National Library of Energy BETA

Sample records for 3005a sw-846 6010b

  1. Comparison of SW-846 method 3051 and SW-846 method 7471A for the preparation of solid waste samples for mercury determination

    SciTech Connect (OSTI)

    Giaquinto, J.M.; Essling, A.M.; Keller, J.M.

    1996-08-01

    This report describes experimental studies to evaluate the use of EPA SW-846 method 3051 for preparation and dissolution of solid samples for Hg analysis. The study showed that the method is effective in dissolution of four sample types without significant loss of Hg. Based on results of this study, method 3051 was used for analysis of high radioactive waste samples to obtain results for a number of RCRA regulated metals without the need to utilize a separate sample preparation method (EPA SW-846 method 7471A) specific only for Hg.

  2. Comparative Analysis for Polluted Agricultural Soils with Arsenic, Lead, and Mercury in Mexico

    SciTech Connect (OSTI)

    Yarto-Ramirez, Mario; Santos-Santos, Elvira; Gavilan-Garcia, Arturo; Castro-Diaz, Jose; Gavilan-Garcia, Irma Cruz; Rosiles, Rene; Suarez, Sara

    2004-03-31

    The use of mercury in Mexico has been associated with the mining industry of Zacatecas. This activity has polluted several areas currently used for agriculture. The main objective of this study was to investigate the heavy metal concentration (Hg, As and Pb) in soil of Guadalupe Zacatecas in order to justify a further environmental risk assessment in the site. A 2X3 km grid was used for the sampling process and 20 soil samples were taken. The analysis was developed using EPA SW 846: 3050B/6010B method for arsenic and metals and EPA SW 846: 7471A for total mercury. It was concluded that there are heavy metals in agricultural soils used for corn and bean farming. For this it is required to make an environmental risk assessment and a bioavailability study in order to determine if there's a risk for heavy metals bioaccumulation in animals or human beings or metal lixiviation to aquifers.

  3. Analytical Characterization of the Thorium Nitrate Stockpile

    SciTech Connect (OSTI)

    Mattus, CH

    2003-12-30

    For several years, Oak Ridge National Laboratory (ORNL) has been supporting the Defense Logistics Agency-Defense National Stockpile Center with stewardship of a thorium nitrate (ThN) stockpile. The effort for fiscal year 2002 was to prepare a sampling and analysis plan and to use the activities developed in the plan to characterize the ThN stockpile. The sampling was performed in June and July 2002 by RWE NUKEM with oversight by ORNL personnel. The analysis was performed by Southwest Research Institute of San Antonio, Texas, and data validation was performed by NFT, Inc., of Oak Ridge, Tennessee. Of the {approx} 21,000 drums in the stockpile, 99 were sampled and 53 were analyzed for total metals composition, radiological constituents (using alpha and gamma spectrometry), and oxidizing characteristics. Each lot at the Curtis Bay Depot was sampled. Several of the samples were also analyzed for density. The average density of the domestic ThN was found to be 1.89 {+-} 0.08 g/cm{sup 3}. The oxidizer test was performed following procedures issued by the United Nations in 1999. Test results indicated that none of the samples tested was a Division 5.1 oxidizer per Department of Transportation definition. The samples were analyzed for total metals following the U.S. Environmental Protection Agency methods SW-846-6010B and 6020 (EPA 2003) using a combination of inductively coupled plasma--atomic emission spectroscopy and inductively coupled plasma--mass spectroscopy techniques. The results were used to compare the composition of the eight Resource Conservation and Recovery Act metals present in the sample (arsenic, barium, cadmium, chromium, lead, mercury, selenium, and silver) to regulatory limits. None of the samples was found to be hazardous for toxicity characteristics. The radiological analyses confirmed, when possible, the results obtained by the inductively coupled plasma analyses. These results--combined with the historical process knowledge acquired on the material and the results of previous tests--classified the ThN as low-level radioactive waste for disposal purposes. This characterization was necessary to continue the efforts associated with disposition of the material at the Nevada Test Site, Mercury, Nevada. With the current work presented in this report, the analytical characterization phase is completed for this source material stockpile.

  4. Microsoft Word - N01628_Sitewide semiannual Dec-May 2011

    Office of Legacy Management (LM)

    Kae E Yoder Project Manager II kae.yoder@testamericainc.com 04082011 The test results in ... TAL DEN TestAmerica Denver Method References: SW846 "Test Methods For Evaluating Solid ...

