National Library of Energy BETA

Sample records for qc sample results

  1. Reinforcing of QA/QC programs in radiotherapy departments in Croatia: Results of treatment planning system verification

    SciTech Connect (OSTI)

    Jurkovi?, Slaven; Švabi?, Manda; Dikli?, Ana; Smilovi? Radoj?i?, ?eni; Dundara, Dea; Kasabaši?, Mladen; Ivkovi?, Ana; Faj, Dario

    2013-04-01

    Implementation of advanced techniques in clinical practice can greatly improve the outcome of radiation therapy, but it also makes the process much more complex with a lot of room for errors. An important part of the quality assurance program is verification of treatment planning system (TPS). Dosimetric verifications in anthropomorphic phantom were performed in 4 centers where new systems were installed. A total of 14 tests for 2 photon energies and multigrid superposition algorithms were conducted using the CMS XiO TPS. Evaluation criteria as specified in the International Atomic Energy Agency Technical Reports Series (IAEA TRS) 430 were employed. Results of measurements are grouped according to the placement of the measuring point and the beam energy. The majority of differences between calculated and measured doses in the water-equivalent part of the phantom were in tolerance. Significantly more out-of-tolerance values were observed in “nonwater-equivalent” parts of the phantom, especially for higher-energy photon beams. This survey was done as a part of continuous effort to build up awareness of quality assurance/quality control (QA/QC) importance in the Croatian radiotherapy community. Understanding the limitations of different parts of the various systems used in radiation therapy can systematically improve quality as well.

  2. Microsoft Word - Ventilation System Sampling Results 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Ventilation System Sampling Results Air sampling results before and after the High Efficiency Particulate Air (HEPA) filters at WIPP are available here. Station A samples air before the filters and Station B samples air after passing through the filters. These samples were analyzed following the detection of airborne radioactivity on February 14, 2014. They are not environmental samples, and are not representative of the public or worker breathing zone air samples. They do provide assurance that

  3. Lithium Ion Electrode Production NDE and QC Considerations |...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Lithium Ion Electrode Production NDE and QC Considerations Lithium Ion Electrode Production NDE and QC Considerations Review of Oak Ridge process and QC activities by David Wood, ...

  4. EERE QC Workshop: Overview of Relevant Processes

    Office of Energy Efficiency and Renewable Energy (EERE)

    Overview of relevant QC process by Michael Ulsh, National Renewable Energy Laboratory, at the EERE QC Workshop held December 9-10, 2013, at the National Renewable Energy Laboratory in Golden, Colorado.

  5. SERI QC Solar Data Quality Assessment Software

    Energy Science and Technology Software Center (OSTI)

    1994-12-31

    SERI QC is a mathematical software package that assesses the quality of solar radiation data. The SERI QC software is a function written in the C programming language. IT IS NOT A STANDALONE SOFTWARE APPLICATION. The user must write the calling application that requires quality assessment of solar data. The C function returns data quality flags to the calling program. A companion program, QCFIT, is a standalone Windows application that provides support files for themore » SERI QC function (data quality boundaries). The QCFIT software can also be used as an analytical tool for visualizing solar data quality independent of the SERI QC function.« less

  6. Sample Results from Routine Salt Batch 7 Samples

    SciTech Connect (OSTI)

    Peters, T.

    2015-05-13

    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”) 7B have been analyzed for 238Pu, 90Sr, 137Cs, Inductively Coupled Plasma Emission Spectroscopy (ICPES), and Ion Chromatography Anions (IC-A). The results from the current microbatch samples are similar to those from earlier samples from this and previous macrobatches. The Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU) continue to show more than adequate Pu and Sr removal, and there is a distinct positive trend in Cs removal, due to the use of the Next Generation Solvent (NGS). The Savannah River National Laboratory (SRNL) notes that historically, most measured Concentration Factor (CF) values during salt processing have been in the 12-14 range. However, recent processing gives CF values closer to 11. This observation does not indicate that the solvent performance is suffering, as the Decontamination Factor (DF) has still maintained consistently high values. Nevertheless, SRNL will continue to monitor for indications of process upsets. The bulk chemistry of the DSSHT and SEHT samples do not show any signs of unusual behavior.

  7. SAMPLE RESULTS FROM MCU SOLIDS OUTAGE

    SciTech Connect (OSTI)

    Peters, T.; Washington, A.; Oji, L.; Coleman, C.; Poirier, M.

    2014-09-22

    Savannah River National Laboratory (SRNL) has received several solid and liquid samples from MCU in an effort to understand and recover from the system outage starting on April 6, 2014. SRNL concludes that the presence of solids in the Salt Solution Feed Tank (SSFT) is the likely root cause for the outage, based upon the following discoveries ? A solids sample from the extraction contactor #1 proved to be mostly sodium oxalate ? A solids sample from the scrub contactor#1 proved to be mostly sodium oxalate ? A solids sample from the Salt Solution Feed Tank (SSFT) proved to be mostly sodium oxalate ? An archived sample from Tank 49H taken last year was shown to contain a fine precipitate of sodium oxalate ? A solids sample from the extraction contactor #1 drain pipe from extraction contactor#1 proved to be mostly sodium aluminosilicate ? A liquid sample from the SSFT was shown to have elevated levels of oxalate anion compared to the expected concentration in the feed Visual inspection of the SSFT indicated the presence of precipitated or transferred solids, which were likely also in the Salt Solution Receipt Tank (SSRT). The presence of the solids coupled with agitation performed to maintain feed temperature resulted in oxalate solids migration through the MCU system and caused hydraulic issues that resulted in unplanned phase carryover from the extraction into the scrub, and ultimately the strip contactors. Not only did this carryover result in the Strip Effluent (SE) being pushed out of waste acceptance specification, but it resulted in the deposition of solids into several of the contactors. At the same time, extensive deposits of aluminosilicates were found in the drain tube in the extraction contactor #1. However it is not known at this time how the aluminosilicate solids are related to the oxalate solids. The solids were successfully cleaned out of the MCU system. However, future consideration must be given to the exclusion of oxalate solids into the MCU system

  8. Lithium Ion Electrode Production NDE and QC Considerations | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Lithium Ion Electrode Production NDE and QC Considerations Lithium Ion Electrode Production NDE and QC Considerations Review of Oak Ridge process and QC activities by David Wood, Oak Ridge National Laboratory, at the EERE QC Workshop held December 9-10, 2013, at the National Renewable Energy Laboratory in Golden, Colorado. Lithium Ion Electrode Production NDE and QC Considerations (1.1 MB) More Documents & Publications Vehicle Technologies Office Merit Review 2014: Roll-to-Roll

  9. Recent Results of the Investigation of a Microfluidic Sampling...

    Office of Scientific and Technical Information (OSTI)

    Cell Aqueous Processing Streams Citation Details In-Document Search Title: Recent Results of the Investigation of a Microfluidic Sampling Chip and Sampling System for Hot Cell ...

  10. Summary of Test Results for Daya Bay Rock Samples (Technical...

    Office of Scientific and Technical Information (OSTI)

    Summary of Test Results for Daya Bay Rock Samples Citation Details In-Document Search Title: Summary of Test Results for Daya Bay Rock Samples You are accessing a document from ...

  11. Summary of Test Results for Daya Bay Rock Samples (Technical...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Summary of Test Results for Daya Bay Rock Samples Citation Details In-Document Search Title: Summary of Test Results for Daya Bay Rock Samples A series of ...

  12. News Release: DOE Announces Riverton Water Sampling Results | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Announces Riverton Water Sampling Results News Release: DOE Announces Riverton Water Sampling Results May 11, 2012 - 3:25pm Addthis News Contact: Contractor, Judy Miller, S.M. Stoller Corporation Public Affairs (970) 248-6363 jmiller@lm.doe.gov Laboratory results indicate water from the alternative water supply system is safe for residents to drink The U.S. Department of Energy announced today that residential drinking water testing from an alternative water supply system in Riverton,

  13. DOE Releases Biological Monitoring and Sampling Results Report for the

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Amchitka, Alaska, Site | Department of Energy Biological Monitoring and Sampling Results Report for the Amchitka, Alaska, Site DOE Releases Biological Monitoring and Sampling Results Report for the Amchitka, Alaska, Site October 28, 2013 - 3:39pm Addthis Contractor, Judy Miller, S.M. Stoller Corporation Public Affairs, (970) 248-6363 jmiller@lm.doe.gov GRAND JUNCTION, Colo. - The U.S. Department of Energy today announced the availability of the Amchitka Island, Alaska, Biological Monitoring

  14. Statistical Analysis of Tank 5 Floor Sample Results

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  17. EERE QC Workshop: Overview of Quality Control Techniques

    Broader source: Energy.gov [DOE]

    Overview of quality control techniques by Michael Ulsh, National Renewable Energy Laboratory, at the EERE QC Workshop held December 9-10, 2013, at the National Renewable Energy Laboratory in Golden, Colorado.

  18. Aquifer Sampling Tube Results for Fiscal Year 2003

    SciTech Connect (OSTI)

    Hartman, Mary J.; Peterson, Robert E.

    2003-10-27

    This report presents and discusses results of the fiscal year 2003 sampling event associated with aquifer tubes along the Columbia River in the northern Hanford Site. Aquifer tube data help define the extent of groundwater contamination near the river, determine vertical variations in contamination, monitor the performance of interim remedial actions near the river, and support impact studies.

  19. Lithium Ion Electrode Production NDE and QC Considerations

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Lithium Ion Electrode Production NDE and QC Considerations David Wood, Debasish Mohanty, Jianlin Li, and Claus Daniel 12/9/13 EERE Quality Control Workshop 2 Presentation name Lithium Ion Electrode Production QC State-of-the-Art * In-Line Measurement - Conventional in-line thickness and/or areal weight by beta transmission gauge: * Thickness measurement precision of ±0.2% over 2-1000 µm * But expensive equipment (several hundred thousand dollars or more) * And ionizing radiation hazard

  20. using historical ARM measurements to systematically improve QC limits

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Historical ARM Measurements to Systematically Improve QC L Using Historical ARM Measurements to Systematically Improve QC L imits imits Sean Moore Sean Moore - - ATK Mission Research, Santa Barbara, California. Supported b ATK Mission Research, Santa Barbara, California. Supported by DOE y DOE Grant DE Grant DE- -FG02 FG02- -04ER63864 04ER63864 http://arm.atk.com/ http://arm.atk.com/ Kenneth Kehoe, Randy Peppler, Karen Sonntag Kenneth Kehoe, Randy Peppler, Karen Sonntag - - ARM Data Quality

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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).

  4. Recent Results of the Investigation of a Microfluidic Sampling...

    Office of Scientific and Technical Information (OSTI)

    Initially sampling technologies were evaluated and microfluidics sampling chip technology ... Language: English Subject: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS microfluidics; ...

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

    SciTech Connect (OSTI)

    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.

  6. ARM - Evaluation Product - AERI Data Quality Metric (AERI-QC)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ProductsAERI Data Quality Metric (AERI-QC) ARM Data Discovery Browse Data Documentation Use the Data File Inventory tool to view data availability at the file level. Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Evaluation Product : AERI Data Quality Metric (AERI-QC) Ancillary NetCDF file to be used with the regular AERI data files to document times when the data may not be correct. Data Details Contact David Turner National Oceanic and

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

    SciTech Connect (OSTI)

    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.

  8. NREL/DOE EERE QC/Metrology Workshop - EERE Fuel Cell Technologies Office

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Welcome Remarks | Department of Energy NREL/DOE EERE QC/Metrology Workshop - EERE Fuel Cell Technologies Office Welcome Remarks NREL/DOE EERE QC/Metrology Workshop - EERE Fuel Cell Technologies Office Welcome Remarks Welcome remarks from Nancy Garland, EERE Fuel Cell Technologies Office, at the EERE QC Workshop held December 9-10, 2013, at the National Renewable Energy Laboratory in Golden, Colorado. NREL/DOE EERE QC/Metrology Workshop - EERE Fuel Cell Technologies Office Welcome Remarks

  9. Retained Gas Sampling Results for the Flammable Gas Program

    SciTech Connect (OSTI)

    J.M. Bates; L.A. Mahoney; M.E. Dahl; Z.I. Antoniak

    1999-11-18

    The key phenomena of the Flammable Gas Safety Issue are generation of the gas mixture, the modes of gas retention, and the mechanisms causing release of the gas. An understanding of the mechanisms of these processes is required for final resolution of the safety issue. Central to understanding is gathering information from such sources as historical records, tank sampling data, tank process data (temperatures, ventilation rates, etc.), and laboratory evaluations conducted on tank waste samples.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  14. RESULTS OF ANALYTICAL SAMPLE CROSSCHECKS FOR NEXT GENERATION SOLVENT EXTRACTION SAMPLES ISOPAR L CONCENTRATION AND PH

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2011-09-29

    As part of the implementation process for the Next Generation Cesium Extraction Solvent (NGCS), SRNL and F/H Lab performed a series of analytical cross-checks to ensure that the components in the NGCS solvent system do not constitute an undue analytical challenge. For measurement of entrained Isopar{reg_sign} L in aqueous solutions, both labs performed similarly with results more reliable at higher concentrations (near 50 mg/L). Low bias occurred in both labs, as seen previously for comparable blind studies for the baseline solvent system. SRNL recommends consideration to use of Teflon{trademark} caps on all sample containers used for this purpose. For pH measurements, the labs showed reasonable agreement but considerable positive bias for dilute boric acid solutions. SRNL recommends consideration of using an alternate analytical method for qualification of boric acid concentrations.

