parameters. The primary microcosmic interactions of medical-energy x-ray within matter including photoabsorption, Compton scattering, and coherent scattering, have been taken into account in the Monte Carlo simulation. A diffraction processing based on Fresnel diffraction theory is carried out to simulate the macroscopic diffraction effect. A comparison with experiment results has also been performed.

  6. Tank 241-U-103, grab samples 3U-99-1, 3u-99-2 and 3U-99-3

    SciTech Connect

    STEEN, F.H.

    1999-08-25

    This document is the final report for tank 241-U-103 grab samples. Three grab samples were collected from riser 13 on March 12, 1999 and received by the 222-S laboratory on March 15, 1999. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan for Fiscal year 1999 (TSAP) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO). The analytical results are presented in the data summary report. None of the subsamples submitted for differential scanning calorimetry (DSC), total organic carbon (TOC) and plutonium 239 (Pu239) analyses exceeded the notification limits as stated in TSAP.

  7. Tank 241-S-304, Grab samples, 304S-98-1, 304S-98-2 and 304S-98-3 analytical results for the final report

    SciTech Connect

    STEEN, F.H.

    1999-02-23

    This document is the final report for tank 241-S-304 grab samples. Four grab samples were collected from riser 4 on July 30, 1998. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1998) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO). The analytical results are presented in the data summary report (Table 1). None of the subsamples submitted for differential scanning calorimetry (DSC), total organic carbon (TOC) and plutonium 239 (Pu239) analyses exceeded the notification limits as stated in TSAP (Saaaki, 1998).

  8. Tank 241-BY-111 tank characterization plan

    SciTech Connect

    Homi, C.S.

    1994-11-03

    The sampling and analytical needs associated with the 51 Hanford Site underground storage tanks classified on one or more of the four Watch Lists (ferrocyanide, organic, flammable gas, and high heat), and the safety screening of all 177 tanks have been identified through the Data Quality Objective (DQO) process. DQO`s identify information needed by a program group in the Tank Waste Remediation System concerned with safety issues, regulatory requirements, or the transporting and processing of tank waste. This Tank Characterization Plan will identify characterization objectives for Tank BY-111 pertaining to sample collection, sample preparation and analysis, and laboratory analytical evaluation and reporting requirements. In addition, an estimate of the current contents and status of the tank is given.

  9. Solvent Hold Tank Sample Results for MCU-15-389-390 and MCU-15-439-440-441. February 2015 Monthly Samples

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2015-05-04

    Savannah River National Laboratory (SRNL) received two sets of Solvent Hold Tank (SHT) samples (MCU-15-389 and MCU-15-390 pulled on February 23, 2015 and MCU-15-439, MCU-15-440, and MCU-15-441 pulled on February 28, 2015) for analysis. The samples in each set were combined and analyzed for composition. Analysis of the composite samples MCU-15-389-390 and MCU-15-439-440- 441 indicated a low concentration (~ 92 to 93 % of nominal) of the suppressor (TiDG) and slightly below nominal concentrations of the extractant (MaxCalix), but nominal levels of the modifier (CS-7SB) and of the Isopar™ L. This analysis confirms the addition of TiDG, MaxCalix, and modifier to the solvent on February 22, 2015. Despite that the values are below the target component levels, the current levels of TiDG and MaxCalix are sufficient for continuing operation without adding a trim at this time. No impurities above the 1000 ppm level were found in this solvent. However, the p-nut vials that delivered the samples contained small (1 mm) droplets of oxidized modifier and amides. The laboratory will continue to monitor the quality of the solvent in particular for any new impurity or degradation of the solvent components.

  10. Associations between Mycobacterium avium subsp. paratuberculosis antibodies in bulk tank milk, season of sampling and protocols for managing infected cows

    PubMed Central

    2013-01-01

    Background The objective of this study was to identify associations between the concentration of Mycobacterium avium subsp. paratuberculosis (MAP) antibodies in bulk milk and potential risk factors in herd management and herd characteristics, explaining high MAP antibody titers in milk. An extensive questionnaire was administered to 292 organic and conventional dairy farms from New York, Wisconsin and Oregon. Bulk milk samples were taken from each farm for MAP enzyme-linked immunosorbent assay (ELISA). A general linear model was constructed with MAP ELISA value as the outcome variable and the management factors and herd characteristics as independent variables, while at the same time controlling for the study design variables of state, herd size, and production system (organic or conventional). High bulk tank MAP ELISA value may be due to either a high prevalence of MAP in a herd with many cows contributing to the antibody titer or due to a few infected cows that produce large quantities of antibodies. Results Results of the regression models indicated that bulk milk ELISA value was associated with season of sampling and the presence or absence of protocols for managing MAP-positive cows. The concentration of MAP antibodies in bulk milk varied seasonally with a peak in the summer and low concentrations in the winter months. When compared to farms that had never observed clinical Johne’s disease, keeping MAP-positive cows or only culling them after a period of delay was associated with an increase in optical density. Conclusions The seasonal variation in MAP antibody titers, with a peak in the summer, may be due to a seasonal increase in MAP-bacterial load. Additionally, seasonal calving practices may contribute to seasonal fluctuations in MAP antibody titers in bulk tank milk. Keeping MAP-positive cows increases the antibody titer in bulk milk, likely due to direct antibody production in the infected cow and indirect triggering of antibody production in herdmates

  11. Tank 241-BX-104 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1994-12-14

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-BX-104.

  12. Tank 241-SX-106 tank characterization plan

    SciTech Connect

    Homi, C.S.

    1995-03-08

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-SX-106.

  13. Tank 241-SX-103 tank characterization plan

    SciTech Connect

    Homi, C.S.

    1995-03-08

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-SX-103.

  14. Tank 241-T-107 tank characterization plan

    SciTech Connect

    Homi, C.S.

    1995-01-05

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-T-107.

  15. Tank 241-U-103 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1995-01-24

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-U-103.

  16. Tank 241-TX-118 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1994-12-09

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-TX-118.

  17. Tank 241-U-105 tank characterization plan

    SciTech Connect

    Homi, C.S.

    1995-02-03

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-U-105.

  18. Tank 241-U-111 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1995-01-24

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-U-111.

  19. Tank 241-TX-105 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1995-01-01

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-TX-105.

  20. Tank 241-T-111 tank characterization plan

    SciTech Connect

    Homi, C.S.

    1995-01-10

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-T-111.

  1. Tank 241-TY-101 Tank Characterization Plan

    SciTech Connect

    Homi, C.S.

    1995-03-20

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-TY-101.

  2. Polychlorinate biphenyls (PCB) analysis report for solid sample for 219S tank 102

    SciTech Connect

    Ross, G.A.

    1997-12-05

    One waste sample was analyzed (with duplicate, matrix spike, and matrix spike duplicate) for PCBs as Aroclor mixtures by the Inorganic/Organic Chemistry Group. A soxhlet extraction procedure was used for extraction of the Aroclors from the sample. Analysis was performed using dual column confirmation gas chromatography/electron capture detection (GC/ECD). Extraction follows closely method 354 C of SW-846, analysis follows SW-846 method 8082. A cross reference of laboratory sample number to the customer identification is given in a table.

  3. Results of Hg speciation testing on tanks 30, 32, and 37 surface samples

    SciTech Connect

    Bannochie, C. J.

    2015-11-11

    The Savannah River National Laboratory (SRNL) was tasked with preparing and shipping samples for Hg speciation by Eurofins Frontier Global Sciences, Inc. in Seattle, WA on behalf of the Savannah River Remediation (SRR) Mercury Task Team.

  4. Development of an inventory/archive program for the retention, management, and disposition of tank characterization samples at the 222-S laboratory

    SciTech Connect

    Seidel, C.M.

    1998-04-29

    The Hanford Tank Waste Remediation Systems (TWRS) Characterization Program is responsible for coordinating the sampling and analysis of the 177 large underground storage tanks at the Hanford site. The 222-S laboratory has been the primary laboratory for chemical analysis of this highly-radioactive material and has been accumulating these samples for many years. As part of the Fiscal Year 1998 laboratory work scope, the 222-S laboratory has performed a formal physical inventory of all tank characterization samples which are currently being stored. In addition, an updated inventory/archive program has been designed. This program defines sample storage, retention, consolidation, maintenance, and disposition activities which will ensure that the sample integrity is preserved to the greatest practical extent. In addition, the new program provides for continued availability of waste material in a form which will be useful for future bench-scale studies. Finally, when the samples have exceeded their useful lifetime, the program provides for sample disposition from,the laboratory in a controlled, safe and environmentally compliant manner. The 222-S laboratory maintains custody over samples of tank waste material which have been shipped to the laboratory for chemical analysis. The storage of these samples currently requires an entire hotcell, fully dedicated to sample archive storage, and is rapidly encroaching on additional hotcell space. As additional samples are received, they are beginning to limit the 222-S laboratory hotcell utility for other activities such as sample extrusion and subsampling. The 222-S laboratory tracks the number of sample containers and the mass of each sample through an internal database which has recently been verified and updated via a physical inventory.

  5. 45-Day safety screen results and final report for Tank 241-SX-113, Auger samples 94-AUG-028 and 95-AUG-029

    SciTech Connect

    Sasaki, L.M.

    1995-06-22

    This document serves as the 45-day report deliverable for tank 241-SX-113 auger samples collected on May 9 and 10, 1995. The samples were extruded, and analyzed by the 222-S Laboratory. Laboratory procedures completed include: differential scanning calorimetry; thermogravimetric analysis; and total alpha analysis. This report incudes the primary safety screening results obtained from the analyses. As the final report, the following are also included: chains of custody; the extrusion logbook; sample preparation data; and total alpha analysis raw data.

  6. Tank 241-SX-106 headspace gas and vapor characterization results for samples collected in March 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  7. Tank 241-T-107 Headspace Gas and Vapor Characterization Results for Samples Collected in January 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-26

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories

  8. Tank 241-TY-104 headspace gas and vapor characterization results for samples collected in April 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  9. Tank 241-S-111 headspace gas and vapor characterization results for samples collected in March 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  10. Tank 241-C-104 headspace gas and vapor characterization results for samples collected in March 1994

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-28

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories

  11. Tank 241-AX-102 headspace gas and vapor characterization results for samples collected in June 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  12. Tank 241-C-102 headspace gas and vapor characterization results for samples collected in August 1994

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  13. Tank 241-U-103 headspace gas and vapor characterization results for samples collected in February 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-27

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  14. Tank 241-TX-105 headspace gas and vapor characterization results for samples collected in December 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-25

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories

  15. Tank 241-B-103 headspace gas and vapor characterization results for samples collected in February 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-27

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories

  16. Tank 241-A-101 headspace gas and vapor characterization results for samples collected in June 1995

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  17. Tank 241-C-110 headspace gas and vapor characterization results for samples collected in August 1994

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  18. Sample taking problems in measuring actual histamine levels of human gastroduodenal mucosa: specific and general relevance in clinical trials on peptic ulcer pathogenesis and selective proximal vagotomy.

    PubMed Central

    Thon, K P; Lorenz, W; Ohmann, C; Weber, D; Rohde, H; Röher, H D

    1985-01-01

    Changes in histamine storage in the oxyntic mucosa of duodenal ulcer patients and their reversal by vagotomy and the histamine H2-antagonist cimetidine supported the hypothesis that histamine could be a causal factor in peptic ulcer pathogenesis. The specificity of these findings was impaired by problems in biopsy taking, however, and in the preparative steps before measuring the actual histamine contents in all parts of the gastric mucosa and in the duodenum. A prospective trial was carried out in 190 patients to identify these sources of bias and to overcome them by appropriate study designs. Usually a direct correlation was found between weight of biopsy and mucosal histamine content. This problem was solved by selecting a biopsy forceps producing smaller variations in sample size, by limiting the time of cold ischaemia to four to five minutes only and by taking three biopsy specimens for each single histamine value. The actual histamine content of mucosal biopsies remained constant for about four to five minutes only. The 'disappearance' rate was faster in control subjects than in duodenal ulcer patients. Hence by variation of the cold ischaemia time any artefacts of differences between mucosal histamine levels in controls and duodenal ulcer patients could be produced. Using the optimised sample taking procedure mucosal histamine contents of several gastric regions and the duodenal bulb were measured in 24 patients with duodenal ulcer, after selective proximal vagotomy without drainage and in control subjects without any stomach disease (randomised controlled trial). The histamine content was lower in all parts of the upper gastrointestinal tract in duodenal ulcer patients than in controls and was raised again in all regions after selective proximal vagotomy. As the most likely hypothesis it is suggested that vagal reflexes with afferent fibres coming from the oxyntic mucosa stimulate histamine release in duodenal ulcer patients by efferent peptidergic neurones

  19. Tank vapor characterization project. Headspace vapor characterization of Hanford waste tank 241-T-104: Results from samples collected on 02/07/96

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1996-06-01

    This report describes the analytical results, which were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds; the analyses were performed by PNNL`s Vapor Analytical Laboratory. Results are summarized as: NH{sub 3} 105{+-}3 ppmv, NO{sub 2} 0.3{+-}0.1 ppmv, NO 0.3{+-}0.2 ppmv, H{sub 2}O 12.0{+-}0.5 mg/L, CO{sub 2} 241 ppmv, CO undetected, CH{sub 4} undetected, H{sub 2} detected, N{sub 2}O detected, and hydrocarbons 1.93 mg/m{sub 3}.

  20. Vapor space characterization of Waste Tank 241-C-103: Inorganic results from sample Job 7B (May 12-25, 1994)

    SciTech Connect

    Ligotke, M.W.; Pool, K.H.; Lerner, B.D.

    1994-10-01

    This report is to provide analytical results for use in safety and toxicological evaluations of the vapor space of Hanford single-shell waste storage tanks C-103. Samples were analysed to determine concentrations of ammonia, nitric oxide, nitrogen dioxide, sulfur oxides, and hydrogen cyanide. In addition to the samples, controls were analyzed that included blanks, spiked blanks, and spiked samples. These controls provided information about the suitability of sampling and analytical methods. Also included are the following: information describing the methods and sampling procedures used; results of sample analyses; and Conclusions and recommendations.

  1. 45-day safety screen results and final report for Tank 241-C-203, Auger samples 95 AUG-020 and 95-AUG-021

    SciTech Connect

    Conner, J.M.

    1995-05-18

    This document serves as the 45-day report deliverable for the tank C-203 auger samples collected on April 5, 1995 (samples 95-AUG-20 and 95-AUG-021). As no secondary analyses were required and no other analyses have been requested, this document also serves as the final report for C-203 auger sampling. Each sample was received, extruded, and analyzed by the 222-S Laboratories in accordance with the Tank Characterization Plan (TCP) referenced below. Included in this report are the primary safety screening results (DSC, TGA, and alpha) and density results. The worklists and raw data are included in this report. Photographs of the auger samples were taken during extrusion and, although not included in this report, are available.