  5. Microsoft Word - N01962_Sitewide semiannual June-Nov14 final...

    Office of Legacy Management (LM)

    ... STAR Center Solid-Waste Management Units (SWMUs) U.S. ... Surface Sample Piezometer Water Level Not Used in Contouring ... SW846 "Test Methods For Evaluating Solid Waste, Physical...

  6. Sitewide Environmental Monitoring Semiannual Progress Report...

    Office of Legacy Management (LM)

    ... U.S. DEPARTMENT OF ENERGY OFFICE OF LEGACY MANAGEMENT Work ... blank is not present at a level greater than half the ... SW846 "Test Methods For Evaluating Solid Waste, Physical...

  7. Microsoft Word - S08406_MND_OM_Plan.docx

    Office of Legacy Management (LM)

    ... for Evaluating Solid Waste, PhysicalChemical Methods ... EPA SW-846 Method 8260B (Low Level) 1 gL PCE cis-1,2-DCE ... documentation, sample management, data validation, data ...

  8. Pinellas Sitewide Semiannual Progress Report for December 2013…May...

    Office of Legacy Management (LM)

    ... STAR Center Solid-Waste Management Units (SWMUs) U.S. ... Surface Sample Piezometer Water Level Not Used in Contouring ... SW846 "Test Methods For Evaluating Solid Waste, Physical...

  9. Microsoft Word - 13035181 13035182 DVP.docx

    Office of Legacy Management (LM)

    ... X San Juan River about 1500' below dist. Channel 1118 X Seep sump (423426) U, SO4, N as ... MIS-A-039 Chromium Gross Alpha Gross Beta Iron Lead Magnesium X X 5 SW-846 6010 LMM-01 ...

  10. Method and apparatus for controlling gas evolution from chemical reactions

    DOE Patents [OSTI]

    Skorpik, James R.; Dodson, Michael G.

    1999-01-01

    The present invention is directed toward monitoring a thermally driven gas evolving chemical reaction with an acoustic apparatus. Signals from the acoustic apparatus are used to control a heater to prevent a run-away condition. A digestion module in combination with a robotic arm further automate physical handling of sample material reaction vessels. The invention is especially useful for carrying out sample procedures defined in EPA Methods SW-846.

  11. Method and apparatus for controlling gas evolution from chemical reactions

    DOE Patents [OSTI]

    Skorpik, J.R.; Dodson, M.G.

    1999-05-25

    The present invention is directed toward monitoring a thermally driven gas evolving chemical reaction with an acoustic apparatus. Signals from the acoustic apparatus are used to control a heater to prevent a run-away condition. A digestion module in combination with a robotic arm further automate physical handling of sample material reaction vessels. The invention is especially useful for carrying out sample procedures defined in EPA Methods SW-846. 8 figs.

  12. SALTSTONE 4QCY10 TCLP RESULTS

    SciTech Connect (OSTI)

    Reigel, M.

    2011-03-31

    Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the fourth quarter of calendar year 2010 (4QCY10). After the prescribed 28 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  13. Saltstone 2QCY13 TCLP Results

    SciTech Connect (OSTI)

    Reigel, M. M.

    2013-10-29

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the second quarter of calendar year 2013 (2QCY13). After a 49 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  14. Saltstone 3QCY13 TCLP Results

    SciTech Connect (OSTI)

    Miller, D. H.

    2013-12-20

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the third quarter of calendar year 2013 (3QCY13). After a 63 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  15. Saltstone 3QCY12 TCLP Results

    SciTech Connect (OSTI)

    Eibling, R. E.

    2012-12-19

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the third quarter of calendar year 2012 (3QCY12). After a 34 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  16. Saltstone 4QCY12 TCLP results

    SciTech Connect (OSTI)

    Reigel, M. M.

    2013-03-14

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the fourth quarter of calendar year 2012 (4QCY12). After a 48 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  17. Saltstone 1QCY13 TCLP Results

    SciTech Connect (OSTI)

    Eibling, R. E.

    2013-07-08

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the first quarter of calendar year 2013 (1QCY13). After a 49 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  18. SALTSTONE 4QCY13 TCLP RESULTS

    SciTech Connect (OSTI)

    Miller, D.