  15. Results from tests of TFL Hydragard sampling loop

    SciTech Connect (OSTI)

    Steimke, J.L.

    1995-03-01

    When the Defense Waste Processing Facility (DWPF) is operational, processed radioactive sludge will be transferred in batches to the Slurry Mix Evaporator (SME), where glass frit will be added and the contents concentrated by boiling. Batches of the slurry mixture are transferred from the SME to the Melter Feed Tank (MFT). Hydragard{reg_sign} sampling systems are used on the SME and the MFT for collecting slurry samples in vials for chemical analysis. An accurate replica of the Hydragard sampling system was built and tested in the thermal Fluids Laboratory (TFL) to determine the hydragard accuracy. It was determined that the original Hydragard valve frequently drew a non-representative sample stream through the sample vial that ranged from frit enriched to frit depleted. The Hydragard valve was modified by moving the plunger and its seat backwards so that the outer surface of the plunger was flush with the inside diameter of the transfer line when the valve was open. The slurry flowing through the vial accurately represented the composition of the slurry in the reservoir for two types of slurries, different dilution factors, a range of transfer flows and a range of vial flows. It was then found that the 15 ml of slurry left in the vial when the Hydragard valve was closed, which is what will be analyzed at DWPF, had a lower ratio of frit to sludge as characterized by the lithium to iron ratio than the slurry flowing through it. The reason for these differences is not understood at this time but it is recommended that additional experimentation be performed with the TFL Hydragard loop to determine the cause.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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.

  6. Amchitka Island, Alaska, Biological Monitoring Report 2011 Sampling Results

    SciTech Connect (OSTI)

    2013-09-01

    seawater samples from the marine and terrestrial environment of Amchitka Island adjacent to the three detonation sites and at a background or reference site, Adak Island, 180 miles to the east. Consistent with the goals of the Amchitka LTS&M Plan, four data quality objectives (DQOs) were developed for the 2011 sampling event.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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).

  13. DUS II SOIL GAS SAMPLING AND AIR INJECTION TEST RESULTS (Technical...

    Office of Scientific and Technical Information (OSTI)

    DUS II SOIL GAS SAMPLING AND AIR INJECTION TEST RESULTS Citation Details In-Document Search Title: DUS II SOIL GAS SAMPLING AND AIR INJECTION TEST RESULTS Soil vapor extraction ...

  14. DUS II SOIL GAS SAMPLING AND AIR INJECTION TEST RESULTS (Technical...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: DUS II SOIL GAS SAMPLING AND AIR INJECTION TEST RESULTS Citation Details In-Document Search Title: DUS II SOIL GAS SAMPLING AND AIR INJECTION TEST RESULTS You ...

  15. The Development of QC Standards for ARM Data Products

    SciTech Connect (OSTI)

    Gaustad, Krista L.; Flynn, Connor J.; Beus, Sherman J.; Ermold, Brian D.

    2010-06-20

    While the overall object of the Atmospheric Radiation Measurement (ARM) program, to study cloud formation processes and their influence on radiative transfer, has not changed since the program’s inception in 1992 [1], the challenges associated with and the methods applied to ensure ARM data is of “known and reasonable” quality have evolved as the program has matured. This paper describes an effort initiated in 2005 to create standards to guide the creation, formatting, and assessment of QC in ARM Value-Added Products (VAPs). It includes background on the motivation and process for creating the standards, a description of the requirements defined to guide the development of the standards, the standards themselves, and tools created to verify VAP data products properly adhere to the standards.

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

    SciTech Connect (OSTI)

    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.

  17. Gasbuggy, New Mexico, Hydrologic and Natural Gas Sampling and Analysis Results for 2009

    SciTech Connect (OSTI)

    2009-11-01

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted hydrologic and natural gas sampling for the Gasbuggy, New Mexico, site on June 16, and 17, 2009. Hydrologic sampling consists of collecting water samples from water wells and surface water locations. Natural gas sampling consists of collecting both gas samples and samples of produced water from gas production wells. The water well samples were analyzed for gamma-emitting radionuclides and tritium. Surface water samples were analyzed for tritium. Water samples from gas production wells were analyzed for gamma-emitting radionuclides, gross alpha, gross beta, and tritium. Natural gas samples were analyzed for tritium and carbon-14. Water samples were analyzed by ALS Laboratory Group in Fort Collins, Colorado, and natural gas samples were analyzed by Isotech Laboratories in Champaign, Illinois. Concentrations of tritium and gamma-emitting radionuclides in water samples collected in the vicinity of the Gasbuggy site continue to demonstrate that the sample locations have not been impacted by detonation-related contaminants. Results from the sampling of natural gas from producing wells demonstrate that the gas wells nearest the Gasbuggy site are not currently impacted by detonation-related contaminants. Annual sampling of the gas production wells nearest the Gasbuggy site for gas and produced water will continue for the foreseeable future. The sampling frequency of water wells and surface water sources in the surrounding area will be reduced to once every 5 years. The next hydrologic sampling event at water wells, springs, and ponds will be in 2014.

  18. 60-Day waste compatibility safety issues and final results for AY-102 grab samples

    SciTech Connect (OSTI)

    Nuzum, J.L.

    1997-01-31

    Four grab samples (2AY-96-15, 2AY-96-16, 2AY-96-17, and 2AY-96-18) were taken from Riser 15D of Tank 241-AY-102 on October 8, 1996, and received by 222-S Laboratory on October 8, 1996. These samples were analyzed in accordance with Compatibility Grab Sampling and Analysis Plan (TSAP) and Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) in support of the Waste Compatibility Program. No notifications were required based on sample results.

  19. B Plant canyon sample TK-21-1 analytical results for the final report

    SciTech Connect (OSTI)

    Steen, F.H.

    1998-04-10

    This document is the analytical laboratory report for the TK-21-1 sample collected from the B Plant Canyon on February 18, 1998. The sample was analyzed in accordance with the Sampling and Analysis Plan for B Plant Solutions (SAP) (Simmons, 1997) in support of the B Plant decommissioning project. Samples were analyzed to provide data both to describe the material which would remain in the tanks after the B Plant transition is complete and to determine Tank Farm compatibility. The analytical results are included in the data summary table (Table 1).

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

    SciTech Connect (OSTI)

    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.

  1. SU-E-T-473: A Patient-Specific QC Paradigm Based On Trajectory Log Files and DICOM Plan Files

    SciTech Connect (OSTI)

    DeMarco, J; McCloskey, S; Low, D; Moran, J

    2014-06-01

    Purpose: To evaluate a remote QC tool for monitoring treatment machine parameters and treatment workflow. Methods: The Varian TrueBeamTM linear accelerator is a digital machine that records machine axis parameters and MLC leaf positions as a function of delivered monitor unit or control point. This information is saved to a binary trajectory log file for every treatment or imaging field in the patient treatment session. A MATLAB analysis routine was developed to parse the trajectory log files for a given patient, compare the expected versus actual machine and MLC positions as well as perform a cross-comparison with the DICOM-RT plan file exported from the treatment planning system. The parsing routine sorts the trajectory log files based on the time and date stamp and generates a sequential report file listing treatment parameters and provides a match relative to the DICOM-RT plan file. Results: The trajectory log parsing-routine was compared against a standard record and verify listing for patients undergoing initial IMRT dosimetry verification and weekly and final chart QC. The complete treatment course was independently verified for 10 patients of varying treatment site and a total of 1267 treatment fields were evaluated including pre-treatment imaging fields where applicable. In the context of IMRT plan verification, eight prostate SBRT plans with 4-arcs per plan were evaluated based on expected versus actual machine axis parameters. The average value for the maximum RMS MLC error was 0.067±0.001mm and 0.066±0.002mm for leaf bank A and B respectively. Conclusion: A real-time QC analysis program was tested using trajectory log files and DICOM-RT plan files. The parsing routine is efficient and able to evaluate all relevant machine axis parameters during a patient treatment course including MLC leaf positions and table positions at time of image acquisition and during treatment.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  5. NVO-410-11 EN-VIRONMENTAL SURVEILLANCE SAMPLING RESULTS AT THE

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1 EN-VIRONMENTAL SURVEILLANCE SAMPLING RESULTS AT THE NEVADA TEST SITE JULY, 1969 THROUGH JUNE, 1970 ENVIRONMENTAL SCIENCES D'EPARTlViENT REYNOLDS ELECTRICAL & ENGINEERING CO., INC. MERCURY, NEVADA 89023 APRIL, 1972 . .PREPARED FOR THE U. S. ATOMIC ENERGY COMMISSION NEVADA OPERATIONS OFFICE UNDER CONTRACT NO. AT(26-l)-410 ' NVO-410-11 ENVIRONMENTAL SURVEILLANCE SAMPLING REXJLTS AT THE NEVADA TEST SITE JULY 1969 THROUGH JUNE 1970 COMPILED BY: DAVID N. BRADY Reynolds 'Electrical &

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

    SciTech Connect (OSTI)

    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.

  7. 2015 Long-Term Hydrologic Monitoring Program Sampling and Analysis Results at Rio Blanco, Colorado

    SciTech Connect (OSTI)

    Findlay, Rick; Kautsky, Mark

    2015-12-01

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted annual sampling at the Rio Blanco, Colorado, Site for the Long-Term Hydrologic Monitoring Program (LTHMP) on May 20–21, 2015. This report documents the analytical results of the Rio Blanco annual monitoring event, the trip report, and the data validation package. The groundwater and surface water monitoring samples were shipped to the GEL Group Inc. laboratories for conventional analysis of tritium and analysis of gamma-emitting radionuclides by high-resolution gamma spectrometry. A subset of water samples collected from wells near the Rio Blanco site was also sent to GEL Group Inc. for enriched tritium analysis. All requested analyses were successfully completed. Samples were collected from a total of four onsite wells, including two that are privately owned. Samples were also collected from two additional private wells at nearby locations and from nine surface water locations. Samples were analyzed for gamma-emitting radionuclides by high-resolution gamma spectrometry, and they were analyzed for tritium using the conventional method with a detection limit on the order of 400 picocuries per liter (pCi/L). Four locations (one well and three surface locations) were analyzed using the enriched tritium method, which has a detection limit on the order of 3 pCi/L. The enriched locations included the well at the Brennan Windmill and surface locations at CER-1, CER-4, and Fawn Creek 500 feet upstream.

  8. Tank 241-T-111 headspace gas and vapor characterization results for samples collected in January 1995

    SciTech Connect (OSTI)

    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-U-111 headspace gas and vapor characterization results for samples collected in February 1995

    SciTech Connect (OSTI)

    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-S-111 headspace gas and vapor characterization results for samples collected in March 1995

    SciTech Connect (OSTI)

    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.

  11. Results of Remediation and Verification Sampling for the 600-270 Horseshoe Landfill

    SciTech Connect (OSTI)

    W. S. Thompson

    2005-12-14

    This report presents the results of the 2005 remedial action and verification soil sampling conducted at the 600-270 waste site after removal of soil containing residual concentrations of dichlorodiphenyl trichloroethane and its breakdown products dichlorodiphenyl dichloroethylene and dichlorodiphenyl dichloroethane. The remediation was performed in response to post-closure surface soil sampling performed between 1998 and 2003 that indicated the presence of residual DDT contamination exceeding the Record of Decision for the 1100 Area National Priorities List site cleanup criteria of 1 mg/kg that was established for the original 1994 cleanup activities.

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  15. Results of groundwater monitoring and vegetation sampling at Everest, Kansas, in 2009 .

    SciTech Connect (OSTI)

    LaFreniere, L. M.; Environmental Science Division

    2010-05-13

    In April 2008, the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) conducted groundwater sampling for the analysis of volatile organic compounds (VOCs) in the existing network of monitoring points at Everest, Kansas (Argonne 2008). The objective of the 2008 investigation was to monitor the distribution of carbon tetrachloride contamination in groundwater previously identified in CCC/USDA site characterization and groundwater sampling studies at Everest in 2000-2006 (Argonne 2001, 2003, 2006a,b). The work at Everest is being undertaken on behalf of the CCC/USDA by Argonne National Laboratory, under the oversight of the Kansas Department of Health and Environment (KDHE). The findings of the 2008 investigation were as follows: (1) Measurements of groundwater levels obtained manually and through the use of automatic recorders demonstrated a consistent pattern of groundwater flow - and inferred contaminant migration - to the north-northwest from the former CCC/USDA facility toward the Nigh property, and then west-southwest from the Nigh property toward the intermittent creek that lies west of the former CCC/USDA facility and the Nigh property. (2) The range of concentrations and the areal distribution of carbon tetrachloride identified in the groundwater at Everest in April 2008 were generally consistent with previous results. The results of the 2008 sampling (reflecting the period from 2006 to 2008) and the earlier investigations at Everest (representing the period from 2000 to 2006) show that no significant downgradient extension of the carbon tetrachloride plume occurred from 2000 to 2008. (3) The slow contaminant migration indicated by the monitoring data is qualitatively consistent with the low groundwater flow rates in the Everest aquifer unit estimated previously on the basis of site-specific hydraulic testing (Argonne 2006a,b). (4) The April 2008 and earlier sampling results demonstrate that the limits of the plume have been

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

    SciTech Connect (OSTI)

    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.

  17. Cast Stone Oxidation Front Evaluation: Preliminary Results For Samples Exposed To Moist Air

    SciTech Connect (OSTI)

    Langton, C. A.; Almond, P. M.