  2. Revised final report for tank 241-AN-101, grab samples 1AN-95-1 through 1AN-95-7. Revision 1

    SciTech Connect

    Esch, R.A.

    1996-01-17

    Six supernate grab samples and one field blank were taken from tank 241-AN-101. This report documents analyses performed in support of the Safety Screening program: differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), density by specific gravity (Sp.G.), and total alpha activity (AT).

  3. Analysis of tank 39H (HTF-39-15-61, 62) surface and subsurface supernatant samples in support of corrosion control program

    SciTech Connect

    Oji, L. N.

    2015-08-19

    This report provides the results of analyses on Tanks 39H surface and subsurface supernatant liquid samples in support of the Corrosion Control Program. Analyses included warm acid strike preparation followed by analysis for silicon, aluminum, and sodium and water dilution preparation followed by analysis for anions. Other reported analytical results include analyses results for uranium, Pu-241 and Pu-239.

  4. Association between subjective actual sleep duration, subjective sleep need, age, body mass index, and gender in a large sample of young adults

    PubMed Central

    Kalak, Nadeem; Brand, Serge; Beck, Johannes; Holsboer-Trachsler, Edith; Wollmer, M Axel

    2015-01-01

    Background Poor sleep is a major health concern, and there is evidence that young adults are at increased risk of suffering from poor sleep. There is also evidence that sleep duration can vary as a function of gender and body mass index (BMI). We sought to replicate these findings in a large sample of young adults, and also tested the hypothesis that a smaller gap between subjective sleep duration and subjective sleep need is associated with a greater feeling of being restored. Methods A total of 2,929 university students (mean age 23.24±3.13 years, 69.1% female) took part in an Internet-based survey. They answered questions related to demographics and subjective sleep patterns. Results We found no gender differences in subjective sleep duration, subjective sleep need, BMI, age, or feeling of being restored. Nonlinear associations were observed between subjective sleep duration, BMI, and feeling of being restored. Moreover, a larger discrepancy between subjective actual sleep duration and subjective sleep need was associated with a lower feeling of being restored. Conclusion The present pattern of results from a large sample of young adults suggests that males and females do not differ with respect to subjective sleep duration, BMI, or feeling of being restored. Moreover, nonlinear correlations seemed to provide a more accurate reflection of the relationship between subjective sleep and demographic variables. PMID:25657583

  5. Final report for tank 241-AP-108, grab samples 8AP-96-1, 8AP-96-2 and 8AP-96-FB

    SciTech Connect

    Esch, R.A.

    1996-04-19

    This document is the final report deliverable for the tank 241-AP-108 grab samples. The samples were subsampled and analyzed in accordance with the TSAP. Included in this report are the results for the Waste Compatibility analyses, with the exception of DSC and thermogravimetric analysis (TGA) results which were presented in the 45 Day report (Part 2 of this document). The raw data for all analyses, with the exception of DSC and TGA, are also included in this report.

  6. Tank 241-AX-101 grab samples 1AX-97-1 through 1AX-97-3 analytical results for the final report

    SciTech Connect

    Esch, R.A.

    1997-11-13

    This document is the final report for tank 241-AX-101 grab samples. Four grab samples were collected from riser 5B on July 29, 1997. Analyses were performed on samples 1AX-97-1, 1AX-97-2 and 1AX-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Miller, 1997). The analytical results are presented in Table 1. No notification limits were exceeded. All four samples contained settled solids that appeared to be large salt crystals that precipitated upon cooling to ambient temperature. Less than 25 % settled solids were present in the first three samples, therefore only the supernate was sampled and analyzed. Sample 1AX-97-4 contained approximately 25.3 % settled solids. Compatibility analyses were not performed on this sample. Attachment 1 is provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed. Table 2 provides the appearance information. All four samples contained settled solids that appeared to be large salt crystal that precipitated upon cooling to ambient temperature. The settled solids in samples 1AX-97-1, 1AX-97-2 and 1AX-97-3 were less than 25% by volume. Therefore, for these three samples, two 15-mL subsamples were pipetted to the surface of the liquid and submitted to the laboratory for analysis. In addition, a portion of the liquid was taken from each of the these three samples to perform an acidified ammonia analysis. No analysis was performed on the settled solid portion of the samples. Sample 1AX-97-4 was reserved for the Process Chemistry group to perform boil down and dissolution testing in accordance with Letter of Instruction for Non-Routine Analysis of Single-Shell Tank 241-AX-101 Grab Samples (Field, 1997) (Correspondence 1). However, prior to the analysis, the sample was inadvertently

  7. Tank characterization report: Tank 241-C-109

    SciTech Connect

    Simpson, B.C.; Borshiem, G.L.; Jensen, L.

    1993-09-01

    Single-shell tank 241-C-109 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in September 1992. Analyses of materials obtained from tank 241-C-109 were conducted to support the resolution of the ferrocyanide unreviewed safety question (USQ) and to support Hanford Federal Facility Agreement and consent Order (Tri- Party Agreement) Milestone M-10-00. This report describes this analysis.

  8. Waste Tank Organic Safety Program: Analytical methods development. Progress report, FY 1994

    SciTech Connect

    Campbell, J.A.; Clauss, S.A.; Grant, K.E.

    1994-09-01

    The objectives of this task are to develop and document extraction and analysis methods for organics in waste tanks, and to extend these methods to the analysis of actual core samples to support the Waste Tank organic Safety Program. This report documents progress at Pacific Northwest Laboratory (a) during FY 1994 on methods development, the analysis of waste from Tank 241-C-103 (Tank C-103) and T-111, and the transfer of documented, developed analytical methods to personnel in the Analytical Chemistry Laboratory (ACL) and 222-S laboratory. This report is intended as an annual report, not a completed work.

  9. ANALYSES OF HTF-48-12-20/24 (FEBRUARY, 2012) AND ARCHIVED HTF-E-05-021 TANK 48H SLURRY SAMPLES

    SciTech Connect

    Nash, C.; Peters, T.

    2012-08-02

    Personnel characterized a Savannah River National Laboratory (SRNL) archived sample of Tank 48H slurry (HTF-E-05-021) in addition to the composite of samples HTF-48-12-20 and HTF-48-12-24, which were both retrieved in February 2012. The combined February 2012 sample is referred to as HTF-48-12-20/24 in this report. The results from these analyses are compared with Tank 48H samples analyzed in 2003, 2004, and 2005. This work supports the effort to demonstrate copper-catalyzed peroxide oxidation (CCPO) of organic content in this material. The principal findings with respect to the chemical and physical characteristics of the most recent sample are: (1) The measured potassium tetraphenylborate (KTPB) solid concentration is 1.76 wt %; (2) Titanium was in line with 2004 and 2005 slurry measurements at 897 mg/L, it represents 0.1535 {+-} 0.0012 wt % monosodium titanate (MST); (3) The measured insoluble solids content was 1.467 wt %; (4) The free hydroxide concentration in the Tank 48H filtrate sample (1.02 {+-} 0.02 M) is close to the Tank 48H limit (1.0 M); (5) Carbonate reported by total inorganic carbon (TIC, 1.39 {+-} 0.03 M) is more than double the concentrations measured in past (2003-2005) samples; (6) The soluble potassium content (measured at 286 {+-} 23 mg/L) in the filtrate is in line with all past measurements; and (7) The measured {sup 137}Cs concentration is 7.81E + 08 {+-} 3.9E + 07 dpm/mL of slurry (1.33 {+-} 5% Ci/gallon or 3.18E + 05 {+-} 5% curies of {sup 137}Cs in the tank) in the slurry which is in agreement with the 2005 report of 3.14E + 05 {+-} 1.5% curies of {sup 137}Cs in the tank. The filtrate {sup 137}Cs concentration is 2.57E + 07 {+-} 2.6E + 05 dpm/mL. This result is consistent with previous results. Significant analytical data are summarized in Table 1.

  10. Vapor space characterization of waste Tank 241-BY-106 (in situ): Results from samples collected on 5/4/94 and 5/5/94

    SciTech Connect

    Clauss, T.W.; Ligotke, M.W.; Pool, K.H.; Lucke, R.B.; McVeety, B.D.; Sharma, A.K.; McCulloch, M.; Fruchter, J.S.; Goheen, S.C.

    1995-04-01

    This report describes inorganic and organic analyses results from in situ samples obtained from the headspace of the Hanford waste storage Tank 241-BY-106 (referred to as Tank BY-106). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds NH{sub 3}, NO{sub 2}, NO, HCN, and H{sub 2}O. Sampling for sulfur oxides was not requested. Organic compounds were also quantitatively determined. Twenty-three organic tentatively identified compounds (TICS) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, the authors looked for the 41 standard TO-14 analytes. Of these, only a few were observed above the 2-ppbv detection limit. The 10 organic analytes with the highest estimated concentrations are listed in Table 1. The 10 analytes account for approximately 64% of the total organic components in Tank BY-106. Tank BY-106 is on the Ferrocyanide Watch List.

  11. 222-S Analytical services final results for Tank 241-U-101, grab samples 1U-96-1 through 1U-96-4

    SciTech Connect

    Miller, G.L., Westinghouse Hanford

    1996-08-23

    This document is the final, format IV, laboratory report for characterization of tank 241-U-101 (U-101) grab samples from risers 1 and 7. It transmits additional analytical data for specific gravity (Sp.G.), and all raw analytical data which were not provided in the 45-day report. The 45-day report is attached to this final report as Part II. Secondary analyses were not performed on any of the U-101 samples. This is because none of the primary analyte limits, which trigger the performance of secondary analyses, were exceeded. Grab samples were taken on May 29, 1996 and May 30, 1996 from risers 1 and 7, respectively, and were received at the 222-S Laboratory on the same days that they were collected. Analyses were performed in accordance with the Tank Sampling and Analysis Plan (TSAP) for this tank and the Safety Screening Data Quality Objective (DQO). The samples were analyzed for differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), total alpha activity (AT), visual appearance, bulk density, and specific gravity. A sample data summary table, includes sample analytical data accompanied by quality control data (for example, duplicate, spike, blank and standard results and detection limits and counting efforts). The table includes data for DSC, TGA, AT, bulk density, volume percent solids and Sp.G. analyses. Data regarding the visual appearance of samples, volume percent solids and density of the solids are provided in tabular form of the 45-day report (attached as Part II). The table of the 45-day report also associates the original customer sample number with corresponding laboratory sample numbers. The TSAP specified notification limits for only DSC and total alpha. Notification limits were not exceeded for DSC or total alpha analyses for any of the samples, consequently immediate notifications were not necessary and were not made.

  12. Laboratory stabilization/solidification of surrogate and actual mixed-waste sludge in glass and grout

    SciTech Connect

    Spence, R.D.; Gilliam, T.M.; Mattus, C.H.; Mattus, A.J.

    1998-03-03

    Grouting and vitrification are currently the most likely stabilization/solidification technologies for mixed wastes. Grouting has been used to stabilize and solidify hazardous and low-level waste for decades. Vitrification has long been developed as a high-level-waste alternative and has been under development recently as an alternative treatment technology for low-level mixed waste. Laboratory testing has been performed to develop grout and vitrification formulas for mixed-waste sludges currently stored in underground tanks at Oak Ridge National Laboratory (ORNL) and to compare these waste forms. Envelopes, or operating windows, for both grout and soda-lime-silica glass formulations for a surrogate sludge were developed. One formulation within each envelope was selected for testing the sensitivity of performance to variations ({+-}10 wt%) in the waste form composition and variations in the surrogate sludge composition over the range previously characterized in the sludges. In addition, one sludge sample of an actual mixed-waste tank was obtained, a surrogate was developed for this sludge sample, and grout and glass samples were prepared and tested in the laboratory using both surrogate and the actual sludge. The sensitivity testing of a surrogate tank sludge in selected glass and grout formulations is discussed in this paper, along with the hot-cell testing of an actual tank sludge sample.

  13. Sampling and analysis of water from Upper Three Runs and its wetlands near Tank 16 and the Mixed Waste Management Facility

    SciTech Connect

    Dixon, K.L.; Cummins, C.L.

    1994-06-01

    In April and September 1993, sampling was conducted to characterize the Upper Three Runs (UTR) wetland waters near the Mixed Waste Management Facility to determine if contaminants migrating from MWMF are outcropping into the floodplain wetlands. For the spring sampling event, 37 wetlands and five stream water samples were collected. Thirty-six wetland and six stream water samples were collected for the fall sampling event. Background seepline and stream water samples were also collected for both sampling events. All samples were analyzed for RCRA Appendix IX volatiles, inorganics appearing on the Target Analyte List, tritium, gamma-emitting radionuclides, and gross radiological activity. Most of the analytical data for both the spring and fall sampling events were reported as below method detection limits. The primary exceptions were the routine water quality indicators (e.g., turbidity, alkalinity, total suspended solids, etc.), iron, manganese, and tritium. During the spring, cadmium, gross alpha, nonvolatile beta, potassium-40, ruthenium-106, and trichloroethylene were also detected above the MCLs from at least one location. A secondary objective of this project was to identify any UTR wetland water quality impacts resulting from leaks from Tank 16 located at the H-Area Tank Farm.

  14. Vapor space characterization of waste Tank 241-C-104: Results from samples collected on 2/17/94 and 3/3/94

    SciTech Connect

    Lucke, R.B.; McVeety, B.D.; Clauss, T.W.; Pool, K.H.; Young, J.S.; McCulloch, M.; Ligotke, M.W.; Fruchter, J.S.; Goheen, S.C.

    1995-10-01

    This report describes inorganic and organic analyses results from samples obtained from the headspace of the Hanford waste storage Tank 241-C-104 (referred to as Tank C-104). The results described here were obtained to support safety and toxicological evaluations. A summary of the results for inorganic and organic analytes is listed in Summary Table 1. Detailed descriptions of the results appear in the text. Quantitative results were obtained for the inorganic compounds ammonia (NH{sub 3}), nitrogen dioxide (NO{sub 2}), nitric oxide (NO), sulfur oxides (SO{sub x}), and water vapor (H{sub 2}O). Organic compounds were also quantitatively determined. Occupational Safety and Health Administration (OSHA) versatile sampler (OVS) tubes were analyzed for tributyl phosphate. Twenty-four organic tentatively identified compounds (TICs) were observed above the detection limit of (ca.) 10 ppbv, but standards for most of these were not available at the time of analysis, and the reported concentrations are semiquantitative estimates. In addition, the authors looked for the 40 standard TO-14 analytes. Of these, two were observed above the 2-ppbv calibrated instrument detection limit. The 10 organic analytes with the highest estimated concentrations are listed in Summary Table 1. These 10 analytes account for approximately 88% of the total organic components in Tank C 104. Tank C-104 is not on any of the Watch Lists.