    2014-04-23

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the fourth quarter of calendar year 2013 (4QCY13). After a 62 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  19. RCRA ground-water monitoring: Draft technical guidance

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    The manual was prepared to provide guidance for implementing the ground-water monitoring regulations for regulated units contained in 40 CFR Part 264 Subpart F and the permitting standards of 40 CFR Part 270. The manual also provides guidance to owners and operators of treatment, storage, and disposal facilities (TSDFs) that are required to comply with the requirements of 40 CFR Part 264 Subparts J (Tank Systems), K (Surface Impoundments), L (Waste Piles), N (Landfills), and X (Miscellaneous Units). This document updates technical information contained in other sources of U.S. EPA guidance, such as chapter eleven of SW-846 (Revision O, September 1986) and the Technical Enforcement Guidance Document (TEGD).

  20. SALTSTONE 1QCY14 TCLP RESULTS

    SciTech Connect (OSTI)

    Miller, D.

    2014-06-19

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the first quarter of calendar year 2014 (1QCY14). After a 64 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846.

  1. Sorbent Testing for the Solidification of Unidentified Rocky Flats Laboratory Waste Stored at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Bickford, J.; Kimmitt, R.

    2007-07-01

    At the request of the U.S. Department of Energy (DOE), MSE Technology Applications, Inc. (MSE) evaluated various commercially available sorbents to solidify unidentified laboratory liquids from Rocky Flats that are stored at the Idaho National Laboratory (INL). The liquids are a collection of laboratory wastes that were generated from various experiments and routine analytical laboratory activities carried out at Rocky Flats. The liquids are in bottles discovered inside of buried waste drums being exhumed from the subsurface disposal area at the Radioactive Waste Management Complex (RWMC) by the contractor, CH2M Hill Washington International (CWI). Free liquids are unacceptable at the Waste Isolation Pilot Plant (WIPP), and some of these liquids cannot be returned to the retrieval pit. Stabilization of the liquids into a solid mass will allow these materials to be sent to an appropriate disposal location. The selected sorbent or sorbent combinations should produce a stabilized mass that is capable of withstanding conditions similar to those experienced during storage, shipping, and burial. The final wasteform should release less than 1% liquid by volume per the WIPP Waste Acceptance Criteria (WAC). The absence or presence of free liquid in the solidified waste-forms was detected when tested by SW-846, Method 9095B, Paint Filter Free Liquids, and the amount of liquid released from the wasteform was determined by SW-846, Method 9096, Liquid Release Test. Reactivity testing was also conducted on the solidified laboratory liquids. (authors)

  2. Field test of a generic method for halogenated hydrocarbons: Semivost test at a chemical manufacturing facility. Final project report, August 1992-August 1993

    SciTech Connect (OSTI)

    McGaughey, J.F.; Bursey, J.T.; Merrill, R.G.

    1996-11-01

    The candidate methods for semivolatile organic compounds are SW-846 Sampling Method 0010 and Analytical Method 8270, which are applicable to stationary sources. Two field tests were conducted using quadruple sampling trains with dynamic spiking were performed according to the guidelines of EPA Method 301. The first field test was performed at a site with low levels of moisture. The second test reported here was conducted at a chemical manufacturing facility where chemical wastes were burned in a coal-fired boiler. Poor recoveries obtained for the spiked analytes at the second test were attributed to wet sorbent from the sampling train, use of methanol to effect complete transfer of wet sorbent from the sampling module, and use of extraction techniques which did not effect a complete separation of methylene chloride from methanol. A procedure to address problems with preparation of samples from Method 0010 is included in the report.

  3. A Standard Analysis Method (SAM) for the automated analysis of polychlorinated biphenyls (PCBs) in soils using the chemical analysis automation (CAA) paradigm: Validation and performance

    SciTech Connect (OSTI)

    Rzeszutko, C.; Johnson, C.R.; Monagle, M.; Klatt, L.N.