    2013-11-26

    The rate of oxidation is important to the long-term performance of reducing salt waste forms because the solubility of some contaminants, e.g., technetium, is a function of oxidation state. TcO{sub 4}{sup −} in the salt solution is reduced to Tc(IV) and has been shown to react with ingredients in the waste form to precipitate low solubility sulfide and/or oxide phases. Upon exposure to oxygen, the compounds containing Tc(IV) oxidize to the pertechnetate ion, Tc(VII)O{sub 4}{sup −}, which is very soluble. Consequently the rate of technetium oxidation front advancement into a monolith and the technetium leaching profile as a function of depth from an exposed surface are important to waste form performance and ground water concentration predictions. An approach for measuring contaminant oxidation rate (effective contaminant specific oxidation rate) based on leaching of select contaminants of concern is described in this report. In addition, the relationship between reduction capacity and contaminant oxidation is addressed. Chromate (Cr(VI) was used as a non-radioactive surrogate for pertechnetate, Tc(VII), in Cast Stone samples prepared with 5 M Simulant. Cast Stone spiked with pertechnetate was also prepared and tested. Depth discrete subsamples spiked with Cr were cut from Cast Stone exposed to Savannah River Site (SRS) outdoor ambient temperature fluctuations and moist air. Depth discrete subsamples spiked with Tc-99 were cut from Cast Stone exposed to laboratory ambient temperature fluctuations and moist air. Similar conditions are expected to be encountered in the Cast Stone curing container. The leachability of Cr and Tc-99 and the reduction capacities, measured by the Angus-Glasser method, were determined for each subsample as a function of depth from the exposed surface. The results obtained to date were focused on continued method development and are preliminary and apply to the sample composition and curing / exposure conditions described in this report

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

    SciTech Connect (OSTI)

    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.

  19. 2015 Long-Term Hydrologic Monitoring Program Sampling and Analysis Results Report for Project Rulison, Co

    SciTech Connect (OSTI)

    Findlay, Rick; Kautsky, Mark

    2015-12-01

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted annual sampling at the Rulison, Colorado, Site for the Long-Term Hydrologic Monitoring Program (LTHMP) on May 20–22 and 27, 2015. Several of the land owners were not available to allow access to their respective properties, which created the need for several sample collection trips. This report documents the analytical results of the Rulison monitoring event and includes the trip report and the data validation package (Appendix A). The groundwater and surface water monitoring were shipped to the GEL Group Inc. laboratories for analysis. All requested analyses were successfully completed. Samples were analyzed for gamma-emitting radionuclides by high- resolution gamma spectrometry. Tritium was analyzed using two methods, the conventional tritium method, which has a detection limit on the order of 400 picocuries per liter (pCi/L), and the enriched method (for selected samples), which has a detection limit on the order of 3 pCi/L.

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

    SciTech Connect (OSTI)

    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.

  1. Results of Self-Absorption Study on the Versapor 3000 Filters for Radioactive Particulate Air Sampling

    SciTech Connect (OSTI)

    Barnett, J. M.; Cullinan, Valerie I.; Barnett, Debra S.; Trang-Le, Truc LT; Bliss, Mary; Greenwood, Lawrence R.; Ballinger, Marcel Y.

    2009-02-17

    Since the mid-1980s, Pacific Northwest National Laboratory (PNNL) has used a value of 0.85 as the correction factor for self absorption of activity for particulate radioactive air samples collected from building exhaust for environmental monitoring. This value accounts for activity that cannot be detected by direct counting of alpha and beta particles. Emissions can be degraded or blocked by filter fibers for particles buried in the filter material or by inactive dust particles collected with the radioactive particles. These filters are used for monitoring air emissions from PNNL stacks for radioactive particles. This paper describes an effort to re-evaluate self-absorption effects in particulate radioactive air sample filters (Versapor® 3000, 47 mm diameter) used at PNNL. There were two methods used to characterize the samples. Sixty samples were selected from the archive for acid digestion to compare the radioactivity measured by direct gas-flow proportional counting of filters to the results obtained after acid digestion of the filter and counting again by gas-flow proportional detection. Thirty different sample filters were selected for visible light microscopy to evaluate filter loading and particulate characteristics. Mass-loading effects were also considered. Filter ratios were calculated by dividing the initial counts by the post-digestion counts with the expectation that post-digestion counts would be higher because digestion would expose radioactivity embedded in the filter in addition to that on top of the filter. Contrary to expectations, the post digestion readings were almost always lower than initial readings and averaged approximately half the initial readings for both alpha and beta activity. Before and after digestion readings appeared to be related to each other, but with a low coefficient of determination (R^2) value. The ratios had a wide range of values indicating that this method did not provide sufficient precision to quantify self

  2. Concordant plutonium-241-americium-241 dating of environmental samples: results from forest fire ash

    SciTech Connect (OSTI)

    Goldstein, Steven J; Oldham, Warren J; Murrell, Michael T; Katzman, Danny

    2010-12-07

    We have measured the Pu, {sup 237}Np, {sup 241}Am, and {sup 151}Sm isotopic systematics for a set of forest fire ash samples from various locations in the western U.S. including Montana, Wyoming, Idaho, and New Mexico. The goal of this study is to develop a concordant {sup 241}Pu (t{sub 1/2} = 14.4 y)-{sup 241}Am dating method for environmental collections. Environmental samples often contain mixtures of components including global fallout. There are a number of approaches for subtracting the global fallout component for such samples. One approach is to use {sup 242}/{sup 239}Pu as a normalizing isotope ratio in a three-isotope plot, where this ratio for the nonglobal fallout component can be estimated or assumed to be small. This study investigates a new, complementary method of normalization using the long-lived fission product, {sup 151}Sm (t{sub 1/2} = 90 y). We find that forest fire ash concentrates actinides and fission products with {approx}1E10 atoms {sup 239}Pu/g and {approx}1E8 atoms {sup 151}Sm/g, allowing us to measure these nuclides by mass spectrometric (MIC-TIMS) and radiometric (liquid scintillation counting) methods. The forest fire ash samples are characterized by a western U.S. regional isotopic signature representing varying mixtures of global fallout with a local component from atmospheric testing of nuclear weapons at the Nevada Test Site (NTS). Our results also show that {sup 151}Sm is well correlated with the Pu nuclides in the forest fire ash, suggesting that these nuclides have similar geochemical behavior in the environment. Results of this correlation indicate that the {sup 151}Sm/{sup 239}Pu atom ratio for global fallout is {approx}0.164, in agreement with an independent estimate of 0.165 based on {sup 137}Cs fission yields for atmospheric weapons tests at the NTS. {sup 241}Pu-{sup 241}Am dating of the non-global fallout component in the forest fire ash samples yield ages in the late 1950's-early 1960's, consistent with a peak in NTS

  3. Gasbuggy, New Mexico, Natural Gas and Produced Water Sampling and Analysis Results for 2011

    SciTech Connect (OSTI)

    2011-09-01

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted natural gas sampling for the Gasbuggy, New Mexico, site on June 7 and 8, 2011. Natural gas sampling consists of collecting both gas samples and samples of produced water from gas production wells. Water samples from gas production wells were analyzed for gamma-emitting radionuclides, gross alpha, gross beta, and tritium. Natural gas samples were analyzed for tritium and carbon-14. ALS Laboratory Group in Fort Collins, Colorado, analyzed water samples. Isotech Laboratories in Champaign, Illinois, analyzed natural gas samples.

  4. Ballistic penetration test results for Ductal and ultra-high performance concrete samples.

    SciTech Connect (OSTI)

    Reinhart, William Dodd; Thornhill, Tom Finley, III

    2010-03-01

    This document provides detailed test results of ballistic impact experiments performed on several types of high performance concrete. These tests were performed at the Sandia National Laboratories Shock Thermodynamic Applied Research Facility using a 50 caliber powder gun to study penetration resistance of concrete samples. This document provides test results for ballistic impact experiments performed on two types of concrete samples, (1) Ductal{reg_sign} concrete is a fiber reinforced high performance concrete patented by Lafarge Group and (2) ultra-high performance concrete (UHPC) produced in-house by DoD. These tests were performed as part of a research demonstration project overseen by USACE and ERDC, at the Sandia National Laboratories Shock Thermodynamic Applied Research (STAR) facility. Ballistic penetration tests were performed on a single stage research powder gun of 50 caliber bore using a full metal jacket M33 ball projectile with a nominal velocity of 914 m/s (3000 ft/s). Testing was observed by Beverly DiPaolo from ERDC-GSL. In all, 31 tests were performed to achieve the test objectives which were: (1) recovery of concrete test specimens for post mortem analysis and characterization at outside labs, (2) measurement of projectile impact velocity and post-penetration residual velocity from electronic and radiographic techniques and, (3) high-speed photography of the projectile prior to impact, impact and exit of the rear surface of the concrete construct, and (4) summarize the results.

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

    SciTech Connect (OSTI)

    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.

  6. RESULTS OF ANALYSIS OF NGS CONCENTRATE DRUM SAMPLES [Next Generation Solvent

    SciTech Connect (OSTI)

    Peters, T.; Williams, M.

    2013-09-13

    Savannah River National Laboratory (SRNL) prepared two drums (50 gallons each in ?Drum#2? and ?Drum#4?) of NGS-MCU (Next Generation Solvent-Modular CSSX Unit) concentrate for future use at MCU in downblending the BOBCalixC6 based solvent to produce NGS-MCU solvent. Samples of each drum were sent for analysis. The results of all the analyses indicate that the blend concentrate is of the correct composition and should produce a blended solvent at MCU of the desired formulation.

  7. Characterization Of Superconducting Samples With SIC System For Thin Film Developments: Status And Recent Results

    SciTech Connect (OSTI)

    Phillips, H. Lawrence; Reece, Charles E.; Valente-Feliciano, Anne-Marie; Xiao, Binping; Eremeev, Grigory V.

    2014-02-01

    Within any thin film development program directed towards SRF accelerating structures, there is a need for an RF characterization device that can provide information about RF properties of small samples. The current installation of the RF characterization device at Jefferson Lab is Surface Impedance Characterization (SIC) system. The data acquisition environment for the system has recently been improved to allow for automated measurement, and the system has been routinely used for characterization of bulk Nb, films of Nb on Cu, MgB{sub 2}, NbTiN, Nb{sub 3}Sn films, etc. We present some of the recent results that illustrate present capabilities and limitations of the system.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  12. Sample Results From The Extraction, Scrub, And Strip Test For The Blended NGS Solvent

    SciTech Connect (OSTI)

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

    2014-03-03

    This report summarizes the results of the extraction, scrub, and strip testing for the September 2013 sampling of the Next Generation Solvent (NGS) Blended solvent from the Modular Caustic Side-Solvent Extraction Unit (MCU) Solvent Hold Tank. MCU is in the process of transitioning from the BOBCalixC6 solvent to the NGS Blend solvent. As part of that transition, MCU has intentionally created a blended solvent to be processed using the Salt Batch program. This sample represents the first sample received from that blended solvent. There were two ESS tests performed where NGS blended solvent performance was assessed using either the Tank 21 material utilized in the Salt Batch 7 analyses or a simulant waste material used in the V-5/V-10 contactor testing. This report tabulates the temperature corrected cesium distribution, or DCs values, step recovery percentage, and actual temperatures recorded during the experiment. This report also identifies the sample receipt date, preparation method, and analysis performed in the accumulation of the listed values. The calculated extraction DCs values using the Tank 21H material and simulant are 59.4 and 53.8, respectively. The DCs values for two scrub and three strip processes for the Tank 21 material are 4.58, 2.91, 0.00184, 0.0252, and 0.00575, respectively. The D-values for two scrub and three strip processes for the simulant are 3.47, 2.18, 0.00468, 0.00057, and 0.00572, respectively. These values are similar to previous measurements of Salt Batch 7 feed with lab-prepared blended solvent. These numbers are considered compatible to allow simulant testing to be completed in place of actual waste due to the limited availability of feed material.

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

    SciTech Connect (OSTI)

    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

  14. The Lyman alpha reference sample. II. Hubble space telescope imaging results, integrated properties, and trends

    SciTech Connect (OSTI)

    Hayes, Matthew; Östlin, Göran; Duval, Florent; Sandberg, Andreas; Guaita, Lucia; Melinder, Jens; Rivera-Thorsen, Thøger; Adamo, Angela; Schaerer, Daniel; Verhamme, Anne; Orlitová, Ivana; Mas-Hesse, J. Miguel; Otí-Floranes, Héctor; Cannon, John M.; Pardy, Stephen; Atek, Hakim; Kunth, Daniel; Laursen, Peter; Herenz, E. Christian

    2014-02-10

    We report new results regarding the Ly? output of galaxies, derived from the Lyman Alpha Reference Sample, and focused on Hubble Space Telescope imaging. For 14 galaxies we present intensity images in Ly?, H?, and UV, and maps of H?/H?, Ly? equivalent width (EW), and Ly?/H?. We present Ly? and UV radial light profiles and show they are well-fitted by Sérsic profiles, but Ly? profiles show indices systematically lower than those of the UV (n ? 1-2 instead of ? 4). This reveals a general lack of the central concentration in Ly? that is ubiquitous in the UV. Photometric growth curves increase more slowly for Ly? than the far ultraviolet, showing that small apertures may underestimate the EW. For most galaxies, however, flux and EW curves flatten by radii ?10 kpc, suggesting that if placed at high-z only a few of our galaxies would suffer from large flux losses. We compute global properties of the sample in large apertures, and show total Ly? luminosities to be independent of all other quantities. Normalized Ly? throughput, however, shows significant correlations: escape is found to be higher in galaxies of lower star formation rate, dust content, mass, and nebular quantities that suggest harder ionizing continuum and lower metallicity. Six galaxies would be selected as high-z Ly? emitters, based upon their luminosity and EW. We discuss the results in the context of high-z Ly? and UV samples. A few galaxies have EWs above 50 Å, and one shows f{sub esc}{sup Ly?} of 80%; such objects have not previously been reported at low-z.