  15. Performance evaluation of a thermal desorption/gas chromatographic/mass spectrometric method for the characterization of waste tank headspace samples

    SciTech Connect

    Ma, C.Y.; Skeen, J.T.; Dindal, A.B.; Bayne, C.K.; Jenkins, R.A.

    1997-03-01

    A thermal desorption/gas chromatography/mass spectrometry (TD/GC/MS) method was validated for the determination of volatile organic compounds collected on carbonaceous triple sorbent traps and applied to characterize samples of headspace gases collected from underground nuclear waste storage tanks at the U.S. Department of Energy`s Hanford site, in Richland, WA. Method validation used vapor-phase standards generated from 25 target analytes, including alkanes, alkyl alcohols, alkyl ketones, alkylated aromatics, and alkyl nitriles. The target analytes represent a group of compounds identified in one of the most problematic tanks. TD/GC/MS was carried out with modified injectors. Performance was characterized based on desorption efficiency, reproducibility, stability, and linearity of the calibration, method detection limits, preanalytical holding time, and quality control limits for surrogate standard recoveries. Desorption efficiencies were all greater than 82%, and the majority of the analytes (23 out of 25) had reproducibility values less than 24% near the method detection levels. The method was applied to the analysis of a total of 305 samples collected from the headspaces of 48 underground waste storge tanks. Quality control procedures were implemented to monitor sampling and TD/GC/MS method. 33 refs., 2 figs., 4 tabs.

  16. Final report for tank 241-AN-102, grab samples 2AN-95-1 through 2AN-95-6 and 102-AN-1 through 102-AN-4

    SciTech Connect

    Esch, R.A.

    1996-03-21

    Ten grab samples (2AN-95-1, 2, 3, 4A, 5A; 102-AN-1, 2, 3(A), 3(B), and 4) and one field blank (2AN-95-6) were taken from tank 241-AN-102. In support of the safety screening program, total organic carbon and cyanide were performed as secondary analyses because the differential scanning calorimetry results exceeded the notification limit. These were compared to safety screening limits at a confidence level of 95%. Waste compatibility analyses were performed on the 3 supernate samples and the field blank from the latest sampling event. Results presented in the 45 day and in this report show that the waste in Tank 241-AN-1D2 has energetics greater than 480 J/g (dry) and total organic carbon > 3 wt%; however, with a moisture content > 17 wt%, the tank may be considered ``conditionally`` safe in accordance with the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue.

  17. Detection of Mycobacterium avium subspecies paratuberculosis specific IS900 insertion sequences in bulk-tank milk samples obtained from different regions throughout Switzerland

    PubMed Central

    Corti, Sabrina; Stephan, Roger

    2002-01-01

    Background Since Mycobacterium avium subspecies paratuberculosis (MAP) was isolated from intestinal tissue of a human patient suffering Crohn's disease, a controversial discussion exists whether MAP have a role in the etiology of Crohn's disease or not. Raw milk may be a potential vehicle for the transmission of MAP to human population. In a previous paper, we have demonstrated that MAP are found in raw milk samples obtained from a defined region in Switzerland. The aim of this work is to collect data about the prevalence of MAP specific IS900 insertion sequence in bulk-tank milk samples in different regions of Switzerland. Furthermore, we examined eventual correlation between the presence of MAP and the somatic cell counts, the total colony counts and the presence of Enterobacteriaceae. Results 273 (19.7%) of the 1384 examined bulk-tank milk samples tested IS900 PCR-positive. The prevalence, however, in the different regions of Switzerland shows significant differences and ranged from 1.7% to 49.2%. Furthermore, there were no statistically significant (p >> 0.05) differences between the somatic cell counts and the total colony counts of PCR-positive and PCR-negative milk samples. Enterobacteriaceae occur as often in IS900 PCR-positive as in PCR-negative milk samples. Conclusion This is the first study, which investigates the prevalence of MAP in bulk-tank milk samples all over Switzerland and infers the herd-level prevalence of MAP infection in dairy herds. The prevalence of 19.7% IS900 PCR-positive bulk-milk samples shows a wide distribution of subclinical MAP-infections in dairy stock in Switzerland. MAP can therefore often be transmitted to humans by raw milk consumption. PMID:12097144

  18. Laboratory stabilizations/solidification of tank sludges: MVST/BVEST.

    PubMed

    Spence, R D; Mattus, A J

    2004-03-01

    Oak Ridge tank sludges that have been collected over several decades are being combined for treatment and disposal. Stabilization of the highly radioactive, mixed-waste sludges in the different tank sets has been evaluated prior to the proposed combination and treatment. This paper documents the testing of a Melton Valley Storage Tank (MVST)/Bethel Valley Evaporator Storage Tank set. Subsequent papers will discuss continued work on other tank sets and efforts to maximize the sludge loading. Grout formulations were tested in the laboratory both with a surrogate and with a sample of an actual mixed waste tank sludge from MVST W-25. Wet-sludge loadings of 50-60wt% resulted in strong wasteforms with no free water and gave a volume increase of about 40-50vol%. Resource Conservation and Recovery Act (RCRA) metals included in the surrogate testing were cadmium, chromium, lead, selenium, thallium, and mercury. The actual sludge sample was only characteristically hazardous for mercury by the Toxic Characteristic Leaching Procedure but exceeded the Universal Treatment Standard (UTS) limit for chromium. The grout formulations stabilized these two RCRA metals within UTS limits. In addition, a grout leachability index of about 9.0-10.0 was measured for both (85)Sr and (137)Cs, meeting the recommended requirement of >6.0. PMID:15036693

  19. Leaking underground storage tanks

    SciTech Connect

    Dowd, R.M.

    1984-10-01

    The problems associated with leaking underground storage tanks are discussed. An estimated 10-30% of the 3.5 million or more underground tanks now used to store petroleum products and other liquids may be leaking their contents to the surrounding environment. The EPA is initiating a national field survey of tanks used for the storing of engine fuels. The first phase of the survey will cover a representative sample of 1050 facilities and approximately 2800 tanks. EPA will analyze the questionnaires and then select a sub-sample of about 500 tanks to examine leakage problems in more detail. In the absence of specific groundwater protection legislation or regulation, EPA is planning to use the Toxic Substances Control Act to regulate underground tanks.

  20. Tank 241-B-103 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1995-01-23

    The Defense Nuclear Facilities Safety Board (DNFSB) has advised the US Department of Energy (DOE) to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The data quality objective (DQO) process was chosen as a tool to be used to identify sampling and analytical needs for the resolution of safety issues. As a result, a revision in the Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) milestone M-44-00 has been made, which states that ``A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process... Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.`` This document satisfies that requirement for Tank 241-B-103 (B-103) sampling activities. Tank B-103 was placed on the Organic Watch List in January 1991 due to review of TRAC data that predicts a TOC content of 3.3 dry weight percent. The tank was classified as an assumed leaker of approximately 30,280 liters (8,000 gallons) in 1978 and declared inactive. Tank B-103 is passively ventilated with interim stabilization and intrusion prevention measures completed in 1985.

  1. Stabilization of Mercury in High pH Tank Sludges

    SciTech Connect

    Spence, R.; Barton, J.

    2003-02-24

    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.

  2. Caustic Leaching of Sludges from Selected Hanford Tanks

    SciTech Connect

    Chase, C.W.; Egan, B.Z.; Spencer, B.B.

    1998-08-01

    The objective of this project was to measure the caustic dissolution behavior of sludge components from selected Hanford waste tank sludge samples under different conditions. The dissolution of aluminum, chromium, and other constituents of actual sludge samples in aqueous sodium hydroxide solution was evaluated using various values of temperature, sodium hydroxide concentration, volume of caustic solution per unit mass of sludge (liquid:solids ratio), and leaching time.

  3. Tank 241-U-202 tank characterization plan

    SciTech Connect

    Schreiber, R.D.

    1995-02-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-202.

  4. Tank 241-U-201 tank characterization plan

    SciTech Connect

    Schreiber, R.D.

    1995-02-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 22-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-201.

  5. Tank 241-BY-103 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1994-10-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, Oak Ridge National Laboratory, and PNL 329 Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-BY-103.

  6. Tank 241-BY-105 tank characterization plan

    SciTech Connect

    Schreiber, R.D.

    1995-02-01

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, PNL 325 Analytical Chemistry Laboratory, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-105.

  7. Tank 241-C-201: Tank characterization plan

    SciTech Connect

    Schreiber, R.D.

    1995-03-06

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. Scope of this plan is to provide guidance for sampling and analysis of samples for tank 241-C-201.

  8. AN ASSESSMENT OF THE SERVICE HISTORY AND CORROSION SUSCEPTIBILITY OF TYPE IV WASTE TANKS

    SciTech Connect

    Wiersma, B

    2008-09-18

    Type IV waste tanks were designed and built to store waste that does not require auxiliary cooling. Each Type IV tank is a single-shell tank constructed of a steel-lined pre-stressed concrete tank in the form of a vertical cylinder with a concrete domed roof. There are four such tanks in F-area, Tanks 17-20F, and four in H-Area, Tanks 21-24H. Leak sites were discovered in the liners for Tanks 19 and 20F in the 1980's. Although these leaks were visually observed, the investigation to determine the mechanism by which the leaks had occurred was not completed at that time. Therefore, a concern was raised that the same mechanism which caused the leak sites in the Tanks in F-area may also be operable in the H-Area tanks. Data from the construction of the tanks (i.e., certified mill test reports for the steel, no stress-relief), the service history (i.e., waste sample data, temperature data), laboratory tests on actual wastes and simulants (i.e., electrochemical testing), and the results of the visual inspections were reviewed. The following observations and conclusions were made: (1) Comparison of the compositional and microstructural features indicate that the A212 material utilized for construction of the H-Area tanks are far more resistant to SCC than the A285 materials used for construction of the F-Area tanks. (2) A review of the materials of construction, temperature history, service histories concluded that F-Area tanks likely failed by caustic stress corrosion cracking. (3) The environment in the F-Area tanks was more aggressive than that experienced by the H-Area tanks. (4) Based on a review of the service history, the H-Area tanks have not been exposed to an environment that would render the tanks susceptible to either nitrate stress corrosion cracking (i.e., the cause of failures in the Type I and II tanks) or caustic stress corrosion cracking. (5) Due to the very dilute and uninhibited solutions that have been stored in Tank 23H, vapor space corrosion has

  9. Benzene Generation Testing for Tank 48H Waste Disposition

    SciTech Connect

    Peters, T

    2005-05-13

    In support for the Aggregation option1, researchers performed a series of tests using actual Tank 48H slurries. The tests were designed to examine potential benzene generation issues if the Tank 48H slurry is disposed to Saltstone. Personnel used the archived Tank 48H sample (HTF-E-03-127, collected September 17, 2003) for the experiments. The tests included a series of three experiments (Tests A, B, and F) performed in duplicate, giving a total of six experiments. Test A used Tank 48H slurry mixed with {approx}20:1 with Defense Waste Processing Facility (DWPF) Recycle from Tanks 21H and 22H. Test B used Tank 48H slurry mixed with {approx}2.7:1 with DWPF Recycle from Tanks 21H and 22H, while Test F used Tank 48H slurry as-is. Tests A and B occurred at 45 C, while Test F occurred at 55 C. Over a period of 8 weeks, personnel collected samples for analysis, once per week. Each sample was tested with the in-cell gamma counter. The researchers noted a decline in the cesium activity in solution which is attributed to temperature dependence of the complex slurry equilibrium. Selected samples were sent to ADS for potassium, boron, and cesium analysis. The benzene generation rate was inferred from the TPB destruction which is indirectly measured by the in-growth of cesium, potassium or boron. The results of all the analyses reveal no discernible in-growth of radiocesium, potassium or boron, indicating no significant tetraphenylborate (TPB) decomposition in any of the experiments. From boron measurements, the inferred rate of TPB destruction remained less than 0.332 mg/(L-h) implying a maximum benzene generation rate of <0.325 mg/(L-h).

  10. Preliminary safety criteria for organic watch list tanks at the Hanford site

    SciTech Connect

    Webb, A.B.; Stewart, J.L.; Turner, O.A.; Plys, M.G.; Malinovic, B.; Grigsby, J.M.; Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J.

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended.

  11. Tank characterization reference guide

    SciTech Connect

    De Lorenzo, D.S.; DiCenso, A.T.; Hiller, D.B.; Johnson, K.W.; Rutherford, J.H.; Smith, D.J.; Simpson, B.C.

    1994-09-01

    Characterization of the Hanford Site high-level waste storage tanks supports safety issue resolution; operations and maintenance requirements; and retrieval, pretreatment, vitrification, and disposal technology development. Technical, historical, and programmatic information about the waste tanks is often scattered among many sources, if it is documented at all. This Tank Characterization Reference Guide, therefore, serves as a common location for much of the generic tank information that is otherwise contained in many documents. The report is intended to be an introduction to the issues and history surrounding the generation, storage, and management of the liquid process wastes, and a presentation of the sampling, analysis, and modeling activities that support the current waste characterization. This report should provide a basis upon which those unfamiliar with the Hanford Site tank farms can start their research.

  12. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-12-488, MCU-12-489, MCU-12-490, MCU-12-491, MCU-12-492 AND MCU-12-493: QUARTERLY SAMPLE FROM OCTOBER 2012

    SciTech Connect

    Fondeur, F. F.; Peters, T. B.; Fink, S. D.

    2013-01-16

    Savannah River National Laboratory (SRNL) analyzed solvent samples from Modular Caustic-Side Solvent Extraction Unit (MCU) in support of continuing operations. A quarterly analysis of the solvent is required to maintain solvent composition within specifications. Analytical results of the analyses of Solvent Hold Tank (SHT) samples MCU-12-488, MCU-12-489, MCU-12-490, MCU-12-491, MCU-12-492 and MCU-12-493 received 24 October 2012 are reported. The results show that the solvent at MCU does not require an Isopar® L addition, but it will require addition of trioctylamine. SRNL also analyzed the SHT sample for {sup 137}Cs content and determined the measured value is within tolerance but is trending upward compared to the {sup 137}Cs measurement made last year.

  13. Solvent hold tank sample results for MCU-13-143, MCU-13-144, MCU-13-145, MCU-13-146, MCU-13-147 AND MCU-13-148: quarterly sample from January 2013

    SciTech Connect

    Fondeur, F. F.; Peters, T. B.

    2013-03-27

    Savannah River National Laboratory (SRNL) analyzed solvent samples from Modular Caustic-Side Solvent Extraction Unit (MCU) in support of continuing operations. A quarterly analysis of the solvent is required to maintain solvent composition within specifications. Analytical results of the analyses of Solvent Hold Tank (SHT) samples MCU-13-143, MCU-13-144, MCU-13-145, MCU-13-146, MCU-13-147 and MCU-13-148 received 29 January 2012 are reported. The results show that the solvent at MCU does not require an Isopar® L addition, but it will require addition of trioctylamine. SRNL also analyzed the SHT sample for {sup 137}Cs content and determined the measured value is within tolerance and the value has returned to levels observed in 2012.