    1997-11-01

    The Chemical Analysis Automation (CAA) program is developing a standardized modular automation strategy for chemical analysis. In this automation concept, analytical chemistry is performed with modular building blocks that correspond to individual elements of the steps in the analytical process. With a standardized set of behaviors and interactions, these blocks can be assembled in a plug-and-play manner into a complete analysis system. These building blocks, which are referred to as Standard laboratory Modules (SLM), interface to a host control system that orchestrates the entire analytical process, from sample preparation through data interpretation. The integrated system is called a Standard Analysis Method (SAM). A SAM for the automated determination of polychlorinated biphenyls (PCBs) in soils, assembled in a mobile laboratory, is undergoing extensive testing and validation. The SAM consists of the following SLMs: a four-channel Soxhlet extractor, a high-volume concentration, a column clean-up, a gas chromatography, a PCB data-interpretation module, a robot, and a human-computer interface. The SAM is configured to meet the requirements specified in the US Environmental Protection Agency`s (EPA) SW-846 methods 3541/3620A/8082 for the analysis of PCBs in soils. The PCB SAM will be described along with the developmental test plan. Performance data obtained during developmental testing will also be discussed.

  4. A standard analysis method (SAM) for the automated analysis of polychlorinated biphenyls (PCBs) in soils using the chemical analysis automation (CAA) paradigm: validation and performance

    SciTech Connect (OSTI)

    Rzeszutko, C.; Johnson, C.R.; Monagle, M.; Klatt, L.N.

    1997-10-01

    The Chemical Analysis Automation (CAA) program is developing a standardized modular automation strategy for chemical analysis. In this automation concept, analytical chemistry is performed with modular building blocks that correspond to individual elements of the steps in the analytical process. With a standardized set of behaviors and interactions, these blocks can be assembled in a `plug and play` manner into a complete analysis system. These building blocks, which are referred to as Standard Laboratory Modules (SLM), interface to a host control system that orchestrates the entire analytical process, from sample preparation through data interpretation. The integrated system is called a Standard Analysis Method (SAME). A SAME for the automated determination of Polychlorinated Biphenyls (PCB) in soils, assembled in a mobile laboratory, is undergoing extensive testing and validation. The SAME consists of the following SLMs: a four channel Soxhlet extractor, a High Volume Concentrator, column clean up, a gas chromatograph, a PCB data interpretation module, a robot, and a human- computer interface. The SAME is configured to meet the requirements specified in U.S. Environmental Protection Agency`s (EPA) SW-846 Methods 3541/3620A/8082 for the analysis of pcbs in soils. The PCB SAME will be described along with the developmental test plan. Performance data obtained during developmental testing will also be discussed.

  5. Classification and storage of wastewater from floor finish removal operations

    SciTech Connect (OSTI)

    Hunt, C.E.

    1996-05-01

    This study evaluates the wastewater generated from hard surface floor finish removal operations at Lawrence Livermore Laboratory in order to determine if this wastewater is a hazardous waste, either by statistical evaluation, or other measurable regulatory guidelines established in California Regulations. This research also comparatively evaluates the 55 gallon drum and other portable tanks, all less than 1,000 gallons in size in order to determine which is most effective for the management of this waste stream at Lawrence Livermore Laboratory. The statistical methods in SW-846 were found to be scientifically questionable in their application to hazardous waste determination. In this statistical evaluation, the different data transformations discussed in the regulatory guidance document were applied along with the log transformation to the population of 18 samples from 55 gallon drums. Although this statistical evaluation proved awkward in its application, once the data is collected and organized on a spreadsheet this statistical analysis can be an effective tool which can aid the environmental manager in the hazardous waste classification process.

  6. SALTSTONE 1QCY11 TCLP RESULTS

    SciTech Connect (OSTI)

    Reigel, M.