  15. Illumina GA IIx& HiSeq 2000 Production Sequenccing and QC Analysis Pipelines at the DOE Joint Genome Institute

    SciTech Connect (OSTI)

    Daum, Christopher; Zane, Matthew; Han, James; Kennedy, Megan; San Diego, Matthew; Copeland, Alex; Li, Mingkun; Lucas, Susan

    2011-01-31

    The U.S. Department of Energy (DOE) Joint Genome Institute's (JGI) Production Sequencing group is committed to the generation of high-quality genomic DNA sequence to support the mission areas of renewable energy generation, global carbon management, and environmental characterization and clean-up. Within the JGI's Production Sequencing group, a robust Illumina Genome Analyzer and HiSeq pipeline has been established. Optimization of the sesequencer pipelines has been ongoing with the aim of continual process improvement of the laboratory workflow, reducing operational costs and project cycle times to increases ample throughput, and improving the overall quality of the sequence generated. A sequence QC analysis pipeline has been implemented to automatically generate read and assembly level quality metrics. The foremost of these optimization projects, along with sequencing and operational strategies, throughput numbers, and sequencing quality results will be presented.

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

    SciTech Connect (OSTI)

    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.

  17. Gasbuggy, New Mexico, Hydrologic and Natural Gas Sampling and Analysis Results for 2010

    SciTech Connect (OSTI)

    None

    2010-12-01

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted natural gas sampling for the Gasbuggy, New Mexico, site on July 6 and 7, 2010. Additionally, a water sample was obtained at one well known as the 29-6 Water Hole, several miles west of the Gasbuggy site. Natural gas sampling consists of collecting both gas samples and samples of produced water from gas production wells. Water samples from gas production wells were analyzed for gamma-emitting radionuclides, gross alpha, gross beta, and tritium. Natural gas samples were analyzed for tritium and carbon-14. The one water well sample was analyzed for gamma-emitting radionuclides and tritium. ALS Laboratory Group in Fort Collins, Colorado, analyzed water samples. Isotech Laboratories in Champaign, Illinois, analyzed natural gas samples.

  18. Gasbuggy, New Mexico, Natural Gas and Produced Water Sampling Results for 2012

    SciTech Connect (OSTI)

    2012-12-01

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted annual natural gas sampling for the Gasbuggy, New Mexico, Site on June 20 and 21, 2012. This long-term monitoring of natural gas includes samples of produced water from gas production wells that are located near the site. Water samples from gas production wells were analyzed for gamma-emitting radionuclides, gross alpha, gross beta, and tritium. Natural gas samples were analyzed for tritium and carbon-14. ALS Laboratory Group in Fort Collins, Colorado, analyzed water samples. Isotech Laboratories in Champaign, Illinois, analyzed natural gas samples.

  19. Results of Stainless Steel Canister Corrosion Studies and Environmental Sample Investigations

    SciTech Connect (OSTI)

    Bryan, Charles R; Enos, David

    2014-12-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of used nuclear fuel. The work involves both characterization of the potential physical and chemical environment on the surface of the storage canisters and how it might evolve through time, and testing to evaluate performance of the canister materials under anticipated storage conditions. To evaluate the potential environment on the surface of the canisters, SNL is working with the Electric Power Research Institute (EPRI) to collect and analyze dust samples from the surface of in-service SNF storage canisters. In FY 13, SNL analyzed samples from the Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI); here, results are presented for samples collected from two additional near-marine ISFSI sites, Hope Creek NJ, and Diablo Canyon CA. The Hope Creek site is located on the shores of the Delaware River within the tidal zone; the water is brackish and wave action is normally minor. The Diablo Canyon site is located on a rocky Pacific Ocean shoreline with breaking waves. Two types of samples were collected: SaltSmart™ samples, which leach the soluble salts from a known surface area of the canister, and dry pad samples, which collected a surface salt and dust using a swipe method with a mildly abrasive ScotchBrite™ pad. The dry samples were used to characterize the mineralogy and texture of the soluble and insoluble components in the dust via microanalytical techniques, including mapping X-ray Fluorescence spectroscopy and Scanning Electron Microscopy. For both Hope Creek and Diablo Canyon canisters, dust loadings were much higher on the flat upper surfaces of the canisters than on the vertical sides. Maximum dust sizes collected at both sites were slightly larger than 20 μm, but Phragmites grass seeds ~1 mm in size, were observed on the tops of the Hope Creek canisters

  20. Quality assurance/quality control (QA/QC) procedures for hazardous-waste incineration. Handbook

    SciTech Connect (OSTI)

    Dux, T.; Gilford, P.; Bergman, F.; Boomer, B.; Hooton, D.

    1990-01-01

    The Environmental Protection Agency (EPA) has promulgated regulations for hazardous waste incinerators under the Resource Conservation and Recovery Act. These regulations require the permit applicant to conduct trial burns to demonstrate compliance with the regulatory limits and provide data needed to write the individual permits. Trial burns require a Quality Assurance Project Plan (QAPjP) with quality assurance/quality control (QA/QC) procedures to control and evaluate data quality. The primary focus of the handbook is the trial burn itself; however, a discussion of the QA/QC for routine incinerator monitoring and permit compliance is included in a separate chapter. The area has slightly different requirements and objectives from those of the trial burn. The trial burn should be viewed as a short-term project with a defined beginning and end, while compliance monitoring is considered an ongoing process.

  1. Long-Term Hydrologic Monitoring Program Sampling and Analysis Results for 2009

    SciTech Connect (OSTI)

    2010-01-21

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted annual sampling at the Rulison, Colorado, Site for the Long-Term Hydrologic Monitoring Program (LTHMP) on May 11 and 12, 2009. Samples were analyzed by the U.S. Environmental Protection Agency (EPA) Radiation&Indoor Environments National Laboratory in Las Vegas, Nevada. Samples were analyzed for gamma-emitting radionuclides by high-resolution gamma spectroscopy and for tritium using the conventional and enriched methods.

  2. Rio Blanco, Colorado, Long-Term Hydrologic Monitoring Program Sampling and Analysis Results for 2009

    SciTech Connect (OSTI)

    2009-12-21

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted annual sampling at the Rio Blanco, Colorado, Site, for the Long-Term Hydrologic Monitoring Program (LTHMP) on May 13 and 14, 2009. Samples were analyzed by the U.S. Environmental Protection Agency (EPA) Radiation&Indoor Environments National Laboratory in Las Vegas, Nevada. Samples were analyzed for gamma-emitting radionuclides by high-resolution gamma spectroscopy and tritium using the conventional and enriched methods.

  3. ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLES POURED AUGUST 29, 2012

    SciTech Connect (OSTI)

    Cozzi, A.; Best, D.; Reigel, M.

    2012-10-30

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Samples poured 8/29/12 were received on 9/20/2012 and analyzed. The average total density of each of the samples measured by the ASTM method C 642 was within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density of samples 8.6.1, 8.7.1, and 8.5.3 as measured using method ASTM E 1311 met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density of each sample met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method. The average partial hydrogen density of samples 8.5.1, 8.6.3, and 8.7.3 did not meet the lower bound. The samples, as received, were not wrapped in a moist towel as previous samples and appeared to be somewhat drier. This may explain the lower hydrogen partial density with respect to previous samples.

  4. ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLES POURED AUGUST 29, 2012

    SciTech Connect (OSTI)

    Best, D.; Cozzi, A.; Reigel, M.

    2012-12-20

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Samples poured 8/29/12 were received on 9/20/2012 and analyzed. The average total density of each of the samples measured by the ASTM method C 642 was within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density of samples 8.6.1, 8.7.1, and 8.5.3 as measured using method ASTM E 1311 met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density of each sample met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method. The average partial hydrogen density of samples 8.5.1, 8.6.3, and 8.7.3 did not meet the lower bound. The samples, as received, were not wrapped in a moist towel as previous samples and appeared to be somewhat drier. This may explain the lower hydrogen partial density with respect to previous samples.

  5. Analytical Results For MOX Colemanite Concrete Samples Received On November, 2013

    SciTech Connect (OSTI)

    Reigel, Marissa M.

    2013-12-18

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received two samples of colemanite concrete for analysis on November 21, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

  6. ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON SEPTEMBER 4, 2013

    SciTech Connect (OSTI)

    Reigel, M.

    2014-05-19

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received three samples of colemanite concrete for analysis on September 4, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

  7. ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON NOVEMBER 21, 2013

    SciTech Connect (OSTI)

    Reigel, M.

    2014-05-19

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received two samples of colemanite concrete for analysis on November 21, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

  8. Analytical Results For MOX Colemanite Concrete Samples Received On September 4, 2013

    SciTech Connect (OSTI)

    Reigel, Marissa M.

    2013-09-24

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received three samples of colemanite concrete for analysis on September 4, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

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

    SciTech Connect (OSTI)

    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.

  10. Results of Hg speciation testing on tanks 30, 32, and 37 surface samples

    SciTech Connect (OSTI)

    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.

  11. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-14-135/136 AND MCU-14-214/215/216: FEBRUARY AND MARCH 2014 MONTHLY SAMPLES

    SciTech Connect (OSTI)

    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.

  12. Characterization Results For The 2013 HTF 3H Evaporator Overhead Samples

    SciTech Connect (OSTI)

    Washington, A. L. II

    2013-12-04

    This report tabulates the radiochemical analysis of the 3H evaporator overhead sample for {sup 137}Cs, {sup 90}Sr, and {sup 129}I to meet the requirements in the Effluent Treatment Project (ETP) Waste Acceptance Criteria (WAC) (rev. 6). This report identifies the sample receipt date, preparation method, and analysis performed in the accumulation of the listed values. All data was found to be within the ETP WAC (rev. 6) specification for the Waste Water Collection Tanks (WWCT).

  13. The SAGES Legacy Unifying Globulars and Galaxies survey (SLUGGS): sample definition, methods, and initial results

    SciTech Connect (OSTI)

    Brodie, Jean P.; Romanowsky, Aaron J.; Jennings, Zachary G.; Pota, Vincenzo; Kader, Justin; Roediger, Joel C.; Villaume, Alexa; Arnold, Jacob A.; Woodley, Kristin A.; Strader, Jay; Forbes, Duncan A.; Pastorello, Nicola; Usher, Christopher; Blom, Christina; Kartha, Sreeja S.; Foster, Caroline; Spitler, Lee R.

    2014-11-20

    We introduce and provide the scientific motivation for a wide-field photometric and spectroscopic chemodynamical survey of nearby early-type galaxies (ETGs) and their globular cluster (GC) systems. The SAGES Legacy Unifying Globulars and GalaxieS (SLUGGS) survey is being carried out primarily with Subaru/Suprime-Cam and Keck/DEIMOS. The former provides deep gri imaging over a 900 arcmin{sup 2} field-of-view to characterize GC and host galaxy colors and spatial distributions, and to identify spectroscopic targets. The NIR Ca II triplet provides GC line-of-sight velocities and metallicities out to typically ?8 R {sub e}, and to ?15 R {sub e} in some cases. New techniques to extract integrated stellar kinematics and metallicities to large radii (?2-3 R {sub e}) are used in concert with GC data to create two-dimensional (2D) velocity and metallicity maps for comparison with simulations of galaxy formation. The advantages of SLUGGS compared with other, complementary, 2D-chemodynamical surveys are its superior velocity resolution, radial extent, and multiple halo tracers. We describe the sample of 25 nearby ETGs, the selection criteria for galaxies and GCs, the observing strategies, the data reduction techniques, and modeling methods. The survey observations are nearly complete and more than 30 papers have so far been published using SLUGGS data. Here we summarize some initial results, including signatures of two-phase galaxy assembly, evidence for GC metallicity bimodality, and a novel framework for the formation of extended star clusters and ultracompact dwarfs. An integrated overview of current chemodynamical constraints on GC systems points to separate, in situ formation modes at high redshifts for metal-poor and metal-rich GCs.

  14. ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON JANUARY 15, 2013

    SciTech Connect (OSTI)

    Reigel, M.; Best, D.

    2013-02-13

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received twelve samples of colemanite concrete for analysis on January 15, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1311, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the hydrogen partial density met or exceeded the specified limit. All of the samples met or exceeded the boron partial density lower bound with the exception of samples G3-M11-2000-H, G3-M11-3000-M, and G5-M1-3000-H which are below the limit of 1.65E-01 g/cm3.

  15. ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON JANUARY 15, 2013

    SciTech Connect (OSTI)

    Reigel, M.

    2014-05-19

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received twelve samples of colemanite concrete for analysis on January 15, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the hydrogen partial density met or exceeded the specified limit. All of the samples met or exceeded the boron partial density lower bound with the exception of samples G3-M11-2000-H, G3-M11-3000-M, and G5-M1-3000-H which are below the limit of 1.65E-01 g/cm{sup 3}.

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

    SciTech Connect (OSTI)

    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.