  14. Tank 241-TX-302C grab samples 302C-TX-97-1A through 302C-TX-97-3B analytical results for the final report

    SciTech Connect

    Esch, R.A.

    1998-03-12

    This document is the final report for tank 241-TX-302C grab samples. Six grabs samples (302C-TX-97-1A, 302C-TX-97-1B, 302C-TX-97-2A, 302C-TX-97-2B, 302C-TX-97-3A, and 302C-TX-97-3B) were collected from the catch tank level gauge riser on December 19, 1997. The ``A`` and ``B`` portions from each sample location were composited and analyses were performed on the composites in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Miller, 1997). The analytical results are presented in Table 1. No notification limits were exceeded. Appearance and Sample Handling Attachment 1 is provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed. Table 2 provides the appearance information.

  15. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-14-135/136 AND MCU-14-214/215/216: FEBRUARY AND MARCH 2014 MONTHLY SAMPLES

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2014-06-30

    SRNL received two sets of SHT samples (MCU-14-135-136 in February 2014 and MCU-14-214-216 in March 2014) for analysis. The samples were analyzed for composition. As with the previous solvent sample results, these analyses indicate that the solvent does not require Isopar® L trimming at this time. However, the addition of TiDG (suppressor) to the blended solvent is recommended. Evidence of possible (slight) isomerization of the solvent, probably Isopar®L or TiDG degradation products, was observed.

  16. Precipitation of nitrate-cancrinite in Hanford Tank Sludge.

    PubMed

    Buck, E C; McNamara, B K

    2004-08-15

    The chemistry of underground storage tanks containing high-level waste at the Hanford Site in Washington State is an area of continued research interest. Thermodynamic models have predicted the formation of analcime and clinoptilolite in Hanford tanks, rather than cancrinite; however, these predictions were based on carbonate-cancrinite. We report the first observation of a nitrate-cancrinite [possibly Na8(K,Cs)(AlSiO4)6(NO3)2 x nH2O] extracted from a Hanford tank 241-AP-101 sample that was evaporated to 6, 8, and 10 M NaOH concentrations. The nitrate-cancrinite phase formed spherical aggregates (4 microm in diameter) that consisted of platy hexagonal crystals (approximately 0.2 microm thick). Cesium-137 was concentrated in these aluminosilicate structures. These phases possessed a morphology identical to that of nitrate-cancrinite synthesized using simulant tests of nonradioactive tank waste, supporting the contention that it is possible to develop nonradioactive artificial sludges. This investigation points to the continued importance of understanding the solubility of NO3-cancrinite and related phases. Knowledge of the detailed structure of actual phases in the tank waste helps with thermodynamic modeling of tank conditions and waste processing. PMID:15382874

  17. Toxic chemical considerations for tank farm releases. Revision 1

    SciTech Connect

    Van Keuren, J.C.

    1995-11-01

    This document provides a method of determining the toxicological consequences of accidental releases from Hanford Tank Farms. A determination was made of the most restrictive toxic chemicals that are expected to be present in the tanks. Concentrations were estimated based on the maximum sample data for each analyte in all the tanks in the composite. Composite evaluated were liquids and solids from single shell tanks, double shell tanks, flammable gas watch list tanks, as well as all solids, all liquids, head space gases, and 241-C-106 solids. A sum of fractions of the health effects was computed for each composite for unit releases based emergency response planning guidelines (ERPGs). Where ERPGs were not available for chemical compounds of interest, surrogate guidelines were established. The calculation method in this report can be applied to actual release scenarios by multiplying the sum of fractions by the release rate for continuous releases, or the release amount for puff releases. Risk guidelines are met if the product is less than for equal to one.

  18. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-14-259/260/261 AND MCU-14-315/316/317: APRIL AND MAY 2014 MONTHLY SAMPLES

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2014-08-05

    SRNL received two sets of SHT samples (MCU-14-259/260/261 in April 2014 and MCU-14- 315/316/317 in May 2014) for analysis. The samples were analyzed for composition. Both samples have similar chemical composition. As with the previous solvent sample results, these analyses indicate that the solvent does not require Isopar® L trimming at this time. Since an addition of TiDG and MaxCalix to the SHT was added in early July 2014, the solvent does not require TiDG addition at this time. The current TiDG level (1.5 mM) is above the minimum recommended operating level of 1 mM.

  19. SINDA/FLUINT Stratified Tank Modeling for Cryrogenic Propellant Tanks

    NASA Technical Reports Server (NTRS)

    Sakowski, Barbara

    2014-01-01

    A general purpose SINDA/FLUINT (S/F) stratified tank model was created to simulate self-pressurization and axial jet TVS; Stratified layers in the vapor and liquid are modeled using S/F lumps.; The stratified tank model was constructed to permit incorporating the following additional features:, Multiple or singular lumps in the liquid and vapor regions of the tank, Real gases (also mixtures) and compressible liquids, Venting, pressurizing, and draining, Condensation and evaporation/boiling, Wall heat transfer, Elliptical, cylindrical, and spherical tank geometries; Extensive user logic is used to allow detailed tailoring - Don't have to rebuilt everything from scratch!!; Most code input for a specific case is done through the Registers Data Block:, Lump volumes are determined through user input:; Geometric tank dimensions (height, width, etc); Liquid level could be input as either a volume percentage of fill level or actual liquid level height

  20. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-14-667-672 AND MCU-14-846-847: AUGUST AND SEPTEMBER 2014 MONTHLY SAMPLES

    SciTech Connect

    Fondeur, F.; Taylor-Pashow, K.

    2014-10-20

    SRNL received two sets of SHT samples (MCU-14-667-672, pulled 8/27/2014 and MCU-14-846-847, pulled on 9/22/2014) for analysis. The samples were analyzed for composition. It is recommended that the solvent receives Isopar® L and TiDG trimming at this time. Analysis of sample MCU-14-846-847 indicates the solvent has evaporated Isopar®L and has lost TiDG to a level below the recommended minimum 1 mM level. Since the addition of MaxCalix to the SHT in early July 2014, the MaxCalix concentration in the solvent has reached nominal values. The laboratory will continue to monitor the quality of the solvent in particular for any new impurity or degradation of the solvent components.

  1. Tank 241-BY-106 headspace gas and vapor characterization results for samples collected in May 1994 and July 1994

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  2. Tank 241-C-105 headspace gas and vapor characterization results for samples collected in February 1994. Revision 1

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  3. Tank 241-C-111 headspace gas and vapor characterization results for samples collected in August 1993 and September 1994

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  4. Tank 241-C-109 headspace gas and vapor characterization results for samples collected in August 1994. Revision 2

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  5. Tank 241-BY-104 headspace gas and vapor characterization results for samples collected in April 1994 and June 1994

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-01

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

  6. Tank 241-TX-118 headspace gas and vapor characterization results for samples collected in September 1994 and December 1994

    SciTech Connect

    Huckaby, J.L.; Bratzel, D.R.

    1995-09-27

    Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories

  7. Think Tanks

    NASA Technical Reports Server (NTRS)

    2001-01-01

    A new inspection robot from Solex Robotics Systems was designed to eliminate hazardous inspections of petroleum and chemical storage tanks. The submersible robot, named Maverick, is used to inspect the bottoms of tanks, keeping the tanks operational during inspection. Maverick is able to provide services that will make manual tank inspections obsolete. While the inspection is conducted, Maverick's remote human operators remain safe outside of the tank. The risk to human health and life is now virtually eliminated. The risk to the environment is also minimal because there is a reduced chance of spillage from emptying and cleaning the tanks, where previously, tons of pollutants were released through the process of draining and refilling.

  8. Tank characterization data report: Tank 241-C-112

    SciTech Connect

    Simpson, B.C.; Borsheim, G.L.; Jensen, L.

    1993-04-01

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. It is probable that tank 241-C-112 exceeds the 1,000 g-mol inventory criteria established for the Ferrocyanide USQ; however, extensive energetic analysis of the waste has determined a maximum exothermic value of -9 cal/g dry waste. This value is substantially below any levels of concern (-75 cal/g). In addition, an investigation of potential mechanisms to generate concentration levels of radionuclides high enough to be of concern was performed. No credible mechanism was postulated that could initiate the formation of such concentration levels in the tank. Tank 241-C-112 waste is a complex material made up primarily of water and inert salts. The insoluble solids are a mixture of phosphates, sulfates, and hydroxides in combination with aluminum, calcium, iron, nickel, and uranium. Disodium nickel ferrocyanide and sodium cesium nickel ferrocyanide probably exist in the tank; however, there appears to have been significant degradation of this material since the waste was initially settled in the tank.

  9. Boehmite Actual Waste Dissolutions Studies

    SciTech Connect

    Snow, Lanee A.; Lumetta, Gregg J.; Fiskum, Sandra K.; Peterson, Reid A.

    2008-07-15

    The U.S. Department of Energy plans to vitrify approximately 60,000 metric tons of high-level waste (HLW) sludge from underground storage tanks at the Hanford Nuclear Reservation. To reduce the volume of HLW requiring treatment, a goal has been set to remove a significant quantity of the aluminum, which comprises nearly 70 percent of the sludge. Aluminum is found in the form of gibbsite, sodium aluminate and boehmite. Gibbsite and sodium aluminate can be easily dissolved by washing the waste stream with caustic. Boehmite, which comprises nearly half of the total aluminum, is more resistant to caustic dissolution and requires higher treatment temperatures and hydroxide concentrations. Samples were taken from four Hanford tanks and homogenized in order to give a sample that is representative of REDOX (Reduction Oxidation process for Pu recovery) sludge solids. Bench scale testing was performed on the homogenized waste to study the dissolution of boehmite. Dissolution was studied at three different hydroxide concentrations, with each concentration being run at three different temperatures. Samples were taken periodically over the 170 hour runs in order to determine leaching kinetics. Results of the dissolution studies and implications for the proposed processing of these wastes will be discussed.

  10. Tank 241U102 Grab Samples 2U-99-1 and 2U-99-2 and 2U-99-3 Analytical Results for the Final Report

    SciTech Connect

    STEEN, F.H.

    1999-08-03

    This document is the final report for tank 241-U-102 grab samples. Five grab samples were collected from riser 13 on May 26, 1999 and received by the 222-S laboratory on May 26 and May 27, 1999. Samples 2U-99-3 and 2U-99-4 were submitted to the Process Chemistry Laboratory for special studies. Samples 2U-99-1, 2U-99-2 and 2U-99-5 were submitted to the laboratory for analyses. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan for Fiscal year 1999 (TSAP) (Sasaki, 1999) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Fowler 1995, Mulkey and Miller 1998). The analytical results are presented in the data summary report. None of the subsamples submitted for differential scanning calorimetry (DSC), total organic carbon (TOC) and plutonium 239 (Pu239) analyses exceeded the notification limits as stated in TSAP.

  11. Quality of bulk tank milk samples from Danish dairy herds based on real-time polymerase chain reaction identification of mastitis pathogens.

    PubMed

    Katholm, J; Bennedsgaard, T W; Koskinen, M T; Rattenborg, E

    2012-10-01

    Results of a commercial real-time PCR analysis for 11 mastitis pathogens from bulk tank milk (BTM) samples from all 4,258 Danish dairy herds in November 2009 to January 2010 were compared with somatic cell count (SCC) and total bacteria count (TBC) estimates in BTM. For Streptococcus agalactiae, Streptococcus dysgalactiae, and Streptococcus uberis, a low real-time PCR cycle threshold (Ct) value (corresponding to high bacterial DNA quantity) was correlated with higher SCC and higher TBC. For Staphylococcus aureus, low Ct values were correlated only with higher SCC. For the environmental mastitis pathogens Klebsiella spp., Enterococcus spp., and Escherichia coli, low Ct values had a correlation with higher TBC. Staphylococcus spp. were found in the BTM from all herds, Strep. uberis in 95%, Staph. aureus in 91%, and Strep. dysgalactiae in 86%, whereas E. coli, Klebsiella, and Strep. agalactiae were found in 61, 13, and 7% of the herds. It is concluded that the real-time PCR used provides results that are related to the milk quality in the herds. Real-time PCR can be used in the same way as culture for monitoring BTM samples, and is especially useful for bacteria with low prevalence (e.g., Strep. agalactiae). PMID:22921631

  12. CORROSION TESTING IN SIMULATED TANK SOLUTIONS

    SciTech Connect

    Hoffman, E.

    2010-12-09

    Three simulated waste solutions representing wastes from tanks SY-102 (high nitrate, modified to exceed guidance limits), AN-107, and AY-102 were supplied by PNNL. Out of the three solutions tested, both optical and electrochemical results show that carbon steel samples corroded much faster in SY-102 (high nitrate) than in the other two solutions with lower ratios of nitrate to nitrite. The effect of the surface preparation was not as strong as the effect of solution chemistry. In areas with pristine mill-scale surface, no corrosion occurred even in the SY-102 (high nitrate) solution, however, corrosion occurred in the areas where the mill-scale was damaged or flaked off due to machining. Localized corrosion in the form of pitting in the vapor space of tank walls is an ongoing challenge to overcome in maintaining the structural integrity of the liquid waste tanks at the Savannah River and Hanford Sites. It has been shown that the liquid waste condensate chemistry influences the amount of corrosion that occurs along the walls of the storage tanks. To minimize pitting corrosion, an effort is underway to gain an understanding of the pitting response in various simulated waste solutions. Electrochemical testing has been used as an accelerated tool in the investigation of pitting corrosion. While significant effort has been undertaken to evaluate the pitting susceptibility of carbon steel in various simulated waste solutions, additional effort is needed to evaluate the effect of liquid waste supernates from six Hanford Site tanks (AY-101, AY-102, AN-102, AN-107, SY-102 (high Cl{sup -}), and SY-102 (high nitrate)) on carbon steel. Solutions were formulated at PNNL to replicate tank conditions, and in the case of SY-102, exceed Cl{sup -} and NO{sub 3}{sup -} conditions, respectively, to provide a contrast between in and out of specification limits. The majority of previous testing has been performed on pristine polished samples. To evaluate the actual tank carbon steel

  13. Final report for tank 241-AP-101, grab samples 1AP-95-1, 1AP-95-2, 1AP-95-3, 1AP-95-4, 1AP-95-5, and 1AP-95-6

    SciTech Connect

    Esch, R.A.

    1996-03-04

    Six supernate grab samples (1AP-95-1 through 6) and one field blank (1AP-95-7) were taken from tank 241-AP-101, on Nov. 10 and 13, 1995. Analyses were performed in support of the Safety Screening and the Waste Compatibility Safety programs. All analytical results were within the action limits stated in the TSAP.