    2011-05-16

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the first quarter of calendar year 2011 (1QCY11). After the prescribed 28 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846. The Saltstone Production Facility (SPF) receives waste from Tank 50H for treatment. In the first quarter of the 2011 calendar year (1QCY11), Tank 50H accepted transfers of approximately 15 kgal from the Effluent Treatment Project (ETP), approximately 15 kgal from Tank 710 - the H-Canyon General Purpose Evaporator, approximately 73 kgal from the H-Canyon Super Kukla campaign, approximately 285 kgal from the Actinide Removal Process/Modular Caustic Side Solvent Extraction Unit (ARP/MCU) Decontaminated Salt Solution Hold Tank (DSS-HT), and approximately 21 kgal from other sources. The Saltstone Grout Sampling plan provides the South Carolina Department of Health and Environmental Control (SCDHEC) with the chemical and physical characterization strategy for the salt solution which is to be disposed of in the Z-Area Solid Waste Landfill (SWLF). During operation, samples were collected from Tank 50H and grout samples prepared to determine the non-hazardous nature of the grout to meet the requirements of the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24(b) and R.61-79.268.48(a). Savannah River National Laboratory (SRNL) was asked to prepare saltstone from samples of Tank 50H obtained January 5, 2011 during 1QCY11 to determine the non-hazardous nature of the grout. The samples were cured and shipped to Babcock & Wilcox Technical Services Group-Radioisotope and Analytical Chemistry Laboratory (B&W TSG-RACL) to perform the Toxic Characteristic Leaching Procedure (TCLP) and subsequent extract analysis on saltstone samples for the analytes required for the quarterly analysis saltstone sample. In addition to the eight toxic metals-arsenic, barium, cadmium, chromium, mercury, lead, selenium and silver-analytes included the underlying hazardous constituents (UHC) antimony, beryllium, nickel, and thallium which could not be eliminated from analysis by process knowledge. B&W TSG-RACL provided subsamples to GEL Laboratories, LLC for analysis for the UHCs benzene, phenols and total and amenable cyanide.

  7. SALTSTONE 3QCY11 TCLP RESULTS

    SciTech Connect (OSTI)

    Bannochie, C.

    2012-01-12

    A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the third quarter of calendar year 2011 (3QCY11). After the prescribed 32 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous constituents. These analyses met all quality assurance specifications of USEPA SW-846. The Saltstone Production Facility (SPF) receives waste from Tank 50H for treatment. In the third quarter of the 2011 calendar year (3QCY11), Tank 50H accepted transfers of approximately 20 kgal from the Effluent Treatment Project (ETP), approximately 236 kgal from the Actinide Removal Process/Modular Caustic Side Solvent Extraction Unit (ARP/MCU) Decontaminated Salt Solution Hold Tank (DSS-HT), and approximately 25 kgal from other sources. The Saltstone Grout Sampling plan provides the South Carolina Department of Health and Environmental Control (SCDHEC) with the chemical and physical characterization strategy for the salt solution which is to be disposed of in the Z-Area Solid Waste Landfill (SWLF). During operation, samples were collected from Tank 50H and grout samples prepared to determine the non-hazardous nature of the grout to meet the requirements of the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24(b) and R.61-79.268.48(a). Savannah River National Laboratory (SRNL) was asked to prepare saltstone from samples of Tank 50H obtained July 7, 2011 during 3QCY11 to determine the non-hazardous nature of the grout. The samples were cured and shipped to Babcock & Wilcox Technical Services Group-Radioisotope and Analytical Chemistry Laboratory (B&W TSG-RACL) to perform the Toxic Characteristic Leaching Procedure (TCLP) and subsequent extract analysis on saltstone samples for the analytes required for the quarterly analysis saltstone sample. In addition to the eight toxic metals - arsenic, barium, cadmium, chromium, mercury, lead, selenium and silver - analytes included the underlying hazardous constituents (UHC) antimony, beryllium, nickel, and thallium which could not be eliminated from analysis by process knowledge. B&W TSG-RACL provided subsamples to GEL Laboratories, LLC for analysis for the UHCs benzene, phenols and total and amenable cyanide.

  8. SALTSTONE VAULT CLASSIFICATION SAMPLES MODULAR CAUSTIC SIDE SOLVENT EXTRACTION UNIT/ACTINIDE REMOVAL PROCESS WASTE STREAM APRIL 2011

    SciTech Connect (OSTI)

    Eibling, R.