  17. THE SMALL ISOLATED GAS-RICH IRREGULAR DWARF (SIGRID) GALAXY SAMPLE: DESCRIPTION AND FIRST RESULTS

    SciTech Connect (OSTI)

    Nicholls, David C.; Dopita, Michael A.; Jerjen, Helmut; Meurer, Gerhardt R.

    2011-09-15

    Using an optically unbiased selection process based on the HIPASS neutral hydrogen survey, we have selected a sample of 83 spatially isolated, gas-rich dwarf galaxies in the southern hemisphere with cz between 350 and 1650 km s{sup -1}, and with R-band luminosities and H I masses less than that of the Small Magellanic Cloud. The sample is an important population of dwarf galaxies in the local universe, all with ongoing star formation, and most of which have no existing spectroscopic data. We are measuring the chemical abundances of these galaxies, using the integral-field spectrograph on the Australian National University 2.3 m telescope, the Wide-Field Spectrograph. This paper describes our survey criteria and procedures, lists the survey sample, and reports on initial observations.

  18. Long-Term Hydrologic Monitoring Program Sampling and Analysis Results for 2011

    SciTech Connect (OSTI)

    2011-12-21

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted annual sampling at the Rio Blanco site for the LTHMP on May 16 and 17, 2011. The samples were shipped to the U.S. Environmental Protection Agency (EPA) Radiation&Indoor Environments National Laboratory in Las Vegas, Nevada, for analysis. All requested analyses were successfully completed, with the exception of the determination of tritium concentration by the enrichment method, because the laboratory no longer provides that service. Samples were analyzed for gamma-emitting radionuclides by high-resolution gamma spectrometry and tritium using the conventional method. Starting in 2012, DOE will retain a different laboratory that provides the enriched tritium analysis service.

  19. ANALYTICAL RESULTS FOR MOX COLEMANITE SAMPLES RECEIVED ON JULY 22, 2013

    SciTech Connect (OSTI)

    Reigel, M.; Best, D.

    2014-05-19

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the boron oxide content of the colemanite raw aggregate material prior to it being mixed into the concrete. SRNL received ten samples of colemanite for analysis on July 22, 2013. The elemental boron content of each sample was measured according to ASTM C 1301. The boron oxide content was calculated using the oxide conversion factor for boron.

  20. ANALYTICAL RESULTS FOR MOX COLEMANITE SAMPLES RECEIVED ON JULY 22, 2013

    SciTech Connect (OSTI)

    Reigel, M.; Best, D.

    2013-08-13

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the boron oxide content of the colemanite raw aggregate material prior to it being mixed into the concrete. SRNL received ten samples of colemanite for analysis on July 22, 2013. The elemental boron content of each sample was measured according to ASTM C 1301. The boron oxide content was calculated using the oxide conversion factor for boron.

  1. Characterization Results for the 2014 HTF 3H & 2H Evaporator Overhead Samples

    SciTech Connect (OSTI)

    Washington, A.

    2015-05-11

    This report tabulates the radiochemical analysis of the 3H and 2H evaporator overhead samples for 137Cs, 90Sr, and 129I to meet the requirements in the Effluent Treatment Project (ETP) Waste Acceptance Criteria (WAC) (rev. 6). This report identifies the sample receipt date, preparation method, and analysis performed in the accumulation of the listed values. All data was found to be within the ETP WAC (rev. 6) specification for the Waste Water Collection Tanks (WWCT).

  2. 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 (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  4. NREL/DOE EERE QC/Metrology Workshop - EERE Fuel Cell Technologies Office Welcome Remarks

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    2/3/2014 eere.energy.gov Nancy L. Garland, Ph.D. U.S. Department of Energy Fuel Cell Technologies Office December 9-10, 2013 Energy Systems Integration Facility Golden, CO NREL/DOE EERE QC/Metrology Workshop 2 | Fuel Cell Technologies Program Source: US DOE 2/3/2014 eere.energy.gov Clean Energy Patents Reflect Emerging Growth Clean Energy Patent Growth Index [1] shows that fuel cell patents lead in the clean energy field with over 1,000 fuel cell patents issued worldwide in 2012. * Solar and

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

    SciTech Connect (OSTI)

    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.

  6. Letter Report for Analytical Results for five Swipe Samples from the Northern Biomedical Research Facility, Muskegon Michigan

    SciTech Connect (OSTI)

    Ivey, Wade

    2013-12-17

    Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute for Science and Education (ORISE) contract, received five swipe samples on December 10, 2013 from the Northern Biomedical Research Facility in Norton Shores, Michigan. The samples were analyzed for tritium and carbon-14 according to the NRC Form 303 supplied with the samples. The sample identification numbers are presented in Table 1 and the tritium and carbon-14 results are provided in Table 2. The pertinent procedure references are included with the data tables.

  7. Analytical results, statistical analyses, and sample-locality maps of rocks from the Anchorage Quadrangle, southern Alaska

    SciTech Connect (OSTI)

    Madden, D.J.; Arbogast, B.F.; O'Leary, R.M.; Van Trump, G. Jr.; Silberman, M.L.

    1989-01-01

    A U.S. Geological Survey report give the analytical results, statistical analyses, and sample-locality maps of rocks from the Anchorage Quadrangle in southern Alaska is presented.

  8. Results of Stainless Steel Canister Corrosion Studies and Environmental Sample Investigations.

    Broader source: Energy.gov [DOE]

    This report documents experimental work evaluating localized corrosion of container and canister materials performed at Sandia National Laboratories. The report also documents the results of...

  9. ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLE PBC-44.2

    SciTech Connect (OSTI)

    Best, D.; Cozzi, A.; Reigel, M.

    2012-12-20

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Sample PBC-44.2 was received on 9/20/2012 and analyzed. The average total density measured by the ASTM method C 642 was 2.03 g/cm{sup 3}, within the lower bound of 1.88 g/cm3. The average partial hydrogen density was 6.64E-02 g/cm{sup 3} as measured using method ASTM E 1311 and met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density was 1.70E-01 g/cm{sup 3} which met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method.

  10. ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLE POURED JULY 25, 2012 - CURED 28 DAYS

    SciTech Connect (OSTI)

    Cozzi, A. D.; Best, D. R.; Reigel, M. M.

    2012-09-18

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use Colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Samples 8.1.2, 8.2.2, 8.3.2, and 8.4.2 were received on 8/1/2012 and analyzed after curing for 28 days. The average total density measured by the ASTM method C 642 was 2.09 g/cm{sup 3}, within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density was 7.48E-02 g/cm{sup 3} as measured using method ASTM E 1311 and met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density was 1.71E-01 g/cm{sup 3} which met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method.

  11. Analytical Results Of MOX Colemanite Concrete Sample PBC-44.2

    SciTech Connect (OSTI)

    Cozzi, A. D.; Best, D. R.; Reigel, M. M.

    2012-10-18

    The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Sample PBC-44.2 was received on 9/20/2012 and analyzed. The average total density measured by the ASTM method C 642 was 2.03 g/cm{sup 3}, within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density was 6.64E-02 g/cm{sup 3} as measured using method ASTM E 1311 and met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density was 1.97E-01 g/cm{sup 3} which met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method.

  12. SAMPLE RESULTS FROM THE NEXT GENERATION SOLVENT PROGRAM REAL WASTE EXTRACTION-SCRUB-STRIP TESTING

    SciTech Connect (OSTI)

    Peters, T.; Washington, A.

    2013-06-03

    Savannah River National Laboratory (SRNL) performed multiple Extraction-Scrub-Strip (ESS) testing using real waste solutions, and three Next Generation Solvent (NGS) variations, which included radiologically clean pure NGS, a blend of radiologically clean NGS and radiologically clean BOBCalixC6 (NGS-MCU), and a blend of radiologically clean NGS and radiologically contaminated BOBCalixC6 from the MCU Solvent system. The results from the tests indicate that both the NGS and the NGS-MCU blend exhibit adequate extraction, scrub and strip behavior.

  13. Sample Results From The Next Generation Solvent Program Real Waste Extraction-Scrub-Strip Testing

    SciTech Connect (OSTI)

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

    2013-08-08

    Savannah River National Laboratory (SRNL) performed multiple Extraction-Scrub-Strip (ESS) testing using real waste solutions, and three Next Generation Solvent (NGS) variations, which included radiologically clean pure NGS, a blend of radiologically clean NGS and radiologically clean BOBCalixC6 (NGS-MCU), and a blend of radiologically clean NGS and radiologically contaminated BOBCalixC6 from the MCU Solvent system. The results from the tests indicate that both the NGS and the NGS-MCU blend exhibit adequate extraction, scrub and strip behavior.

  14. COMPARISON OF RESULTS FOR QUARTER 4 SURFACE WATER SPLIT SAMPLES COLLECTED AT THE NUCLEAR FUELS SERVICES SITE, ERWIN, TN

    SciTech Connect (OSTI)

    none,

    2013-08-15

    Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute for Science and Education (ORISE) contract, collected split surface water samples with Nuclear Fuel Services (NFS) representatives on June 12, 2013. Representatives from the U.S. Nuclear Regulatory Commission (NRC) and the Tennessee Department of Environment and Conservation were also in attendance. Samples were collected at four surface water stations, as required in the approved Request for Technical Assistance number 11-018. These stations included Nolichucky River upstream (NRU), Nolichucky River downstream (NRD), Martin Creek upstream (MCU), and Martin Creek downstream (MCD). Both ORAU and NFS performed gross alpha and gross beta analyses, and Table 1 presents the comparison of results using the duplicate error ratio (DER), also known as the normalized absolute difference. A DER ≤ 3 indicates at a 99% confidence interval that split sample results do not differ significantly when compared to their respective one standard deviation (sigma) uncertainty (ANSI N42.22). The NFS split sample report specifies 95% confidence level of reported uncertainties (NFS 2013). Therefore, standard two sigma reporting values were divided by 1.96. In conclusion, most DER values were less than 3 and results are consistent with low (e.g., background) concentrations. The gross beta result for sample 5198W0014 was the exception. The ORAU gross beta result of 6.30 ± 0.65 pCi/L from location NRD is well above NFS's non-detected result of 1.56 ± 0.59 pCi/L. NFS's data package includes no detected result for any radionuclide at location NRD. At NRC's request, ORAU performed gamma spectroscopic analysis of sample 5198W0014 to identify analytes contributing to the relatively elevated gross beta results. This analysis identified detected amounts of naturally-occurring constituents, most notably Ac-228 from the thorium decay series, and does not suggest the presence of site-related contamination.

  15. Results of the Excreta Bioassay Quality Control Program for April 1, 2009 through March 31, 2010

    SciTech Connect (OSTI)

    Antonio, Cheryl L.

    2012-07-19

    A total of 58 urine samples and 10 fecal samples were submitted during the report period (April 1, 2009 through March 31, 2010) to General Engineering Laboratories, South Carolina by the Hanford Internal Dosimetry Program (IDP) to check the accuracy, precision, and detection levels of their analyses. Urine analyses for Sr, 238Pu, 239Pu, 241Am, 243Am 235U, 238U, elemental uranium and fecal analyses for 241Am, 238Pu and 239Pu were tested this year as well as four tissue samples for 238Pu, 239Pu, 241Am and 241Pu. The number of QC urine samples submitted during the report period represented 1.3% of the total samples submitted. In addition to the samples provided by IDP, GEL was also required to conduct their own QC program, and submit the results of analyses to IDP. About 33% of the analyses processed by GEL during the third year of this contract were quality control samples. GEL tested the performance of 21 radioisotopes, all of which met or exceeded the specifications in the Statement of Work within statistical uncertainty (Table 4).

  16. Solar Deployment System (SolarDS) Model: Documentation and Sample Results

    SciTech Connect (OSTI)

    Denholm, P.; Drury, E.; Margolis, R.

    2009-09-01

    The Solar Deployment System (SolarDS) model is a bottom-up, market penetration model that simulates the potential adoption of photovoltaics (PV) on residential and commercial rooftops in the continental United States through 2030. NREL developed SolarDS to examine the market competitiveness of PV based on regional solar resources, capital costs, electricity prices, utility rate structures, and federal and local incentives. The model uses the projected financial performance of PV systems to simulate PV adoption for building types and regions then aggregates adoption to state and national levels. The main components of SolarDS include a PV performance simulator, a PV annual revenue calculator, a PV financial performance calculator, a PV market share calculator, and a regional aggregator. The model simulates a variety of installed PV capacity for a range of user-specified input parameters. PV market penetration levels from 15 to 193 GW by 2030 were simulated in preliminary model runs. SolarDS results are primarily driven by three model assumptions: (1) future PV cost reductions, (2) the maximum PV market share assumed for systems with given financial performance, and (3) PV financing parameters and policy-driven assumptions, such as the possible future cost of carbon emissions.

  17. Vapor space characterization of waste tank 241-C-106: Results from samples collected on February 15, 1994

    SciTech Connect (OSTI)

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

    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-C-106. 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.