  14. Composite Tank

    NASA Technical Reports Server (NTRS)

    DeLay, Thomas K. (Inventor)

    2000-01-01

    A composite tank for containing liquid oxygen and the method of making the same Wherein a water-soluble mandrel having ing the desired tank configuration and a cylindrical protuberance on at least one end is fitted with an inner boss conformance, to the configuration of the mandrel and in outer boss conforming to the configuration of the inner boss, the bosses each having a tubular portion for receiving the protuberance on the mandrel and a spherical portion. The mandrel and the bosses are first coated with a nickel coating. The mandrel is then wrapped with graphite fibers wetted with an epoxy resin and this resin is cured. A layer of insulating foam is then applied to the tank and cured. The insulating foam is machined to a desired concentration and a layer of aramid fibers wetted with a second epoxy resin is wrapped around the tank. The second resin is cured and the water soluble mandrel is washed from inside the tank.

  15. Laboratory stabilization/solidification of tank sludges: maximizing sludge loading.

    PubMed

    Spence, R D; Mattus, A J

    2004-03-01

    Highly radioactive, mixed-waste sludges that have been collected in tanks at Oak Ridge over several decades are being combined for treatment and disposal. Stabilization of the sludges in the different tank sets was tested prior to the proposed combination and treatment. This paper is the third one in a series on the laboratory stabilization/solidification of these tank sludges. It discusses efforts to maximize the sludge loading with no strength criterion for the grout formulation. Grout formulations were tested in the laboratory both with surrogates and with actual samples of tank sludge. Hydrogels eliminated free water generation, even at sludge loadings of >90wt%, albeit strong monoliths did not form at such high loadings. Correlations established the dependence of the chromium and mercury performance in the Toxicity Characteristic Leach Procedure for the surrogates on the slag content of the grout while the lead performance depended on the extract pH. The surrogate sludge loading was limited by the chromate content to about 90wt%, meeting Universal Treatment Standard limits. However, tests with actual sludges at such high loadings revealed problems with lead and silver stabilization that were not experienced with the surrogate testing. PMID:15036695

  16. Analysis of Tank 38H (HTF-38-15-119, 127) Surface, Subsurface and Tank 43H (HTF-43-15-116, 117 and 118) Surface, Feed Pump Suction and Jet Suction Subsurface Supernatant Samples in Support of Enrichment, Corrosion Control and Salt Batch Planning Programs

    SciTech Connect

    Oji, L.

    2015-12-17

    Compositional feed limits have been established to ensure that a nuclear criticality event for the 2H and 3H Evaporators is not possible. The Enrichment Control Program (ECP) requires feed sampling to determine the equivalent enriched uranium content prior to transfer of waste other than recycle transfers (requires sampling to determine the equivalent enriched uranium at two locations in Tanks 38H and 43H every 26 weeks) The Corrosion Control Program (CCP) establishes concentration and temperature limits for key constituents and periodic sampling and analysis to confirm that waste supernate is within these limits. This report provides the results of analyses on Tanks 38H and 43H surface and subsurface supernatant liquid samples in support of the ECP, the CCP, and the Salt Batch 10 Planning Program.

  17. Solvent Hold Tank Sample Results For MCU-13-814, MCU-13-815, MCU-13-816, MCU-13,817, MCU-13-818 And MCU-13-819: Quarterly Sample From May 2013

    SciTech Connect

    Fondeur, F. F.; Taylor-Pashow, K. M.

    2013-08-13

    Savannah River National Laboratory (SRNL) analyzed solvent samples from Modular Caustic-Side Solvent Extraction Unit (MCU) in support of continuing operations. A quarterly analysis of the solvent is required to maintain solvent composition within specifications. Analytical results of the analyses of Solvent Hold Tank (SHT) samples MCU-13-814, MCU-13-815, MCU-13-816, MCU-13-817, MCU-13-818 and MCU-13-819 received May 28, 2013 are reported. The results show that the solvent at MCU does not require an Isopar® L addition, but it will require addition of trioctylamine despite of the 272 g of TOA that was added to the solvent on June 5, 2013 based on the solvent containing a TOA level of 45% of nominal. A new TOA analysis method (HCl titration) has been used and its output was statistically similar to the results from the SVOA-TOA method. This method provides an independent method for measuring TOA and TiDG in MCU-NG solvent. An impurity containing a tert-butyl group was detected in the solvent and further analytical analysis is needed to identify it. SRNL recommends determining the impact of this impurity on the mass transfer ability of the solvent. SRNL also analyzed the SHT sample for {sup 137}Cs content and determined the measured value is above the results observed from the January 2013.

  18. Tank characterization data report: Tank 241-C-112

    SciTech Connect

    Simpson, B.C.; Borsheim, G.L.; Jensen, L.

    1993-09-01

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. Analysis of the process history of the tank as well as studies of simulants provided valuable information about the physical and chemical condition of the waste. This information, in combination with the analysis of the tank waste, sup ports the conclusion that an exothermic reaction in tank 241-C-112 is not plausible. Therefore, the contents of tank 241-C-112 present no imminent threat to the workers at the Hanford Site, the public, or the environment from its forrocyanide inventory. Because an exothermic reaction is not credible, the consequences of this accident scenario, as promulgated by the General Accounting Office, are not applicable.

  19. Tank characterization report for single-shell tank 241-U-110. Revision 1

    SciTech Connect

    Brown, T.M.; Jensen, L.

    1993-09-01

    Tank 241-U-110 (U-110) is a Hanford Site waste tank that was ;most recently sampled in November and December 1989. Analysis of the samples obtained from tank U-110 was conducted to support the characterization of the contents of this tank and to support Hanford Federal Facility Agreement and Consent Order milestone M-10-00 (Ecology, et al. 1992). Because of incomplete recovery of the waste during sampling, there may be bias in the results of this characterization report.

  20. Cesium Ion Exchange Using Tank 241-AN-104 Supernate

    SciTech Connect

    Adu-Wusu, K.

    2003-12-22

    The River Protection Project is to design and build a high level nuclear waste treatment facility. The waste treatment plant is to process millions of gallons of radioactive waste stored in tanks at the Hanford Site. The high level nuclear waste treatment process includes various unit operations, such as ultrafiltration, precipitation, evaporation, ion exchange, and vitrification. Ion exchange is identified as the optimal treatment method for removal of cesium-137 and Tc-99 from the waste. Extensive ion exchange testing was performed using small-scale columns with actual waste samples. The objectives of this study were to: demonstrate SuperLig 644 ion exchange performance and process steps for the removal of cesium from actual AN-104 tank waste; pretreat actual AN-104 tank waste to reduce the concentration of cesium-137 in the waste below LAW vitrification limit; produce and characterize cesium eluate solutions for use in eluate evaporation tests. The experiments consisted of batch contact and small-scale column tests. The batch contact tests measured sorption partition coefficients Kds. The Kds were used to predict the effective resin capacity. The small-scale column tests, which closely mimic plant conditions, generated loading and elution profile data used to determine whether removal targets and design requirements were met.

  1. Tank 41H bounding uranium enrichment

    SciTech Connect

    Cavin, W.S.

    1994-07-12

    The intent of this document is to combine data from salt samples and historical process information to bound the uranium (U-235) enrichment which could be expected in the upper portion of the salt in Tank 41H. This bounding enrichment will be used in another document to establish a nuclear safety basis for initial salt removal operations. During the processing period of interest (4/82-4/87), waste was fed to the 2H Evaporator from Tank 43H, and the evaporator bottoms were sent to Tank 41H where the bottoms were allowed to cool (resulting in the formation of salt deposits in the tank). As Tank 41H was filled with concentrate, the supernate left after salt formation was recycled back to Tank 43H and reprocessed through the evaporator along with any additional waste which had been added to Tank 43H. As Tank 41 H filled with salt, this recycle took place with increasing frequency because it took less time to fill the decreased volume with evaporator concentrate. By determining which of the sampled waste tanks were receiving fresh waste from the canyons at the time the tanks were sampled (from published transfer records), it was possible to deduce which samples were likely representative of fresh canyon waste. The processing that was being carried out in the Separation canyons when these tanks were sampled, should be comparable to the processing while Tank 41H was being filled.

  2. Tank 241S109 Grab Samples 9S-99-1 and 9S-99-2 and 9S-99-3 Analytical Results for the Final Report

    SciTech Connect

    STEEN, F.H.

    1999-11-23

    This document is the final report for tank 2414-109 grab samples. Three grab samples were collected from riser 13 on July 28, 1999 and received by the 222-S laboratory on July 28, 1999. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan for Fiscal Year 1999 (TSAP) (Sasaki, 1999) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Fowler 1995, Mulkey and Miller 1998). The analytical results are presented in the data summary report (Table 1). None of the subsamples submitted for differential scanning calorimetry (DSC), total organic carbon (TOC) and plutonium 239 (Pu239) analyses exceeded the notification limits as stated in TSAP (Sasaki, 1999).

  3. Tank characterization report for Single-Shell Tank B-111

    SciTech Connect

    Remund, K.M.; Tingey, J.M.; Heasler, P.G.; Toth, J.J.; Ryan, F.M.; Hartley, S.A.; Simpson, D.B.; Simpson, B.C.

    1994-09-01

    Tank 241-B-111 (hereafter referred to as B-111) is a 2,006,300 liter (530,000 gallon) single-shell waste tank located in the 200 East B tank farm at Hanford. Two cores were taken from this tank in 1991 and analysis of the cores was conducted by Battelle`s 325-A Laboratory in 1993. Characterization of the waste in this tank is being done to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05. Tank B-111 was constructed in 1943 and put into service in 1945; it is the second tank in a cascade system with Tanks B-110 and B-112. During its process history, B-111 received mostly second-decontamination-cycle waste and fission products waste via the cascade from Tank B-110. This tank was retired from service in 1976, and in 1978 the tank was assumed to have leaked 30,300 liters (8,000 gallons). The tank was interim stabilized and interim isolated in 1985. The tank presently contains approximately 893,400 liters (236,000 gallons) of sludge-like waste and approximately 3,800 liters (1,000 gallons) of supernate. Historically, there are no unreviewed safety issues associated with this tank and none were revealed after reviewing the data from the latest core sampling event in 1991. An extensive set of analytical measurements was performed on the core composites. The major constituents (> 0.5 wt%) measured in the waste are water, sodium, nitrate, phosphate, nitrite, bismuth, iron, sulfate and silicon, ordered from largest concentration to the smallest. The concentrations and inventories of these and other constituents are given. Since Tanks B-110 and B-111 have similar process histories, their sampling results were compared. The results of the chemical analyses have been compared to the dangerous waste codes in the Washington Dangerous Waste Regulations (WAC 173-303). This assessment was conducted by comparing tank analyses against dangerous waste characteristics `D` waste codes; and against state waste codes.

  4. Tank characterization report for single shell tank 241-S-107

    SciTech Connect

    Simpson, B.C.

    1996-09-19

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-S-107. This report supports the requirements of Tri- Party Agreement Milestone M-44-09.

  5. The Self Actualized Reader.

    ERIC Educational Resources Information Center

    Marino, Michael; Moylan, Mary Elizabeth

    A study examined the commonalities that "voracious" readers share, and how their experiences can guide parents, teachers, and librarians in assisting children to become self-actualized readers. Subjects, 25 adults ranging in age from 20 to 67 years, completed a questionnaire concerning their reading histories and habits. Respondents varied in…

  6. High-Precision Plutonium Isotopic Compositions Measured on Los Alamos National Laboratory’s General’s Tanks Samples: Bearing on Model Ages, Reactor Modelling, and Sources of Material. Further Discussion of Chronometry

    SciTech Connect

    Spencer, Khalil J.; Rim, Jung Ho; Porterfield, Donivan R.; Roback, Robert Clifford; Boukhalfa, Hakim; Stanley, Floyd E.

    2015-06-29

    In this study, we re-analyzed late-1940’s, Manhattan Project era Plutonium-rich sludge samples recovered from the ''General’s Tanks'' located within the nation’s oldest Plutonium processing facility, Technical Area 21. These samples were initially characterized by lower accuracy, and lower precision mass spectrometric techniques. We report here information that was previously not discernable: the two tanks contain isotopically distinct Pu not only for the major (i.e., 240Pu, 239Pu) but trace (238Pu ,241Pu, 242Pu) isotopes. Revised isotopics slightly changed the calculated 241Am-241Pu model ages and interpretations.

  7. Decision analysis for continuous cover gas monitoring of Ferrocyanide Watch List tanks

    SciTech Connect

    Fowler, K.D.; Graves, R.D.

    1994-07-01

    This document pertains to underground waste storage tanks at the Hanford Site that have been identified to potentially contain a significant amount of ferrocyanide compounds. This document evaluates the need for continuously monitoring the headspace vapors in Ferrocyanide Watch List tanks to detect flammable gases or gases that could indicate the occurrence of a propagating ferrocyanide-nitrate/nitrite reaction. The results of modeling studies and gas monitoring, and sludge sample analyses of actual ferrocyanide tank wastes have indicated no need to continuously monitor the vapor spaces in ferrocyanide tanks. This conclusion is based in part on the following factors: (1) a study performance on waste aging suggests that the ferrocyanide has degraded in the tanks during the more than 35 years of storage; therefore, the ferrocyanide is not present in concentrations that could support an exothermic reaction, also, the moisture present in the waste is sufficient to preclude a self-sustaining (propagating) ferrocyanide-nitrate reaction; (2) evaluation of core sample results from Tank 241-C-109 and Tank 241-C-112 support laboratory studies showing that ferrocyanide has degraded and the fuel concentration in the tanks is considerably lower than postulated by flowsheet simulants; (3) no gases have been identified that would indicate the occurrence of a ferrocyanide nitrate/nitrite reaction; additionally, a self-sustaining ferrocyanide nitrate/nitrite reaction is not possible under current and future planned storage conditions. After reviewing the available information, it is evident that there would be little safety benefit from continuous in-tank vapor monitoring, and the time and commitment of operations schedule and equipment funds are not justified in the face of competing needs.

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

    SciTech Connect

    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

    2009-03-01

    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

  9. Fluidic Sampler. Tanks Focus Area. OST Reference No. 2007

    SciTech Connect

    None, None

    1999-09-01

    Problem Definition; Millions of gallons of radioactive and hazardous wastes are stored in underground tanks across the U.S. Department of Energy (DOE) complex. To manage this waste, tank operators need safe, cost-effective methods for mixing tank material, transferring tank waste between tanks, and collecting samples. Samples must be collected at different depths within storage tanks containing various kinds of waste including salt, sludge, and supernatant. With current or baseline methods, a grab sampler or a core sampler is inserted into the tank, waste is maneuvered into the sample chamber, and the sample is withdrawn from the tank. The mixing pumps in the tank, which are required to keep the contents homogeneous, must be shut down before and during sampling to prevent airborne releases. These methods are expensive, require substantial hands-on labor, increase the risk of worker exposure to radiation, and often produce nonrepresentative and unreproducible samples. How It Works: The Fluidic Sampler manufactured by AEA Technology Engineering Services, Inc., enables tank sampling to be done remotely with the mixing pumps in operation. Remote operation minimizes the risk of exposure to personnel and the possibility of spills, reducing associated costs. Sampling while the tank contents are being agitated yields consistently homogeneous, representative samples and facilitates more efficient feed preparation and evaluation of the tank contents. The above-tank portion of the Fluidic Sampler and the replacement plug and pipework that insert through the tank top are shown.