    2011-09-28

    Savannah River National Laboratory (SRNL) was asked to prepare saltstone from samples of Tank 50H obtained by SRNL on April 5, 2011 (Tank 50H sampling occurred on April 4, 2011) during 2QCY11 to determine the non-hazardous nature of the grout and for additional vault classification analyses. The samples were cured and shipped to Babcock & Wilcox Technical Services Group-Radioisotope and Analytical Chemistry Laboratory (B&W TSG-RACL) to perform the Toxic Characteristic Leaching Procedure (TCLP) and subsequent extract analysis on saltstone samples for the analytes required for the quarterly analysis saltstone sample. In addition to the eight toxic metals - arsenic, barium, cadmium, chromium, mercury, lead, selenium and silver - analytes included the underlying hazardous constituents (UHC) antimony, beryllium, nickel, and thallium which could not be eliminated from analysis by process knowledge. Additional inorganic species determined by B&W TSG-RACL include aluminum, boron, chloride, cobalt, copper, fluoride, iron, lithium, manganese, molybdenum, nitrate/nitrite as Nitrogen, strontium, sulfate, uranium, and zinc and the following radionuclides: gross alpha, gross beta/gamma, 3H, 60Co, 90Sr, 99Tc, 106Ru, 106Rh, 125Sb, 137Cs, 137mBa, 154Eu, 238Pu, 239/240Pu, 241Pu, 241Am, 242Cm, and 243/244Cm. B&W TSG-RACL provided subsamples to GEL Laboratories, LLC for analysis for the VOCs benzene, toluene, and 1-butanol. GEL also determines phenol (total) and the following radionuclides: 147Pm, 226Ra and 228Ra. Preparation of the 2QCY11 saltstone samples for the quarterly analysis and for vault classification purposes and the subsequent TCLP analyses of these samples showed that: (1) The saltstone waste form disposed of in the Saltstone Disposal Facility in 2QCY11 was not characteristically hazardous for toxicity. (2) The concentrations of the eight RCRA metals and UHCs identified as possible in the saltstone waste form were present at levels below the UTS. (3) Most of the inorganic species measured in the leachate do not exceed the MCL, SMCL or TW limits. (4) The inorganic waste species that exceeded the MCL by more than a factor of 10 were nitrate, nitrite and the sum of nitrate and nitrite. (5) Analyses met all quality assurance specifications of US EPA SW-846. (6) The organic species (benzene, toluene, 1-butanol, phenol) were either not detected or were less than reportable for the vault classification samples. (7) The gross alpha and radium isotopes could not be determined to the MCL because of the elevated background which raised the detection limits. (8) Most of the beta/gamma activity was from 137Cs and its daughter 137mBa. (9) The concentration of 137Cs and 90Sr were present in the leachate at concentrations 1/40th and 1/8th respectively than in the 2003 vault classification samples. The saltstone waste form placed in the Saltstone Disposal Facility in 2QCY11 met the SCHWMR R.61-79.261.24(b) RCRA metals requirements for a nonhazardous waste form. The TCLP leachate concentrations for nitrate, nitrite and the sum of nitrate and nitrite were greater than 10x the MCLs in SCDHEC Regulations R.61-107.19, Part I A, which confirms the Saltstone Disposal Facility classification as a Class 3 Landfill. The saltstone waste form placed in the Saltstone Disposal Facility in 2QCY11 met the R.61-79.268.48(a) non wastewater treatment standards.

  9. Radioactive Demonstration Of Mineralized Waste Forms Made From Hanford Low Activity Waste (Tank Farm Blend) By Fluidized Bed Steam Reformation (FBSR)

    SciTech Connect (OSTI)

    Jantzen, C. M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E.; Hall, H. K.; Miller, D. H.; Missimer, D. M.; Nash, C. A.; Williams, M. F.