  18. PCB Analysis Plan for Tank Archive Samples

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  20. COMPARISON OF RESULTS FOR QUARTER 3 SURFACE WATER SPLIT SAMPLES COLLECTED AT THE NUCLEAR FUEL SERVICES SITE, ERWIN, TENNESSEE

    SciTech Connect (OSTI)

    none,

    2013-05-28

    Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute for Science and Education (ORISE) contract, collected split surface water samples with Nuclear Fuel Services (NFS) representatives on March 20, 2013. Representatives from the U.S. Nuclear Regulatory Commission and the Tennessee Department of Environment and Conservation were also in attendance. Samples were collected at four surface water stations, as required in the approved Request for Technical Assistance number 11-018. These stations included Nolichucky River upstream (NRU), Nolichucky River downstream (NRD), Martin Creek upstream (MCU), and Martin Creek downstream (MCD). Both ORAU and NFS performed gross alpha and gross beta analyses, and Table 1 presents the comparison of results using the duplicate error ratio (DER), also known as the normalized absolute difference. A DER {<=} 3 indicates that at a 99% confidence interval, split sample results do not differ significantly when compared to their respective one standard deviation (sigma) uncertainty (ANSI N42.22). The NFS split sample report does not specify the confidence level of reported uncertainties (NFS 2013). Therefore, standard two sigma reporting is assumed and uncertainty values were divided by 1.96. In conclusion, most DER values were less than 3 and results are consistent with low (e.g., background) concentrations. The gross beta result for sample 5198W0012 was the exception. The ORAU result of 9.23 ± 0.73 pCi/L from location MCD is well above NFS's result of -0.567 ± 0.63 pCi/L (non-detected). NFS's data package included a detected result for U-233/234, but no other uranium or plutonium detection, and nothing that would suggest the presence of beta-emitting radionuclides. The ORAU laboratory reanalyzed sample 5198W0012 using the remaining portion of the sample volume and a result of 11.3 ± 1.1 pCi/L was determined. As directed, the laboratory also counted the filtrate using gamma spectrometry analysis and

  1. Tank 241-BY-106 headspace gas and vapor characterization results for samples collected in May 1994 and July 1994

    SciTech Connect (OSTI)

    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-BY-111 headspace gas and vapor characterization results for samples collected in May 1994 and November 1994

    SciTech Connect (OSTI)

    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

  3. Tank 241-C-111 headspace gas and vapor characterization results for samples collected in August 1993 and September 1994

    SciTech Connect (OSTI)

    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. Results of The Excreta Bioassay Quality Control Program For April 1, 2010 Through March 31, 2011

    SciTech Connect (OSTI)

    Antonio, Cheryl L.

    2012-07-19

    A total of 76 urine samples and 10 spiked fecal samples were submitted during the report period (April 1, 2010 through March 31, 2011) to GEL Laboratories, LLC in South Carolina by the Hanford Internal Dosimetry Program (IDP) to check the accuracy, precision, and detection levels of their analyses. Urine analyses for 14C, Sr, for 238Pu, 239Pu, 241Am, 243Am, 235U, 238U, 238U-mass and fecal analyses for 241Am, 238Pu and 239Pu were tested this year. The number of QC urine samples submitted during the report period represented 1.1% of the total samples submitted. In addition to the samples provided by IDP, GEL was also required to conduct their own QC program, and submit the results of analyses to IDP. About 31% of the analyses processed by GEL during the first year of contract 112512 were quality control samples. GEL tested the performance of 23 radioisotopes, all of which met or exceeded the specifications in the Statement of Work within statistical uncertainty except the slightly elevated relative bias for 243,244Cm (Table 4).

  5. COMPARISON OF RESULTS FOR QUARTER 2 SURFACE WATER SPLIT SAMPLES COLLECTED AT THE NUCLEAR FUEL SERVICES SITE, ERWIN, TENNESSEE

    SciTech Connect (OSTI)

    2013-01-21

    Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute for Science and Education (ORISE) contract, collected split surface water samples with Nuclear Fuel Services (NFS) representatives on November 15, 2012. Representatives from the U.S. Nuclear Regulatory Commission and Tennessee Department of Environment and Conservation were also in attendance. Samples were collected at four surface water stations, as required in the approved Request for Technical Assistance number 11-018. These stations included Nolichucky River upstream (NRU), Nolichucky River downstream (NRD), Martin Creek upstream (MCU), and Martin Creek downstream (MCD). Both ORAU and NFS performed gross alpha and gross beta analyses, and the results are compared using the duplicate error ratio (DER), also known as the normalized absolute difference. A DER {<=} 3 indicates that, at a 99% confidence interval, split sample results do not differ significantly when compared to their respective one standard deviation (sigma) uncertainty (ANSI N42.22). The NFS split sample report does not specify the confidence level of reported uncertainties (NFS 2012). Therefore, standard two sigma reporting is assumed and uncertainty values were divided by 1.96. In conclusion, all DER values were less than 3 and results are consistent with low (e.g., background) concentrations.

  6. COMPARISON OF RESULTS FOR QUARTER 5 SURFACE WATER SPLIT SAMPLES COLLECTED AT THE NUCLEAR FUEL SERVICES SITE ERWIN TENNESSEE

    SciTech Connect (OSTI)

    2013-09-23

    Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute for Science and Education (ORISE) contract, collected split surface water samples with Nuclear Fuel Services (NFS) representatives on August 21, 2013. Representatives from the U.S. Nuclear Regulatory Commission (NRC) and the Tennessee Department of Environment and Conservation were also in attendance. Samples were collected at four surface water stations, as required in the approved Request for Technical Assistance number 11-018. These stations included Nolichucky River upstream (NRU), Nolichucky River downstream (NRD), Martin Creek upstream (MCU), and Martin Creek downstream (MCD). Both ORAU and NFS performed gross alpha and gross beta analyses, and the comparison of results using the duplicate error ratio (DER), also known as the normalized absolute difference, are tabulated. All DER values were less than 3 and results are consistent with low (e.g., background) concentrations.

  7. Non destructive multi elemental analysis using prompt gamma neutron activation analysis techniques: Preliminary results for concrete sample

    SciTech Connect (OSTI)

    Dahing, Lahasen Normanshah; Yahya, Redzuan; Yahya, Roslan; Hassan, Hearie

    2014-09-03

    In this study, principle of prompt gamma neutron activation analysis has been used as a technique to determine the elements in the sample. The system consists of collimated isotopic neutron source, Cf-252 with HPGe detector and Multichannel Analysis (MCA). Concrete with size of 10×10×10 cm{sup 3} and 15×15×15 cm{sup 3} were analysed as sample. When neutrons enter and interact with elements in the concrete, the neutron capture reaction will occur and produce characteristic prompt gamma ray of the elements. The preliminary result of this study demonstrate the major element in the concrete was determined such as Si, Mg, Ca, Al, Fe and H as well as others element, such as Cl by analysis the gamma ray lines respectively. The results obtained were compared with NAA and XRF techniques as a part of reference and validation. The potential and the capability of neutron induced prompt gamma as tool for multi elemental analysis qualitatively to identify the elements present in the concrete sample discussed.

  8. SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-14-667-672 AND MCU-14-846-847: AUGUST AND SEPTEMBER 2014 MONTHLY SAMPLES

    SciTech Connect (OSTI)

    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.

  9. Solvent Hold Tank Sample Results for MCU-15-389-390 and MCU-15-439-440-441. February 2015 Monthly Samples

    SciTech Connect (OSTI)

    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. Tank 241-AP-103 08/1999 Compatibility Grab Samples and Analytical Results for the Final Report

    SciTech Connect (OSTI)

    BELL, K.E.

    1999-12-09

    This document is the format IV, final report for the tank 241-AP-103 (AP-103) grab samples taken in August 1999 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank AP-103 samples were performed as directed in ''Compatibility Grub Sampling and Analysis Plan for Fiscal Year 1999'' (Sasaki 1999a). Any deviations from the instructions provided in the tank sampling and analysis plan (TSAP) were discussed in this narrative. No notification limits were exceeded.

  11. Letter Report for Analytical Results for Two Soil Samples Associated with the Westinghouse Hematite Decommisioning Project in Hematite Missouri

    SciTech Connect (OSTI)

    Ivey, Wade

    2013-10-30

    Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute for Science and Education (ORISE) contract, received two soil samples on September 26, 2013 from the Westinghouse Hetnatite Decomminsioning project in Hematite, Missouri. The samples were analyzed for thorium-232, radium-226, uranium-235, and uranium-238 by gamma spectrometry and technetium-99 by liquid scintillation analysis. The samples were received in good condition. The sample collection data and identification numbers are tabulated. Also presented are the gamma spectrometry and technetium-99 data, respectively. The pertinent procedure references are included with the data tables.

  12. Results for the Independent Sampling and Analysis of Used Oil Drums at the Impact Services Facility in Oak Ridge, TN

    SciTech Connect (OSTI)

    2013-04-25

    The U.S. Department of Energy (DOE) requested that Oak Ridge Associated Universities (ORAU), via the Oak Ridge Institute for Science and Education (ORISE) contract, perform independent sampling and analysis of used oils contained within eight 55 gallon drums stored at the former IMPACT Services facility, located at the East Tennessee Technology Park in Oak Ridge, Tennessee. These drums were originally delivered by LATA Sharp Remediation Services (LSRS) to IMPACT Services on January 11, 2011 as part of the Bldg. K-33 demolition project, and the drums plus contents should have been processed as non-hazardous non-radiological waste by IMPACT Services. LSRS received a certificate of destruction on August 29, 2012 (LSRS 2012a). However, IMPACT Services declared bankruptcy and abandoned the site later in 2012, and eight of the original eleven K-33 drums are currently stored at the facility. The content of these drums is the subject of this investigation. The original drum contents were sampled by LSRS in 2010 and analyzed for gross alpha, gross beta, and polychlorinated biphenyls (PCBs), using both compositing and grab sampling techniques. The objective of this 2013 sample and analysis effort was to duplicate, to the extent possible, the 2010 sampling and analysis event to support final disposition decisions. Part of that decision process includes either verifying or refuting the assertion that oils that are currently stored in drums at the IMPACT Services facility originated from Bldg. K-33 equipment.

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

    SciTech Connect (OSTI)

    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.

  14. 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 (OSTI)

    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).

  15. HUBBLE SPACE TELESCOPE PROPER MOTION (HSTPROMO) CATALOGS OF GALACTIC GLOBULAR CLUSTERS. I. SAMPLE SELECTION, DATA REDUCTION, AND NGC 7078 RESULTS

    SciTech Connect (OSTI)

    Bellini, A.; Anderson, J.; Van der Marel, R. P.; Watkins, L. L.; King, I. R.; Bianchini, P.; Chanamé, J.; Chandar, R.; Cool, A. M.; Ferraro, F. R.; Massari, D.; Ford, H.

    2014-12-20

    We present the first study of high-precision internal proper motions (PMs) in a large sample of globular clusters, based on Hubble Space Telescope (HST) data obtained over the past decade with the ACS/WFC, ACS/HRC, and WFC3/UVIS instruments. We determine PMs for over 1.3 million stars in the central regions of 22 clusters, with a median number of ?60,000 stars per cluster. These PMs have the potential to significantly advance our understanding of the internal kinematics of globular clusters by extending past line-of-sight (LOS) velocity measurements to two- or three-dimensional velocities, lower stellar masses, and larger sample sizes. We describe the reduction pipeline that we developed to derive homogeneous PMs from the very heterogeneous archival data. We demonstrate the quality of the measurements through extensive Monte Carlo simulations. We also discuss the PM errors introduced by various systematic effects and the techniques that we have developed to correct or remove them to the extent possible. We provide in electronic form the catalog for NGC 7078 (M 15), which consists of 77,837 stars in the central 2.'4. We validate the catalog by comparison with existing PM measurements and LOS velocities and use it to study the dependence of the velocity dispersion on radius, stellar magnitude (or mass) along the main sequence, and direction in the plane of the sky (radial or tangential). Subsequent papers in this series will explore a range of applications in globular-cluster science and will also present the PM catalogs for the other sample clusters.

  16. Tank 241-AP-107, grab samples, 7AP-99-1, 7AP-99-3 and 7AP-99-4 analytical results for the final report

    SciTech Connect (OSTI)

    BELL, K.E.

    1999-08-12

    This document is the format IV, final report for the tank 241-AP-107 (AP-107) grab samples taken in May 1999 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank AP-107 samples were performed as directed in Compatibility Grab Sampling and Analysis Plan for Fiscal year 1999. Any deviations from the instructions provided in the tank sampling and analysis plan (TSAP) were discussed in this narrative. Interim data were provided earlier to River Protection Project (RPP) personnel, however, the data presented here represent the official results. No notification limits were exceeded.

  17. 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 (OSTI)

    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.

  18. 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 (OSTI)

    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.

  19. 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 (OSTI)

    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.

  20. 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 (OSTI)

    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

  1. Results of Inspection and Cleaning of Two Radionuclide Air-Sampling Systems Based on the Requirements of ANSI/HPS N13.1-1999

    SciTech Connect (OSTI)

    Barnett, J M.; Ballinger, Marcel Y.; Gervais, Todd L.; Douglas, David D.; Edwards, Daniel L.

    2004-04-01

    The Pacific Northwest National Laboratory (PNNL) conducted inspection and cleaning activities at two radionuclide air-sampling systems that continuously monitor radioactive air emissions from research and development (R&D) facilities. The inspection and cleaning was performed to evaluate effective methods and potential cost impacts of maintenance requirements in the revised American National Standard Institute (ANSI) standard Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities (ANSI/HPS N13.1-1999). The standard requires at least annual inspections of sampling systems followed by cleaning if deposits are visible. During 2001 and 2002, inspections were performed leaving the sampling systems in place and inserting videoscope cables into different access points to allow viewing of the inside and outside of sampling manifolds and transport lines. Cleaning was performed on one of the systems by disconnecting and extracting the sampling manifold, then washing it with de-ionized water and scrub brushes. The wash water was analyzed for radioactivity and solids. Results of the inspection showed greater deposition in one of the systems than would be expected by a High Efficiency Particulate Air (HEPA) filtered exhaust stream; the second system was also downstream of HEPA filters and appeared much cleaner. The videoscope was a useful and cost-effective tool and provided a better view than could be obtained with the naked eye. However, because even small amounts of deposition were made visible with the videoscope, clarification is needed in defining when probe washing is merited, particularly in existing sampling systems whose design is not conducive to easy removal and cleaning.