  10. Hanford single-shell tank grouping study

    SciTech Connect

    Remund, K.M.; Anderson, C.M.; Simpson, B.C.

    1995-10-01

    A tank grouping study has been conducted to find Hanford single-shell tanks with similar waste properties. The limited sampling resources of the characterization program could be allocated more effectively by having a better understanding of the groups of tanks that have similar waste types. If meaningful groups of tanks can be identified, tank sampling requirements may be reduced, and the uncertainty of the characterization estimates may be narrowed. This tank grouping study considers the analytical sampling information and the historical information that is available for all single-shell tanks. The two primary sources of historical characterization estimates and information come from the Historical Tank Content Estimate (HTCE) Model and the Sort on Radioactive Waste Tanks (SORWT) Model. The sampling and historical information are used together to come up with meaningful groups of similar tanks. Based on the results of analyses presented in this report, credible tank grouping looks very promising. Some groups defined using historical information (HTCE and SORWT) correspond well with those based on analytical data alone.

  11. Dual Tank Fuel System

    DOEpatents

    Wagner, Richard William; Burkhard, James Frank; Dauer, Kenneth John

    1999-11-16

    A dual tank fuel system has primary and secondary fuel tanks, with the primary tank including a filler pipe to receive fuel and a discharge line to deliver fuel to an engine, and with a balance pipe interconnecting the primary tank and the secondary tank. The balance pipe opens close to the bottom of each tank to direct fuel from the primary tank to the secondary tank as the primary tank is filled, and to direct fuel from the secondary tank to the primary tank as fuel is discharged from the primary tank through the discharge line. A vent line has branches connected to each tank to direct fuel vapor from the tanks as the tanks are filled, and to admit air to the tanks as fuel is delivered to the engine.

  12. Caustic-Side Solvent Extraction: Prediction of Cesium Extraction for Actual Wastes and Actual Waste Simulants

    SciTech Connect

    Delmau, L.H.; Haverlock, T.J.; Sloop, F.V., Jr.; Moyer, B.A.

    2003-02-01

    This report presents the work that followed the CSSX model development completed in FY2002. The developed cesium and potassium extraction model was based on extraction data obtained from simple aqueous media. It was tested to ensure the validity of the prediction for the cesium extraction from actual waste. Compositions of the actual tank waste were obtained from the Savannah River Site personnel and were used to prepare defined simulants and to predict cesium distribution ratios using the model. It was therefore possible to compare the cesium distribution ratios obtained from the actual waste, the simulant, and the predicted values. It was determined that the predicted values agree with the measured values for the simulants. Predicted values also agreed, with three exceptions, with measured values for the tank wastes. Discrepancies were attributed in part to the uncertainty in the cation/anion balance in the actual waste composition, but likely more so to the uncertainty in the potassium concentration in the waste, given the demonstrated large competing effect of this metal on cesium extraction. It was demonstrated that the upper limit for the potassium concentration in the feed ought to not exceed 0.05 M in order to maintain suitable cesium distribution ratios.

  13. Short communication: comparing real-time PCR and bacteriological cultures for Streptococcus agalactiae and Staphylococcus aureus in bulk-tank milk samples.

    PubMed

    Zanardi, G; Caminiti, A; Delle Donne, G; Moroni, P; Santi, A; Galletti, G; Tamba, M; Bolzoni, G; Bertocchi, L

    2014-09-01

    For more than 30 yr, a control plan for Streptococcus agalactiae and Staphylococcus aureus has been carried out in more than 1,500 dairy herds of the province of Brescia (northern Italy). From 2010 to 2011, the apparent prevalence of Strep. agalactiae has been relatively stable around 10%, but the apparent prevalence of Staph. aureus has been greater than 40% with an increasing trend. The aim of this paper was to estimate and compare the diagnostic accuracy of 3 assays for the detection of Strep. agalactiae and Staph. aureus in bulk-tank milk samples (BTMS) in field conditions. The assays were a qualitative and a quantitative bacteriological culture (BC) for each pathogen and a homemade multiplex real-time PCR (rt-PCR). Because a gold standard was not available, the sensitivities (Se) and specificities (Sp) were evaluated using a Bayesian latent class approach. In 2012 we collected one BTMS from 165 dairy herds that were found positive for Strep. agalactiae in the previous 2-yr campaigns of eradication plan. In most cases, BTMS collected in these herds were positive for Staph. aureus as well, confirming the wide spread of this pathogen. At the same time we also collected composite milk samples from all the 8,624 lactating cows to evaluate the within-herd prevalence of Strep. agalactiae. Streptococcus agalactiae samples were cultured using a selective medium Tallium Kristalviolette Tossin, whereas for Staph. aureus, we used Baird Parker modified medium with added Rabbit Plasma Fibrinogen ISO-Formulation. In parallel, BTMS were tested using the rt-PCR. Regarding Strep. agalactiae, the posterior median of Se and Sp of the 2 BC was similar [qualitative BC: Se=98%, posterior credible interval (95%PCI): 94-100%, and Sp=99%, 95%PCI: 96-100%; quantitative BC: Se=99%, 95%PCI: 96-100%, and Sp=99%, 95%PCI: 95-100%] and higher than those of the rt-PCR (at 40 cycle threshold, Se=92%, 95%PCI: 85-97%; Sp=94%, 95%PCI: 88-98%). Also in case of Staph. aureus, the posterior medians

  14. 45-Day safety screen results for single shell tank 241-AP-106, liquid grab samples, riser 1, 30{degrees} and 150{degrees} in conjunction with evaporator campaign 95-1

    SciTech Connect

    Miller, G.L.

    1994-12-14

    This is the 45-Day report for the fiscal year 1995 safety screening characterization of three liquid grab samples from single shell tank 241-AP-106. The required analyses are differential scanning calorimetry (DSC), thermal gravimetric analysis (TGA) and appearance (APPR). No analytes exceeded the notification limits, therefore, secondary analyses (RSST, cyanide, and hot persulfate-total organic carbon) were not required. Summary data tables 2, 3 and 4 present the appearance, DSC and TGA data, respectively. Total alpha analyses are not included in this report, because it is not required for liquid grab samples.

  15. Tank 241-BY-103 Tank Characterization Plan. Revision 1

    SciTech Connect

    Schreiber, R.D.

    1995-02-27

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-103.

  16. Think Tank.

    ERIC Educational Resources Information Center

    Governick, Heather; Wellington, Thom

    1998-01-01

    Examines the options for upgrading, replacing, and removal or closure of underground storage tanks (UST). Reveals the diverse regulatory control involving USTs, the Environmental Protection Agency's interest in pursuing violators, and stresses the need for administrators to be knowledgeable about state and local agency definitions of regulated…

  17. Tank characterization report for double-shell tank 241-AN-103

    SciTech Connect

    Wilkins, N.E.

    1997-08-22

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AN-103. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10. (This tank has been designated an Hydrogen Watch List tank.)

  18. Supporting document for the SW Quadrant Historical Tank Content Estimate for U-Tank Farm

    SciTech Connect

    Brevick, C.H.; Gaddis, L.A.; Johnson, E.D.

    1994-06-01

    This Supporting Document provides historical characterization information gathered on U-Tank Farm, such as historical waste transfer and level data, tank physical information, temperature data, sampling data, and drywell and liquid observation well data for Historical Tank Content Estimate of the SW Quadrant at the Hanford 200 West Area.

  19. Tank 11H Analytical Results as Input to DWPF Sludge Batch 4

    SciTech Connect

    CHRISTOPHER, BANNOCHIE

    2004-09-01

    SRNL was requested by DWPF to conduct analyses on dissolved samples of Tank 11H material in preparation for DWPF processing. Two separate samples of Tank 11H were pulled during Tank Farm slurry and transfer operations. These samples have been designated Tank 11 - Sample 1 and Tank 11 - Sample 2. Aliquots of each slurry sample were digested in HNO3/HF and analyzed by inductively coupled plasma - atomic emission spectroscopy, inductively coupled plasma - mass spectrometry, and cold vapor - atomic absorption spectroscopy.

  20. Tank 241-C-103 headspace flammability

    SciTech Connect

    Huckaby, J.L.

    1994-01-01

    Information regarding flammable vapors, gases, and aerosols is presented for the purpose of resolving the tank 241-C-103 headspace flammability issue. Analyses of recent vapor and liquid samples, as well as visual inspections of the tank headspace, are discussed in the context of tank dynamics. This document is restricted to issues regarding the flammability of gases, vapors, and an aerosol that may exist in the headspace of tank 241-C-103. While discussing certain information about the organic liquid present in tank 241-C-103, this document addresses neither the potential for, nor consequences of, a pool fire involving this organic liquid; they will be discussed in a separate report.

  1. Phase Chemistry of Tank Sludge Residual Components

    SciTech Connect

    J.L. Krumhansl

    2002-04-02

    The US Department of Energy (DOE) has millions of gallons of high level nuclear waste stored in underground tanks at Hanford, Washington and Savannah River, South Carolina. These tanks will eventually be emptied and decommissioned. This will leave a residue of sludge adhering to the interior tank surfaces that may contaminate nearby groundwaters with radionuclides and RCRA metals. Performance assessment (PA) calculations must be carried out prior to closing the tanks. This requires developing radionuclide release models from the sludges so that the PA calculations can be based on credible source terms. These efforts continued to be hindered by uncertainties regarding the actual nature of the tank contents and the distribution of radionuclides among the various phases. In particular, it is of vital importance to know what radionuclides are associated with solid sludge components. Experimentation on actual tank sludges can be difficult, dangerous and prohibitively expensive. The research funded under this grant for the past three years was intended to provide a cost-effective method for developing the needed radionuclide release models using non-radioactive artificial sludges. Insights gained from this work will also have more immediate applications in understanding the processes responsible for heel development in the tanks and in developing effective technologies for removing wastes from the tanks.

  2. Summary of uncertainty estimation results for Hanford tank chemical and radionuclide inventories

    SciTech Connect

    Ferryman, T.A.; Amidan, B.G.; Chen, G.

    1998-09-01

    The exact physical and chemical nature of 55 million gallons of radioactive waste held in 177 underground waste tanks at the Hanford Site is not known in sufficient detail to support safety, retrieval, and immobilization missions. The Hanford Engineering Analysis Best-Basis team has made point estimates of the inventories in each tank. The purpose of this study is to estimate probability distributions for each of the analytes and tanks for which the Hanford Best-Basis team has made point estimates. Uncertainty intervals can then be calculated for the Best-Basis inventories and should facilitate the cleanup missions. The methodology used to generate the results published in the Tank Characterization Database (TCD) and summarized in this paper is based on scientific principles, sound technical knowledge of the realities associated with the Hanford waste tanks, the chemical analysis of actual samples from the tanks, the Hanford Best-Basic research, and historical data records. The methodology builds on research conducted by Pacific Northwest National Laboratory (PNNL) over the last few years. Appendix A of this report summarizes the results of the study. The full set of results (in percentiles, 1--99) is available through the TCD, (http://twins.pnl.gov:8001).

  3. Feed tank transfer requirements

    SciTech Connect

    Freeman-Pollard, J.R.

    1998-09-16

    This document presents a definition of tank turnover. Also, DOE and PC responsibilities; TWRS DST permitting requirements; TWRS Authorization Basis (AB) requirements; TWRS AP Tank Farm operational requirements; unreviewed safety question (USQ) requirements are presented for two cases (i.e., tank modifications occurring before tank turnover and tank modification occurring after tank turnover). Finally, records and reporting requirements, and documentation which will require revision in support of transferring a DST in AP Tank Farm to a privatization contractor are presented.

  4. SUPPLEMENTAL ANALYSES FOR SOLVENT HOLD TANK SAMPLES MCU-11-314, MCU-11-315, MCU-11-316, MCU-11-317, MCU-11-318 AND MCU-11-319

    SciTech Connect

    Peters, T.; Washington, A; . Fondeur, F.; Fink, S.

    2011-09-29

    Savannah River National Laboratory (SRNL) periodically analyses solvent samples from Modular Caustic-Side Solvent Extraction Unit (MCU) in support of continuing operations. A quarterly analysis of the solvent is required to maintain solvent composition within specifications. Analytical results of the analyses of Solvent Hold Tank (SHT) samples MCU-11-314, MCU-11-315, MCU-11-316, MCU-11-317, MCU-11-318 and MCU-11-319 have been previously reported. MCU has experienced a modest decline in cesium removal efficiency while processing the current feed, 'Macrobatch 3'. While the target decontamination factor (DF) is 200, the fiscal year 2011 DF average is 161. The results of the prior solvent analysis report did not identify a specific factor that would correlate with the poor cesium decontamination beyond a low concentration of the suppressor, trioctylamine. New analyses of the quarterly sample are reported in this document, as well as a cross-check of {sup 137}Cs measurements for SRNL and F/H lab. Furthermore, in an attempt to discover the reason for the decline in DF at MCU, SRNL was tasked with analyzing numerous Caustic Wash Tank (CWT) and chemical feed samples.

  5. Test program to demonstrate the stability of hydrazine in propellant tanks

    NASA Technical Reports Server (NTRS)

    Moran, C. M.; Sutton, D.

    1983-01-01

    The suitability of stainless steels and Inconel for long-term hydrazine propellant-storage tanks is investigated. Rectangular coupon samples cut from propellent tanks were sealed with a measured amount of hydrazine in glass capsules, stored at 43 or 60 C, and removed after 6 to 24 months, when corrosion of the coupon and decomposition of the hydrazine was determined, and SEM and electron spectroscopy were performed on some coupons. Corrosion was found to be unmeasurably low for all the coupons, and hydrazine decomposition produced less than 1.0 cu cm of gas per sq cm of wetted surface per year, except in those few cases when catalysis or contamination were detected. Especially good stability was observed for type 304L stainless steel. The decomposition rates determined in the coupon tests are confirmed by preliminary results of actual tank storage trials.