    2013-08-21

    The U.S. Department of Energy’s Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford’s tank waste. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Supplemental Treatment is likely to be required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP’s LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750°C) continuous method by which LAW can be processed irrespective of whether the waste contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be comparable to LAW glass, i.e. leaches Tc-99, Re and Na at <2g/m2 during ASTM C1285 (Product Consistency) durability testing. Monolithing of the granular FBSR product was investigated to prevent dispersion during transport or burial/storage. Monolithing in an inorganic geopolymer binder, which is amorphous, macro-encapsulates the granules, and the monoliths pass ANSI/ANS 16.1 and ASTM C1308 durability testing with Re achieving a Leach Index (LI) of 9 (the Hanford Integrated Disposal Facility, IDF, criteria for Tc-99) after a few days and Na achieving an LI of >6 (the Hanford IDF criteria for Na) in the first few hours. The granular and monolithic waste forms also pass the EPA Toxicity Characteristic Leaching Procedure (TCLP) for all Resource Conservation and Recovery Act (RCRA) components at the Universal Treatment Standards (UTS). Two identical Benchscale Steam Reformers (BSR) were designed and constructed at SRNL, one to treat non-radioactive simulants and the other to treat actual radioactive wastes. The results from the non-radioactive BSR were used to determine the parameters needed to operate the radioactive BSR in order to confirm the findings of non-radioactive FBSR pilot scale and engineering scale tests and to qualify an FBSR LAW waste form for applications at Hanford. Radioactive testing commenced using SRS LAW from Tank 50 chemically trimmed to look like Hanford’s blended LAW known as the Rassat simulant as this simulant composition had been tested in the non-radioactive BSR, the non-radioactive pilot scale FBSR at the Science Applications International Corporation-Science and Technology Applications Research (SAIC-STAR) facility in Idaho Falls, ID and in the TTT Engineering Scale Technology Demonstration (ESTD) at Hazen Research Inc. (HRI) in Denver, CO. This provided a “tie back” between radioactive BSR testing and non-radioactive BSR, pilot scale, and engineering scale testing. Approximately six hundred grams of non-radioactive and radioactive BSR product were made for extensive testing and comparison to the non-radioactive pilot scale tests performed in 2004 at SAIC-STAR and the engineering scale test performed in 2008 at HRI with the Rassat simulant. The same mineral phases and off-gas species were found in the radioactive and non-radioactive testing. The granular ESTD and BSR products (radioactive and non-radioactive) were analyzed for total constituents and durability tested as a granular waste form. A subset of the granular material was stabilized in a clay based geopolymer matrix at 42% and 65% FBSR loadings and durability tested as a monolith waste form. The 65 wt% FBSR loaded monolith made with clay (radioactive) was more durable than the 67-68 wt% FBSR loaded monoliths made from fly ash (non-radioactive) based on short term PCT testing. Long term, 90 to 107 day, ASTM C1308 testing (similar to ANSI/ANS 16.1 testing) was only performed on two fly ash geopolymer monoliths at 67-68 wt% FBSR loading and three clay geopolymer monoliths at 42 wt% FBSR loading. More clay geopolymers need to be made and tested at longer times at higher FBSR loadings for comparison to the fly ash monoliths. Monoliths made with metakaolin (heat treated) clay are of a more constant composition and are very reactive as the heat treated clay is amorphous and alkali activated. The monoliths made with fly ash are subject to the inherent compositional variation found in fly ash as it is a waste product from burning coal and it contains unreactive components such as mullite. However, both the fly ash and the clay based monoliths perform well in long term ASTM C1308 testing. Extensive testing and characterization of the granular and monolith material were made including the following American Society of Testing and Materials (ASTM) tests: ASTM C1285 testing (Product Consistency Test) of granular and monolithic waste forms; Comparison of granular BSR radioactive to ESTD and pilot scale granular non-radioactive waste form made from the Rassat simulant  Comparison of granular radioactive to granular non-radioactive waste form made from the Rassat simulant made using the SRNL BSR; Comparison of monolithic BSR radioactive waste forms to monolithic BSR and ESTD non-radioactive waste forms made of fly ash; Comparison of granular BSR radioactive waste forms to monolithic BSR non-radioactive waste forms made of fly ash; Comparison of granular BSR radioactive waste forms to monolithic BSR non-radioactive waste forms made of clay; ASTM C1308 Accelerated Leach Test for Diffusive Releases from Solidified Waste and a Computer Program to Model Diffusive, Fractional Leaching from Cylindrical Waste Forms; Comparison of BSR non-radioactive waste forms to monolithic ESTD non-radioactive waste forms made from fly ash; Testing of BSR non-radioactive monoliths made from clay for comparison to non-radioactive monoliths made from fly ash; ASTM C39 Compressive Strength of Cylindrical Concrete Specimens; Comparison of monolithic BSR radioactive waste forms to monolithic BSR and ESTD non-radioactive waste forms; EPA Manual SW-846 Method 1311, Toxicity Characteristic Leaching Procedure (TCLP); Comparison of granular BSR radioactive to ESTD and pilot scale granular non-radioactive waste form made from the Rassat simulant; Comparison of granular radioactive to granular non-radioactive waste form made from the Rassat simulant made using the SRNL BSR; Comparison of monolithic BSR radioactive waste forms to monolithic BSR non-radioactive waste forms.