  2. A study of toxic emissions from a coal-fired power plant utilizing an ESP/Wet FGD system. Volume 1, Sampling, results, and special topics: Final report

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    This was one of a group of assessments of toxic emissions from coal-fired power plants, conducted for DOE-PETC in 1993 as mandated by the 1990 Clean Air Act. It is organized into 2 volumes; Volume 1 describes the sampling effort, presents the concentration data on toxic chemicals in several power plant streams, and reports the results of evaluations and calculations. The study involved solid, liquid, and gaseous samples from input, output, and process streams at Coal Creek Station Unit No. 1, Underwood, North Dakota (1100 MW mine-mouth plant burning lignite from the Falkirk mine located adjacent to the plant). This plant had an electrostatic precipitator and a wet scrubber flue gas desulfurization unit. Measurements were conducted on June 21--24, 26, and 27, 1993; chemicals measured were 6 major and 16 trace elements (including Hg, Cr, Cd, Pb, Se, As, Be, Ni), acids and corresponding anions (HCl, HF, chloride, fluoride, phosphate, sulfate), ammonia and cyanide, elemental C, radionuclides, VOCs, semivolatiles (incl. PAH, polychlorinated dioxins, furans), and aldehydes. Volume 2: Appendices includes process data log sheets, field sampling data sheets, uncertainty calculations, and quality assurance results.

  3. Results of sediment and water sampling for inorganic, organic, and radionuclide analysis at recreation areas and water intakes -- Norris, Melton Hill, and Watts Bar Lakes. Data report

    SciTech Connect (OSTI)

    1991-10-01

    Suspected water quality contamination in Watts Bar Reservoir as a result of activities in past decades at the Department of Energy`s (DOE) Oak Ridge facility is of public concern. DOE, the Tennessee Valley Authority (TVA), the State of Tennessee, and other agencies and officials have received many inquiries from the public in recent years concerning this suspected pollution, especially how this potential contamination may affect the health and safety of those persons who use beaches in the area for swimming or other water-body-contact sports. As a result of these concerns, TVA conducted a study in May and June 1991 to obtain data on potential contaminants of concern in the water and sediment of Watts Bar Reservoir. TVA collected water and sediment samples at a total of 29 sites, including 18 recreation areas and 11 water intake locations, located throughout Norris, Melton Hill, and Watts Bar Reservoirs. The samples were analyzed for radionuclides, metals, and organic compounds which could pose a threat to human health.

  4. Letter Report for Analytical Results for Two Concrete and Three Soil Samples Associated with the Worcester Polytechnic Institute in Worcester Massachusetts

    SciTech Connect (OSTI)

    Ivey, Wade

    2013-10-07

    Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute tor Science and Education (ORISE) contract, received two concrete core and three soil samples on August 26, 2013 from the Worcester Polytechnic Institute in Worcester, Massachusetts. The samples were received in good condition. The samples were analyzed tor activation and fission products by gamma spectrometry. The sample collection data and identification numbers are tabulated and the gamma spectrometry data are presented. The pertinent procedure reference is included with the data table.

  5. SAMPLING OSCILLOSCOPE

    DOE Patents [OSTI]

    Sugarman, R.M.

    1960-08-30

    An oscilloscope is designed for displaying transient signal waveforms having random time and amplitude distributions. The oscilloscopc is a sampling device that selects for display a portion of only those waveforms having a particular range of amplitudes. For this purpose a pulse-height analyzer is provided to screen the pulses. A variable voltage-level shifter and a time-scale rampvoltage generator take the pulse height relative to the start of the waveform. The variable voltage shifter produces a voltage level raised one step for each sequential signal waveform to be sampled and this results in an unsmeared record of input signal waveforms. Appropriate delay devices permit each sample waveform to pass its peak amplitude before the circuit selects it for display.

  6. 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 (OSTI)

    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.

  7. Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee. Volume 1: Results of Field Sampling Program

    SciTech Connect (OSTI)

    Watkins, D.R.; Ammons, J.T.; Branson, J.L.

    1993-10-01

    This report presents, evaluates, and documents data and results obtained in the Background Soil Characterization Project (BSCP). It is intended to be a stand-alone document for application and use in structuring and conducting remedial investigation and remedial action projects in the Environmental Restoration (ER) Program. The objectives of the BSCP consist of the following: determine background concentrations of organics, metals, and radionuclides in natural soils that are key to environmental restoration projects; provide remediation projects with 100% validated data on background concentrations, which are technically and legally defensible; and quantify baseline risks from background constituents for comparison of risks associated with contaminated sites.

  8. 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 (OSTI)

    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.

  9. Experimental and Sampling Design for the INL-2 Sample Collection Operational Test

    SciTech Connect (OSTI)

    Piepel, Gregory F.; Amidan, Brett G.; Matzke, Brett D.

    2009-02-16

    , sample extraction, and analytical methods to be used in the INL-2 study. For each of the five test events, the specified floor of the INL building will be contaminated with BG using a point-release device located in the room specified in the experimental design. Then quality control (QC), reference material coupon (RMC), judgmental, and probabilistic samples will be collected according to the sampling plan for each test event. Judgmental samples will be selected based on professional judgment and prior information. Probabilistic samples were selected with a random aspect and in sufficient numbers to provide desired confidence for detecting contamination or clearing uncontaminated (or decontaminated) areas. Following sample collection for a given test event, the INL building will be decontaminated. For possibly contaminated areas, the numbers of probabilistic samples were chosen to provide 95% confidence of detecting contaminated areas of specified sizes. For rooms that may be uncontaminated following a contamination event, or for whole floors after decontamination, the numbers of judgmental and probabilistic samples were chosen using the CJR approach. The numbers of samples were chosen to support making X%/Y% clearance statements with X = 95% or 99% and Y = 96% or 97%. The experimental and sampling design also provides for making X%/Y% clearance statements using only probabilistic samples. For each test event, the numbers of characterization and clearance samples were selected within limits based on operational considerations while still maintaining high confidence for detection and clearance aspects. The sampling design for all five test events contains 2085 samples, with 1142 after contamination and 943 after decontamination. These numbers include QC, RMC, judgmental, and probabilistic samples. The experimental and sampling design specified in this report provides a good statistical foundation for achieving the objectives of the INL-2 study.

  10. 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 (OSTI)

    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).

  11. Protections: Sampling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Protections: Sampling Protections: Sampling Protection #3: Sampling for known and unexpected contaminants August 1, 2013 Monitoring stormwater in Los Alamos Canyon Monitoring stormwater in Los Alamos Canyon The Environmental Sampling Board, a key piece of the Strategy, ensures that LANL collects relevant and appropriate data to answer questions about the protection of human and environmental health, and to satisfy regulatory requirements. LANL must demonstrate the data are technically justified

  12. A study of toxic emissions from a coal-fired power plant utilizing the SNOX innovative clean coal technology demonstration. Volume 1, Sampling/results/special topics: Final report

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    This study was one of a group of assessments of toxic emissions from coal-fired power plants, conducted for DOE during 1993. The motivation for those assessments was the mandate in the 1990 Clean Air Act Amendments that a study be made of emissions of hazardous air pollutants (HAPs) from electric utilities. The report is organized in two volumes. Volume 1: Sampling describes the sampling effort conducted as the basis for this study; Results presents the concentration data on HAPs in the several power plant streams, and reports the results of evaluations and calculations conducted with those data; and Special Topics report on issues such as comparison of sampling methods and vapor/solid distributions of HAPs. Volume 2: Appendices include quality assurance/quality control results, uncertainty analysis for emission factors, and data sheets. This study involved measurements of a variety of substances in solid, liquid, and gaseous samples from input, output, and process streams at the Innovative Clean Coal Technology Demonstration (ICCT) of the Wet Sulfuric Acid-Selective Catalytic Reduction (SNOX) process. The SNOX demonstration is being conducted at Ohio Edison`s Niles Boiler No. 2 which uses cyclone burners to burn bituminous coal. A 35 megawatt slipstream of flue gas from the boiler is used to demonstrate SNOX. The substances measured at the SNOX process were the following: 1. Five major and 16 trace elements, including mercury, chromium, cadmium, lead, selenium, arsenic, beryllium, and nickel; 2. Acids and corresponding anions (HCl, HF, chloride, fluoride, phosphate, sulfate); 3. Ammonia and cyanide; 4. Elemental carbon; 5. Radionuclides; 6. Volatile organic compounds (VOC); 7. Semi-volatile compounds (SVOC) including polynuclear aromatic hydrocarbons (PAH); and 8. Aldehydes.

  13. Protections: Sampling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Protection 3: Sampling for known and unexpected contaminants August 1, 2013 Monitoring stormwater in Los Alamos Canyon Monitoring stormwater in Los Alamos Canyon The Environmental ...

  14. Protections: Sampling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and unexpected contaminants August 1, 2013 Monitoring stormwater in Los Alamos Canyon Monitoring stormwater in Los Alamos Canyon The Environmental Sampling Board, a key piece...

  15. September 2004 Water Sampling

    Office of Legacy Management (LM)

    ... 100, 17B, 1A, 72, and 81 were classified as Category II. The sample results were qualified with a "Q" flag, indicating the data are qualitative because of the sampling technique. ...

  16. Water and Sediment Sampling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    MDC Blank 7222014 Below MDC Below MDC Water Sampling Results Location Sample Date WIPP ... Tut Tank 3132014 Below MDC Below MDC Fresh Water Tank 3122014 Below MDC Below MDC Hill ...

  17. SAMPLING SYSTEM

    DOE Patents [OSTI]

    Hannaford, B.A.; Rosenberg, R.; Segaser, C.L.; Terry, C.L.

    1961-01-17

    An apparatus is given for the batch sampling of radioactive liquids such as slurries from a system by remote control, while providing shielding for protection of operating personnel from the harmful effects of radiation.

  18. Sampling box

    DOE Patents [OSTI]

    Phillips, Terrance D.; Johnson, Craig

    2000-01-01

    An air sampling box that uses a slidable filter tray and a removable filter cartridge to allow for the easy replacement of a filter which catches radioactive particles is disclosed.

  19. Assuring the Quality of Test Results in the Field of Nuclear Techniques and Ionizing Radiation. The Practical Implementation of Section 5.9 of the EN ISO/IEC 17025 Standard

    SciTech Connect (OSTI)

    Cucu, Daniela; Woods, Mike

    2008-08-14

    The paper aims to present a practical approach for testing laboratories to ensure the quality of their test results. It is based on the experience gained in assessing a large number of testing laboratories, discussing with management and staff, reviewing results obtained in national and international PTs and ILCs and exchanging information in the EA laboratory committee.According to EN ISO/IEC 17025, an accredited laboratory has to implement a programme to ensure the quality of its test results for each measurand. Pre-analytical, analytical and post-analytical measures shall be applied in a systematic manner. They shall include both quality control and quality assurance measures.When designing the quality assurance programme a laboratory should consider pre-analytical activities (like personnel training, selection and validation of test methods, qualifying equipment), analytical activities ranging from sampling, sample preparation, instrumental analysis and post-analytical activities (like decoding, calculation, use of statistical tests or packages, management of results).Designed on different levels (analyst, quality manager and technical manager), including a variety of measures, the programme shall ensure the validity and accuracy of test results, the adequacy of the management system, prove the laboratory's competence in performing tests under accreditation and last but not least show the comparability of test results.Laboratory management should establish performance targets and review periodically QC/QA results against them, implementing appropriate measures in case of non-compliance.

  20. September 2004 Water Sampling

    Office of Legacy Management (LM)

    ... The gross alpha, gross beta, radium-226, and radium-228 method blank results were below the DLC. Inductively Coupled Plasma (ICP) Interference Check Sample (ICS) Analysis ICP ...

  1. Nuclear Energy Research Initiative Project No. 02 103 Innovative Low Cost Approaches to Automating QA/QC of Fuel Particle Production Using On Line Nondestructive Methods for Higher Reliability Final Project Report

    SciTech Connect (OSTI)

    Ahmed, Salahuddin; Batishko, Charles R.; Flake, Matthew; Good, Morris S.; Mathews, Royce; Morra, Marino; Panetta, Paul D.; Pardini, Allan F.; Sandness, Gerald A.; Tucker, Brian J.; Weier, Dennis R.; Hockey, Ronald L.; Gray, Joseph N.; Saurwein, John J.; Bond, Leonard J.; Lowden, Richard A.; Miller, James H.