  6. Tank Insulation

    NASA Technical Reports Server (NTRS)

    1979-01-01

    For NASA's Apollo program, McDonnell Douglas Astronautics Company, Huntington Beach, California, developed and built the S-IVB, uppermost stage of the three-stage Saturn V moonbooster. An important part of the development task was fabrication of a tank to contain liquid hydrogen fuel for the stage's rocket engine. The liquid hydrogen had to be contained at the supercold temperature of 423 degrees below zero Fahrenheit. The tank had to be perfectly insulated to keep engine or solar heat from reaching the fuel; if the hydrogen were permitted to warm up, it would have boiled off, or converted to gaseous form, reducing the amount of fuel available to the engine. McDonnell Douglas' answer was a supereffective insulation called 3D, which consisted of a one-inch thickness of polyurethane foam reinforced in three dimensions with fiberglass threads. Over a 13-year development and construction period, the company built 30 tanks and never experienced a failure. Now, after years of additional development, an advanced version of 3D is finding application as part of a containment system for transporting Liquefied Natural Gas (LNG) by ship.

  7. Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

    SciTech Connect

    D. H. Cox

    2001-06-01

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots'' from the concrete vault, and the drilling

  8. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 2 2013-10-01 2013-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  9. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 2 2012-10-01 2012-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  10. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 2 2014-10-01 2014-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  11. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 2 2011-10-01 2011-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  12. Supporting document for the historical tank content estimate for S tank farm

    SciTech Connect

    Brevick, C.H.; Gaddis, L.A.; Walsh, A.C.

    1994-06-01

    This document provides historical evaluations of the radioactive mixed wastes stored in the Hanford Site 200 West Area underground single-shell tanks (SSTs). A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy (DOE) and Department of Defense (DOD) contractors. The historical data will supplement information gathered from in-tank core sampling activities that are currently underway. A tank history review that is accompanied by current characterization data creates a complete and reliable inventory estimate. Additionally, historical review of the tanks may reveal anomalies or unusual contents that are critical to characterization and post characterization activities. Complete and accurate tank waste characterizations are critical first steps for DOE and Westinghouse Hanford Company safety programs, waste pretreatment, and waste retrieval activities. The scope of this document is limited to all the SSTs in the S Tank Farm of the southwest quadrant of the 200 West Area. Nine appendices compile data on: tank level histories; temperature graphs; surface level graphs; drywell graphs; riser configuration and tank cross section; sampling data; tank photographs; unknown tank transfers; and tank layering comparison. 113 refs.

  13. Supporting document for the historical tank content estimate for BY Tank Farm

    SciTech Connect

    Brevick, C.H.; Gaddis, L.A.; Walsh, A.C.

    1994-06-01

    This document provides historical evaluations of the radioactive mixed wastes stored in the Hanford Site 200-East Area underground single-shell tanks (SSTs). A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy (DOE) and Department of Defense (DOD) contractors. The historical data will supplement information gathered from in-tank core sampling activities that are currently underway. A tank history review that is accompanied by current characterization data creates a complete and reliable inventory estimate. Additionally, historical review of the tanks may reveal anomalies or unusual contents that are critical to characterization and post characterization activities. Complete and accurate tank waste characterizations are critical first steps for DOE and Westinghouse Hanford Company safety programs, waste pretreatment, and waste retrieval activities. The scope of this document is limited to the SSTs in the BY Tank Farm of the northeast quadrant of the 200 East Area. Nine appendices contain data on: tank level histories; temperature graphs; surface level graphs; drywell graphs; riser configuration and tank cross section; sampling data; tank photographs; unknown tank transfers; and tank layering comparison. 113 refs.

  14. Supporting document for the historical tank content estimate for B Tank Farm

    SciTech Connect

    Brevick, C.H.; Gaddis, L.A.; Johnson, E.D.

    1994-06-01

    This document provides historical evaluations of the radioactive mixed wastes stored in the Hanford Site 200-East Area underground single-shell tanks (SSTs). A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy (DOE) and Department of Defense (DOD) contractors. The historical data will supplement information gathered from in-tank core sampling activities that are currently underway. A tank history review that is accompanied by current characterization data creates a complete and reliable inventory estimate. Additionally, historical review of the tanks may reveal anomalies or unusual contents that are critical to characterization and post characterization activities. Complete and accurate tank waste characterizations are critical first steps for DOE and Westinghouse Hanford Company safety programs, waste pretreatment, and waste retrieval activities. The scope of this document is limited to the SSTs in the B Tank Farm of the northeast quadrant of the 200 East Area. Nine appendices compile data on: tank level histories; temperature graphs; surface level graphs; drywell graphs; riser configuration and tank cross section; sampling data; tank photographs; unknown tank transfers; and tank layering comparison. 113 refs.

  15. Supporting document for the historical tank content estimate for A Tank Farm

    SciTech Connect

    Brevick, C.H.; Gaddis, L.A.; Walsh, A.C.

    1994-06-01

    This document provides historical evaluations of the radioactive mixed wastes stored in the Hanford Site 200-East Area underground single-shell tanks (SSTs). A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy (DOE) and Department of Defense (DOD) contractors. The historical data will supplement information gathered from in-tank core sampling activities that are currently underway. A tank history review that is accompanied by current characterization data creates a complete and reliable inventory estimate. Additionally, historical review of the tanks may reveal anomalies or unusual contents that are critical to characterization and post characterization activities. Complete and accurate tank waste characterizations are critical first steps for DOE and Westinghouse Hanford Company safety programs, waste pretreatment, and waste retrieval activities. The scope of this document is limited to the SSTs in the A Tank Farm of the northeast quadrant of the 200 East Area. Nine appendices compile data on: tank level histories; temperature graphs; surface level graphs; drywell graphs; riser configuration and tank cross section; sampling data; tank photographs; unknown tank transfers; and tank layering comparison. 113 refs.

  16. Composite Tank Technologies Development

    NASA Technical Reports Server (NTRS)

    DeLay, Tom

    2005-01-01

    The need for cryogenic fuel tanks continues to expand, and research at NASA Marshall Space Flight Center (MSFC) is addressing these needs. This viewgraph presentation provides an overview of composite tank development, including tank testing, cryogenic materials research, tank liners, and dual-walled tanks, at MSFC.

  17. Tank 241-AP-107 tank characterization plan. Revision 1

    SciTech Connect

    Schreiber, R.D.

    1995-01-20

    Defense Nuclear Facilities Safety Board has directed the DOE to concentrate ear-term sampling and analysis activities on identification and resolution of issues (Conway 1993). The Data Quality Objective (DQO) process was chosen as a tool to be used in the resolution of safety issues. As a result, a revision in the Federal Facilities Agreement and Consent Order (Tri-Party Agreement) milestone M-44-00 has been made, which states that ``A Tank Characterization Plan (TCP) will be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process; Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.`` This document satisfies that requirement for the tank 241-AP-107 (AP-107).

  18. ICPP Tank Farm planning through 2012

    SciTech Connect

    Palmer, W.B.; Millet, C.B.; Staiger, M.D.; Ward, F.S.

    1998-04-01

    Historically, liquid high-level waste (HLW) generated at the Idaho Chemical Processing Plant has been stored in the Tank Farm after which it is calcined with the calcine being stored in stainless steel bins. Following the curtailment of spent nuclear fuel reprocessing in 1992, the HLW treatment methods were re-evaluated to establish a path forward for producing a final waste form from the liquid sodium bearing wastes (SBW) and the HLW calcine. Projections for significant improvements in waste generation, waste blending and evaporation, and calcination were incorporated into the Tank Farm modeling. This optimized modeling shows that all of the SBW can be calcined by the end of 2012 as required by the Idaho Settlement Agreement. This Tank Farm plan discusses the use of each of the eleven HLW tanks and shows that two tanks can be emptied, allowing them to be Resource Conservation and Recovery Act closed by 2006. In addition, it describes the construction of each tank and vault, gives the chemical concentrations of the contents of each tank, based on historical input and some sampling, and discusses the regulatory drivers important to Tank Farm operation. It also discusses new waste generation, the computer model used for the Tank Farm planning, the operating schedule for each tank, and the schedule for when each tank will be empty and closed.

  19. Dynamic Effects of Tank Waste Aging on Radionuclide-Complexant Interactions - Final Report - 10/01/1997 - 10/01/2000

    SciTech Connect

    Chamberlin, Rebecca M.; Arterburn, Jeffrey B. rmchamberlin@lanl.gov; jarterbu@nmsu.edu

    2000-10-01

    The long-range objective of this project is to provide a scientific basis for safely processing high-level nuclear tanks wastes for disposal. Our goals are to identify a means to prepare realistic simulant formulations for complexant-containing Hanford tank wastes, and then use those simulants to determine the relative importance of various organic complexants and their breakdown products on the partitioning of important radionuclides. The harsh chemical and radiolytic environment in high-level waste tanks alters both the organic complexants and the metal species, producing radionuclide-chelator complexes that resist standard separation methods. A detailed understanding of the complexation reactions of the key radionuclides in tank wastes would allow for reliable, science-based solutions for high-level waste processing, but a key problem is that tank waste samples are exceedingly difficult to obtain, transport and handle in the laboratory. In contrast, freshly-prepared simulated wastes are safe and readily obtained, but they do not reproduce the partitioning behavior of actual tank waste samples. For this project, we will first artificially age complexant-containing tank waste simulants using microwave, ultrasound, and photolysis techniques that can be applied in any standard laboratory. The aged samples will be compared to samples of actual Hanford tank wastes to determine the most realistic aging method, on the basis of the organic fragments present, and the oxidation states and partitioning behavior of important radionuclides such as 90Sr, 99Tc, and 239Pu. Our successful completion of this goal will make it possible for scientists in academic and industrial laboratories to address tank waste remediation problems without the enormous costs and hazards associated with handling actual tank waste samples. Later, we will use our simulant aging process to investigate the relative effects of chelator degradation products on the partitioning of important radionuclides

  20. Legislation pertaining to underground storage tanks

    SciTech Connect

    Goth, W. )

    1994-04-01

    Statutory authority in California for cleanup of contaminated soil and groundwater to protect water quality is the Porter Cologne Water Quality Control Act (Water Code 1967). Two state laws regulating underground hazardous material storage tanks, passed in late 1983 and effective on January 1, 1984, were AB-2013 (Cortese) and AB-1362 (Sher). Both require specific actions by the tank owners. AB-2013 requires all tank owners to register them with the state Water Resources Control Board (SWCB) and to pay a registration fee. AB-1362, Health and Safety Code Section 25280 et seq., requires tank owners to obtain a Permit to Operate, pay a fee to the local agency, and to install a leak detection system on all existing tanks. New tanks installation requires a Permit to install and provide provide secondary containment for the tank and piping. For tank closures, a permit must be obtained from the local agency to clean out the tank, remove it from the ground, and collect samples from beneath the tank for evidence of contamination. In 1988, state law AB-853 appropriated state funds to be combined with federal EPA money to allow SWRCB to initiate rapid cleanups of leaks from underground tank sites by contracting with local agencies to oversee assessment and cleanup of underground tank releases. Locally, in Ventura County, there are more than 400 leaking underground tank sites in which petroleum products have entered the groundwater. To date, no public water supplies have been contaminated; however, action in necessary to prevent any future contamination to our water supply. Over 250 leaking tank sites have completed cleanup.

  1. Jet mixing long horizontal storage tanks

    SciTech Connect

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

    1994-12-01

    Large storage tanks may require mixing to achieve homogeneity of contents for several reasons: prior to sampling for mass balance purposes, for blending in reagents, for suspending settled solids for removal, or for use as a feed tank to a process. At ORNL, mixed waste evaporator concentrates are stored in 50,000-gal tanks, about 12 ft in diameter and 60 ft long. This tank configuration has the advantage of permitting transport by truck and therefore fabrication in the shop rather than in the field. Jet mixing experiments were carried out on two model tanks: a 230-gal (1/6-linear-scale) Plexiglas tank and a 25,000-gal tank (about 2/3 linear scale). Mixing times were measured using sodium chloride tracer and several conductivity probes distributed through the tanks. Several jet sizes and configurations were tested. One-directional and two-directional jets were tested in both tanks. Mixing times for each tank were correlated with the jet Reynolds number. Mixing times were correlated for the two tank sizes using the recirculation time for the developed jet. When the recirculation times were calculated using the distance from the nozzle to the end of the tank as the length of the developed jet, the correlation was only marginally successful. Data for the two tank sizes were correlated empirically using a modified effective jet length expressed as a function of the Reynolds number raised to the 1/3 power. Mixing experiments were simulated using the TEMTEST computer program. The simulations predicted trends correctly and were within the scatter of the experimental data with the lower jet Reynolds numbers. Agreement was not as good at high Reynolds numbers except for single nozzles in the 25,000-gal tank, where agreement was excellent over the entire range.

  2. AX Tank Farm tank removal study

    SciTech Connect

    SKELLY, W.A.

    1999-02-24

    This report examines the feasibility of remediating ancillary equipment associated with the 241-AX Tank Farm at the Hanford Site. Ancillary equipment includes surface structures and equipment, process waste piping, ventilation components, wells, and pits, boxes, sumps, and tanks used to make waste transfers to/from the AX tanks and adjoining tank farms. Two remedial alternatives are considered: (1) excavation and removal of all ancillary equipment items, and (2) in-situ stabilization by grout filling, the 241-AX Tank Farm is being employed as a strawman in engineering studies evaluating clean and landfill closure options for Hanford single-shell tanks. This is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

  3. Tank characterization report for double-shell tank 241-AN-102

    SciTech Connect

    Jo, J., Westinghouse Hanford

    1996-08-29

    This characterization report summarizes the available information on the historical uses, current status, and sampling and analysis results of waste stored in double-shell underground storage tank 241- AN-102. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09 (Ecology et al. 1996). Tank 241-AN-102 is one of seven double-shell tanks located in the AN Tank Farm in the Hanford Site 200 East Area. The tank was hydrotested in 1981, and when the water was removed, a 6-inch heel was left. Tank 241-AN-102 began receiving waste from tank 241-SY-102 beginning in 1982. The tank was nearly emptied in the third quarter of 1983, leaving only 125 kL (33 kgal) of waste. Between the fourth quarter of 1983 and the first quarter of 1984, tank 241-AN-102 received waste from tanks 241-AY-102, 241-SY-102, 241-AW-105, and 241- AN-101. The tank was nearly emptied in the second quarter of 1984, leaving a heel of 129 kL (34 kgal). During the second and third quarters of 1984, the tank was filled with concentrated complexant waste from tank 241-AW-101. Since that time, only minor amounts of Plutonium-Uranium Extraction (PUREX) Plant miscellaneous waste and water have been received; there have been no waste transfer to or from the tank since 1992. Therefore, the waste currently in the tank is considered to be concentrated complexant waste. Tank 241-AN-102 is sound and is not included on any of the Watch Lists.

  4. CESIUM REMOVAL FROM TANKS 241-AN-103 & 241-SX-105 & 241-AZ-101 & 241AZ-102 COMPOSITE FOR TESTING IN BENCH SCALE STEAM REFORMER

    SciTech Connect

    DUNCAN JB; HUBER HJ

    2011-04-21

    This report documents the preparation of three actual Hanford tank waste samples for shipment to the Savannah River National Laboratory (SRNL). Two of the samples were dissolved saltcakes from tank 241-AN-103 (hereafter AN-103) and tank 241-SX-105 (hereafter SX-105); one sample was a supernate composite from tanks 241-AZ-101 and 241-AZ-102 (hereafter AZ-101/102). The preparation of the samples was executed following the test plans LAB-PLAN-10-00006, Test Plan for the Preparation of Samples from Hanford Tanks 241-SX-105, 241-AN-103, 241-AN-107, and LAB-PLN-l0-00014, Test Plan for the Preparation of a Composite Sample from Hanford Tanks 241-AZ-101 and 241-AZ-102 for Steam Reformer Testing at the Savannah River National Laboratory. All procedural steps were recorded in laboratory notebook HNF-N-274 3. Sample breakdown diagrams for AN-103 and SX-105 are presented in Appendix A. The tank samples were prepared in support of a series of treatability studies of the Fluidized Bed Steam Reforming (FBSR) process using a Bench-Scale Reformer (BSR) at SRNL. Tests with simulants have shown that the FBSR mineralized waste form is comparable to low-activity waste glass with respect to environmental durability (WSRC-STI-2008-00268, Mineralization of Radioactive Wastes by Fluidized Bed Steam Reforming (FBSR): Comparisons to Vitreous Waste Forms and Pertinent Durability Testing). However, a rigorous assessment requires long-term performance data from FBSR product formed from actual Hanford tank waste. Washington River Protection Solutions, LLC (WRPS) has initiated a Waste Form Qualification Program (WP-5.2.1-2010-001, Fluidized Bed Steam Reformer Low-level Waste Form Qualification) to gather the data required to demonstrate that an adequate FBSR mineralized waste form can be produced. The documentation of the selection process of the three tank samples has been separately reported in RPP-48824, Sample Selection Process for Bench-Scale Steam Reforming Treatability Studies Using

  5. CESIUM REMOVAL FROM TANKS 241-AN-103 & 241-SX-105 & 241-AZ-101/102 COMPOSITE FOR TESTING IN BENCH SCALE STEAM REFORMER

    SciTech Connect

    DUNCAN JB; HUBER HJ

    2011-06-08

    This report documents the preparation of three actual Hanford tank waste samples for shipment to the Savannah River National Laboratory (SRNL). Two of the samples were dissolved saltcakes from tank 241-AN-103 (hereafter AN-103) and tank 241-SX-105 (hereafter SX-105); one sample was a supernate composite from tanks 241-AZ-101 and 241-AZ-102 (hereafter AZ-101/102). The preparation of the samples was executed following the test plans LAB-PLAN-10-00006, Test Plan for the Preparation of Samples from Hanford Tanks 241-SX-105, 241-AN-103, 241-AN-107, and LAB-PLN-10-00014, Test Plan for the Preparation of a Composite Sample from Hanford Tanks 241-AZ-101 and 241-AZ-102 for Steam Reformer Testing at the Savannah River National Laboratory. All procedural steps were recorded in laboratory notebook HNF-N-274 3. Sample breakdown diagrams for AN-103 and SX-105 are presented in Appendix A. The tank samples were prepared in support of a series of treatability studies of the Fluidized Bed Steam Reforming (FBSR) process using a Bench-Scale Reformer (BSR) at SRNL. Tests with simulants have shown that the FBSR mineralized waste form is comparable to low-activity waste glass with respect to environmental durability (WSRC-STI-2008-00268, Mineralization of Radioactive Wastes by Fluidized Bed Steam Reforming (FBSR): Comparisons to Vitreous Waste Forms and Pertinent Durability Testing). However, a rigorous assessment requires long-term performance data from FB SR product formed from actual Hanford tank waste. Washington River Protection Solutions, LLC (WRPS) has initiated a Waste Form Qualification Program (WP-S.2.1-20 1 0-00 1, Fluidized Bed Steam Reformer Low-level Waste Form Qualification) to gather the data required to demonstrate that an adequate FBSR mineralized waste form can be produced. The documentation of the selection process of the three tank samples has been separately reported in RPP-48824, 'Sample Selection Process for Bench-Scale Steam Reforming Treatability Studies Using

  6. Flammable Gas Safety Program: actual waste organic analysis FY 1996 progress report; Flammable Gas Safety Program: actual waste organic analysis FY 1996 progress report

    SciTech Connect

    Clauss, S.A.; Grant, K.E.; Hoopes, V.; Mong, G.M.; Rau, J.; Steele, R.; Wahl, K.H.

    1996-09-01

    This report describes the status of optimizing analytical methods to account for the organic components in Hanford waste tanks, with emphasis on tanks assigned to the Flammable Gas Watch List. The methods developed are illustrated by their application to samples from Tanks 241-SY-103 and 241-S-102. Capability to account for organic carbon in Tank SY-101 was improved significantly by improving techniques for isolating organic constituents relatively free from radioactive contamination and by improving derivatization methodology. The methodology was extended to samples from Tank SY-103 and results documented in this report. Results from analyzing heated and irradiated SY-103 samples (Gas Generation Task) and evaluating methods for analyzing tank waste directly for chelators and chelator fragments are also discussed.

  7. Tank characterization report for double-shell Tank 241-AW-105

    SciTech Connect

    DiCenso, A.T.; Amato, L.C.; Franklin, J.D.; Lambie, R.W.; Stephens, R.H.; Simpson, B.C.

    1994-09-28

    In May 1990, double-shell Tank 241-AW-105 was sampled to determine proper handling of the waste, to address corrosivity and compatibility issues, and to comply with requirements of the Washington Administrative Code. This Tank Characterization Report presents an overview of that tank sampling and analysis effort, and contains observations regarding waste characteristics. It also addresses expected concentration and bulk inventory data for the waste contents based on this latest sampling data and background tank information. This report summarizes the available information regarding the waste in Tank 241-AW-105, and using the historical information to place the analytical data in context, arranges this information in a useful format for making management and technical decisions concerning this waste tank. In addition, conclusions and recommendations are given based on safety issues and further characterization needs.

  8. EVALUATION OF LOW TEMPERATURE ALUMINUM DISSOLUTION IN TANK 51

    SciTech Connect

    Pike, J

    2008-09-04

    Liquid Waste Organization (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, which became the baseline aluminum dissolution process. LWO initiated a project to modify a waste tank to meet these requirements. Subsequent to an alternative evaluation, LWO management identified an opportunity to perform aluminum dissolution on sludge destined for Sludge Batch 5, but within a limited window that would not allow time for any modifications for tank heating. A variation of the baseline process, dubbed Low Temperature Aluminum Dissolution (LTAD), was developed based on the constraint of available energy input in Tank 51 and the window of opportunity, but was not constrained to a minimum extent of dissolution, i.e. dissolve as much aluminum as possible within the time available. This process was intended to operate between 55 and 70 C, but for a significantly longer time than the baseline process. LTAD proceeded in parallel with the baseline project. The preliminary evaluation at the completion of LTAD focused on the material balance and extent of the aluminum dissolved. The range of values of extent of dissolution, 56% to 64%, resulted from the variation in liquid phase sample data available at the time. Additional solid phase data is available from a sample taken after LTAD to refine this range. This report provides additional detailed evaluation of the LTAD process based on analytical and field data and includes: a summary of the process chronology; a determination of an acceptable blending strategy for the aluminum-laden supernate stored in Tank 11; an update to the determination of aluminum dissolved using more complete sample results; a determination of the effect of LTAD on uranium, plutonium, and other metals; a determination of the rate of heat

  9. Tank characterization report for Single-Shell Tank 241-T-107

    SciTech Connect

    Valenzuela, B.D.; Jensen, L.

    1994-09-01

    Single shell tank 241-T-107 is a Hanford Site Ferrocyanide Watch List tank most recently sampled in March 1993. Analyses of materials obtained from tank T-107 were conducted to support the Ferrocyanide Unreviewed Safety Question (USQ) and the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-06 as well as Milestones M-44-05 and M-44-07. Characterization of the tank waste T-107 will support the ferrocyanide safety issue in order to classify the tank as safe, conditionally safe, or unsafe. This tank characterization report expands on the data found in Ferrocyanide Safety Program: Data Interpretation Report for Tank 241-T-107 Core Samples. Analysis of core samples obtained from tank T-107 strongly indicate the cyanide and oxidizer (nitrate/nitrite) concentrations in the tank waste are not significant enough to support a self-sustaining exothermic reaction. Therefore, the contents of tank T-107 present no imminent threat to the workers at the Hanford Site, the public, or the environment. Because the possibility of an exothermic reaction is remote, the consequences of an accident scenario, as proposed by the General Accounting Office, are not applicable.

  10. Preliminary tank characterization report for single-shell tank 241-TX-108: best-basis inventory

    SciTech Connect

    Jo, J.

    1997-08-26

    This document is a preliminary Tank Characterization Report (TCR). It only contains the current best-basis inventory (Appendix D) for single-shell tank 241-TX-108. No TCR has been previously issued for this tank, and current core sample analyses are not available. The best-basis inventory, therefore, is based on an engineering assessment of waste type, process flowsheet data, and/or other available information. The Standard Inventories of Chemicals and Radionuclides in Hanford Site Tank Wastes describes standard methodology used to derive the tank-by-tank best-basis inventories. This preliminary TCR will be updated using this same methodology when additional data on tank contents become available.

  11. Summary of tank waste physical properties at the Hanford Site

    SciTech Connect

    Nguyen, Q.H.

    1994-04-01

    This report summarizes the physical parameters measured from Hanford Site tank wastes. Physical parameters were measured to determine the physical nature of the tank wastes to develop simulants and design in-tank equipment. The physical parameters were measured mostly from core samples obtained directly below tank risers. Tank waste physical parameters were collected through a database search, interviewing and selecting references from documents. This report shows the data measured from tank waste but does not describe how the analyses wee done. This report will be updated as additional data are measured or more documents are reviewed.

  12. AX Tank Farm tank removal study

    SciTech Connect

    SKELLY, W.A.

    1998-10-14

    This report considers the feasibility of exposing, demolishing, and removing underground storage tanks from the 241-AX Tank Farm at the Hanford Site. For the study, it was assumed that the tanks would each contain 360 ft{sup 3} of residual waste (corresponding to the one percent residual Inventory target cited in the Tri-Party Agreement) at the time of demolition. The 241-AX Tank Farm is being employed as a ''strawman'' in engineering studies evaluating clean and landfill closure options for Hanford single-shell tank farms. The report is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

  13. Tank Characterization Report for Single Shell Tank 241-U-103

    SciTech Connect

    ADAMS, M.R.

    2000-02-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-U-103. This report supports the requirements of the Tri-Party Agreement Milestone M-44-15B.

  14. Tank characterization report for single-shell Tank 241-B-110

    SciTech Connect

    Amato, L.C.; De Lorenzo, D.S.; DiCenso, A.T.; Rutherford, J.H.; Stephens, R.H.; Heasler, P.G.; Brown, T.M.; Simpson, B.C.

    1994-08-01

    Single-shell Tank 241-B-110 is an underground storage tank containing radioactive waste. The tank was sampled at various times between August and November of 1989 and later in April of 1990. The analytical data gathered from these sampling efforts were used to generate this Tank Characterization Report. Tank 241-B-110, located in the 200 East Area B Tank Farm, was constructed in 1943 and 1944, and went into service in 1945 by receiving second cycle decontamination waste from the B and T Plants. During the service life of the tank, other wastes were added including B Plant flush waste, B Plant fission product waste, B Plant ion exchange waste, PUREX Plant coating waste, and waste from Tank 241-B-105. The tank currently contains 246,000 gallons of non-complexed waste, existing primarily as sludge. Approximately 22,000 gallons of drainable interstitial liquid and 1,000 gallons of supernate remain. The solid phase of the waste is heterogeneous, for the top layer and subsequent layers have significantly different chemical compositions and are visually distinct. A complete analysis of the top layer has not been done, and auger sampling of the top layer is recommended to fully characterize the waste in Tank 241-B-110. The tank is not classified as a Watch List tank; however, it is a Confirmed Leaker, having lost nearly 10,000 gallons of waste. The waste in Tank 241-B-110 is primarily precipitated salts, some of which are composed of radioactive isotopes. The most prevalent analytes include water, bismuth, iron, nitrate, nitrite, phosphate, silicon, sodium, and sulfate. The major radionuclide constituents are {sup 137}Cs and {sup 90}Sr.

  15. HANFORD TANK CLEANUP UPDATE

    SciTech Connect

    BERRIOCHOA MV

    2011-04-07

    Access to Hanford's single-shell radioactive waste storage tank C-107 was significantly improved when workers completed the cut of a 55-inch diameter hole in the top of the tank. The core and its associated cutting equipment were removed from the tank and encased in a plastic sleeve to prevent any potential spread of contamination. The larger tank opening allows use of a new more efficient robotic arm to complete tank retrieval.

  16. 7 CFR 160.28 - Tank cars of turpentine.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 7 Agriculture 3 2013-01-01 2013-01-01 false Tank cars of turpentine. 160.28 Section 160.28... STANDARDS FOR NAVAL STORES Analysis, Inspection, and Grading on Request § 160.28 Tank cars of turpentine. A tank car loaded for shipment with spirits of turpentine shall, after the same has been sampled...

  17. 7 CFR 160.28 - Tank cars of turpentine.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 7 Agriculture 3 2012-01-01 2012-01-01 false Tank cars of turpentine. 160.28 Section 160.28... STANDARDS FOR NAVAL STORES Analysis, Inspection, and Grading on Request § 160.28 Tank cars of turpentine. A tank car loaded for shipment with spirits of turpentine shall, after the same has been sampled...

  18. 7 CFR 160.28 - Tank cars of turpentine.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 7 Agriculture 3 2014-01-01 2014-01-01 false Tank cars of turpentine. 160.28 Section 160.28... STANDARDS FOR NAVAL STORES Analysis, Inspection, and Grading on Request § 160.28 Tank cars of turpentine. A tank car loaded for shipment with spirits of turpentine shall, after the same has been sampled...

  19. 7 CFR 160.28 - Tank cars of turpentine.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 7 Agriculture 3 2011-01-01 2011-01-01 false Tank cars of turpentine. 160.28 Section 160.28... STANDARDS FOR NAVAL STORES Analysis, Inspection, and Grading on Request § 160.28 Tank cars of turpentine. A tank car loaded for shipment with spirits of turpentine shall, after the same has been sampled...

  20. Justification for Continued Operation for Tank 241-Z-361

    SciTech Connect

    BOGEN, D.M.

    1999-09-01

    This justification for continued operations (JCO) summarizes analyses performed to better understand and control the potential hazards associated with Tank 241-2-361. This revision to the JCO has been prepared to identify and control the hazards associated with sampling the tank using techniques developed and approved for use in the Tank Waste Remediation System (TWRS) at Hanford.