    2006-02-28

    This Nuclear Energy Research Initiative (NERI) project was tasked with exploring, adapting, developing and demonstrating innovative nondestructive test methods to automate nuclear coated particle fuel inspection so as to provide the United States (US) with necessary improved and economical Quality Assurance and Control (QA/QC) that is needed for the fuels for several reactor concepts being proposed for both near term deployment [DOE NE & NERAC, 2001] and Generation IV nuclear systems. Replacing present day QA/QC methods, done manually and in many cases destructively, with higher speed automated nondestructive methods will make fuel production for advanced reactors economically feasible. For successful deployment of next generation reactors that employ particle fuels, or fuels in the form of pebbles based on particles, extremely large numbers of fuel particles will require inspection at throughput rates that do not significantly impact the proposed manufacturing processes. The focus of the project is nondestructive examination (NDE) technologies that can be automated for production speeds and make either: (I) On Process Measurements or (II) In Line Measurements. The inspection technologies selected will enable particle “quality” qualification as a particle or group of particles passes a sensor. A multiple attribute dependent signature will be measured and used for qualification or process control decisions. A primary task for achieving this objective is to establish standard signatures for both good/acceptable particles and the most problematic types of defects using several nondestructive methods.

  2. Sampling apparatus

    DOE Patents [OSTI]

    Gordon, Norman R.; King, Lloyd L.; Jackson, Peter O.; Zulich, Alan W.

    1989-01-01

    A sampling apparatus is provided for sampling substances from solid surfaces. The apparatus includes first and second elongated tubular bodies which telescopically and sealingly join relative to one another. An absorbent pad is mounted to the end of a rod which is slidably received through a passageway in the end of one of the joined bodies. The rod is preferably slidably and rotatably received through the passageway, yet provides a selective fluid tight seal relative thereto. A recess is formed in the rod. When the recess and passageway are positioned to be coincident, fluid is permitted to flow through the passageway and around the rod. The pad is preferably laterally orientable relative to the rod and foldably retractable to within one of the bodies. A solvent is provided for wetting of the pad and solubilizing or suspending the material being sampled from a particular surface.

  3. Sampling apparatus

    DOE Patents [OSTI]

    Gordon, N.R.; King, L.L.; Jackson, P.O.; Zulich, A.W.

    1989-07-18

    A sampling apparatus is provided for sampling substances from solid surfaces. The apparatus includes first and second elongated tubular bodies which telescopically and sealingly join relative to one another. An absorbent pad is mounted to the end of a rod which is slidably received through a passageway in the end of one of the joined bodies. The rod is preferably slidably and rotatably received through the passageway, yet provides a selective fluid tight seal relative thereto. A recess is formed in the rod. When the recess and passageway are positioned to be coincident, fluid is permitted to flow through the passageway and around the rod. The pad is preferably laterally orientable relative to the rod and foldably retractable to within one of the bodies. A solvent is provided for wetting of the pad and solubilizing or suspending the material being sampled from a particular surface. 15 figs.

  4. Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2012-October 31, 2013

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  5. Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2011-October 31, 2012

    SciTech Connect (OSTI)

    Mike lewis

    2013-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  6. Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: May 1, 2010-October 31, 2010

    SciTech Connect (OSTI)

    David B. Frederick

    2011-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (#LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  7. Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2010-October 31, 2011

    SciTech Connect (OSTI)

    David Frederick

    2012-02-01

    This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (No.LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  8. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Salmon, Mississippi, Site, Water Sampling Location Map .........5 Water Sampling Field Activities Verification ...

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........1 Water Sampling Locations at the Rulison, .........3 Water Sampling Field Activities Verification ...

  10. Visual Sample Plan

    Energy Science and Technology Software Center (OSTI)

    2007-10-25

    VSP selects the appropriate number and location of environmental samples to ensure that the results of statistical tests performed to provide input to risk decisions have the required confidence and performance. VSP Version 5.0 provides sample-size equations or algorithms needed by specific statistical tests appropriate for specific environmental sampling objectives. It also provides data quality assessment and statistical analysis functions to support evaluation of the data and determine whether the data support decisions regarding sitesmore » suspected of contamination. The easy-to-use program is highly visual and graphic. VSP runs on personal computers with Microsoft Windows operating systems (98, NT, 2000, Millennium Edition, CE, and XP) Designed primarily for project managers and users without expertise in statistics, VSP is applicable to two- and three-dimensional populations to be sampled (e.g., rooms and buildings, surface soil, a defined layer of subsurface soil, water bodies, and other similar applications) for studies of environmental quality. VSP is also applicable for designing sampling plans for assessing chem./rad/bio threat and hazard identification within rooms and buildings, and for designing geophysical surveys for UXO identification.« less

  11. September 2004 Water Sampling

    Office of Legacy Management (LM)

    4 Groundwater and Surface Water Sampling at the Slick Rock, Colorado, Processing Sites .........7 Water Sampling Field Activities Verification ...

  12. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Green River, Utah, Disposal Site August 2014 LMSGRN.........7 Water Sampling Field Activities Verification ...

  13. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and May 2014 Groundwater and Surface Water Sampling at the Shiprock, New Mexico, Disposal .........9 Water Sampling Field Activities Verification ...

  14. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Rio Blanco, Colorado, Site October 2014 LMSRBLS00514 .........5 Water Sampling Field Activities Verification ...

  15. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Natural Gas and Produced Water Sampling at the Rulison, Colorado, Site November 2014 LMS.........3 Water Sampling Field Activities Verification ...

  16. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Groundwater and Surface Water Sampling at the Rulison, Colorado, Site October 2015 LMS.........5 Water Sampling Field Activities Verification ...

  17. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Monticello, Utah, Processing Site July 2015 LMSMNT.........7 Water Sampling Field Activities Verification ...

  18. September 2004 Water Sampling

    Office of Legacy Management (LM)

    2015 Groundwater and Surface Water Sampling at the Shiprock, New Mexico, Disposal Site .........9 Water Sampling Field Activities Verification ...

  19. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Rio Blanco, Colorado, Site October 2015 LMSRBLS00515 .........5 Water Sampling Field Activities Verification ...

  20. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Produced Water Sampling at the Rulison, Colorado, Site May 2015 LMSRULS00115 Available .........3 Water Sampling Field Activities Verification ...

  1. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Natural Gas and Produced Water Sampling at the Gasbuggy, New Mexico, Site December 2013 .........5 Water Sampling Field Activities Verification ...

  2. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Produced Water Sampling at the Rulison, Colorado, Site January 2016 LMSRULS00915 .........3 Water Sampling Field Activities Verification ...

  3. September 2004 Water Sampling

    Office of Legacy Management (LM)

    3 Groundwater and Surface Water Sampling at the Monument Valley, Arizona, Processing Site .........7 Water Sampling Field Activities Verification ...

  4. September 2004 Water Sampling

    Office of Legacy Management (LM)

    July 2015 Groundwater and Surface Water Sampling at the Gunnison, Colorado, Processing .........5 Water Sampling Field Activities Verification ...

  5. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Monticello, Utah, Processing Site July 2014 LMSMNT.........7 Water Sampling Field Activities Verification ...

  6. September 2004 Water Sampling

    Office of Legacy Management (LM)

    3 Water Sampling at the Monticello, Utah, Processing Site January 2014 LMSMNTS01013 This .........7 Water Sampling Field Activities Verification ...

  7. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Naturita, Colorado Processing Site October 2013 LMSNAP.........5 Water Sampling Field Activities Verification ...

  8. September 2004 Water Sampling

    Office of Legacy Management (LM)

    4 Groundwater and Surface Water Sampling at the Gunnison, Colorado, Processing Site .........5 Water Sampling Field Activities Verification ...

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Tuba City, Arizona, Disposal Site November 2013 LMSTUB.........9 Water Sampling Field Activities Verification ...

  10. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Groundwater and Surface Water Sampling at the Monticello, Utah, Processing Site January .........7 Water Sampling Field Activities Verification ...

  11. LCLS Sample Preparation Laboratory | Sample Preparation Laboratories

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    LCLS Sample Preparation Laboratory Kayla Zimmerman | (650) 926-6281 Lisa Hammon, LCLS Lab Coordinator Welcome to the LCLS Sample Preparation Laboratory. This small general use wet lab is located in Rm 109 of the Far Experimental Hall near the MEC, CXI, and XCS hutches. It conveniently serves all LCLS hutches and is available for final stage sample preparation. Due to space limitations, certain types of activities may be restricted and all access must be scheduled in advance. User lab bench

  12. Taking a look at audience sample results from the 'Invisible...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    A Bacterial Guide to Your Health (Dec. 11, 2014) Connect Find an Argonne expert by subject. Follow Argonne on Twitter, Facebook, Google+ and LinkedIn. For inquiries on...

  13. Recent Results of the Investigation of a Microfluidic Sampling...

    Office of Scientific and Technical Information (OSTI)

    Close Cite: Bibtex Format Close 0 pages in this document matching the terms "" Search For Terms: Enter terms in the toolbar above to search the full text of this document for ...

  14. DOE Releases Biological Monitoring and Sampling Results Report...

    Office of Environmental Management (EM)

    Contractor, Judy Miller, S.M. Stoller Corporation Public Affairs, (970) 248-6363 jmiller@lm.doe.gov GRAND JUNCTION, Colo. - The U.S. Department of Energy today announced the ...

  15. NVO-410-16 ENVIRONMENTAL SURVEILLANCE SAMPLING RESULTS AT THE...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... 63-64 Area 5 Old Fallout 7.71 x 10'6 Station Area 11 Stake llW-4 8.86 x 10m6 Area 12 ... DISTRIBUTION M. B. Biles, Director, DOS, AECHQ Major General F. A. Camm, AGMMAHQ R. ...

  16. Recent Results of the Investigation of a Microfluidic Sampling...

    Office of Scientific and Technical Information (OSTI)

    Authors: Julia Tripp ; Jack Law ; Tara Smith Publication Date: 2013-10-01 OSTI Identifier: 1114565 Report Number(s): INLCON-13-28060 DOE Contract Number: DE-AC07-05ID14517 ...

  17. September 2004 Water Sampling

    Office of Legacy Management (LM)

    ... Inductively Coupled Plasma (ICP) Interference Check Sample (ICS) Analysis ICP interference check samples ICSA and ICSAB were analyzed at the required frequency to verify the ...

  18. Visual Sample Plan Flyer

    Office of Energy Efficiency and Renewable Energy (EERE)

    This flyer better explains that VSP is a free, easy-to-use software tool that supports development of optimal sampling plans based on statistical sampling theory.

  19. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Groundwater and Surface Water Sampling at the Tuba City, Arizona Disposal Site June 2015 .........7 Water Sampling Field Activities Verification ...

  20. Germanium-76 Sample Analysis

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Engelhard, Mark H.; Zhu, Zihua

    2011-04-01

    The MAJORANA DEMONSTRATOR is a large array of ultra-low background high-purity germanium detectors, enriched in 76Ge, designed to search for zero-neutrino double-beta decay (0???). The DEMONSTRATOR will utilize 76Ge from Russia, and the first one gram sample was received from the supplier for analysis on April 24, 2011. The Environmental Molecular Sciences facility, a DOE user facility at PNNL, was used to make the required isotopic and chemical purity measurements that are essential to the quality assurance for the MAJORANA DEMONSTRATOR. The results of this first analysis are reported here.

  1. Pulsed field sample neutralization

    DOE Patents [OSTI]

    Appelhans, Anthony D.; Dahl, David A.; Delmore, James E.

    1990-01-01

    An apparatus and method for alternating voltage and for varying the rate of extraction during the extraction of secondary particles, resulting in periods when either positive ions, or negative ions and electrons are extracted at varying rates. Using voltage with alternating charge during successive periods to extract particles from materials which accumulate charge opposite that being extracted causes accumulation of surface charge of opposite sign. Charge accumulation can then be adjusted to a ratio which maintains a balance of positive and negative charge emission, thus maintaining the charge neutrality of the sample.

  2. EERE QC Workshop: Overview of Relevant Processes

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    (jet, ultrasonic) - High temperature (arc, plasma) http:www.directindustry.comprodafs-gmbhplasma-thermal-spray-guns-61471-575137.html NREL Image Gallery 17120 9 ...

  3. QC Solar Suzhou Corporation | Open Energy Information

    Open Energy Info (EERE)

    Jiangsu Province, China Zip: 215123 Sector: Solar Product: Suzhou-based solar PV electronics manufacturing firm. Coordinates: 31.3092, 120.613121 Show Map Loading map......

  4. QA/QC QUESTIONNAIRE for SUPPLIERS

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    8 (Released January 12, 1998) Energy Information Administration DOE/EIA-0202(98/1Q) Distribution Category UC-950 Short-Term Energy Outlook Quarterly Projections First Quarter 1998 Energy Information Administration Office of Energy Markets and End Use U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the U.S. Department of Energy. The information contained herein should be

  5. NID Copper Sample Analysis

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Zhu, Zihua

    2011-09-12

    The current focal point of the nuclear physics program at PNNL is the MAJORANA DEMONSTRATOR, and the follow-on Tonne-Scale experiment, a large array of ultra-low background high-purity germanium detectors, enriched in 76Ge, designed to search for zero-neutrino double-beta decay (0νββ). This experiment requires the use of germanium isotopically enriched in 76Ge. The MAJORANA DEMONSTRATOR is a DOE and NSF funded project with a major science impact. The DEMONSTRATOR will utilize 76Ge from Russia, but for the Tonne-Scale experiment it is hoped that an alternate technology, possibly one under development at Nonlinear Ion Dynamics (NID), will be a viable, US-based, lower-cost source of separated material. Samples of separated material from NID require analysis to determine the isotopic distribution and impurities. DOE is funding NID through an SBIR grant for development of their separation technology for application to the Tonne-Scale experiment. The Environmental Molecular Sciences facility (EMSL), a DOE user facility at PNNL, has the required mass spectroscopy instruments for making isotopic measurements that are essential to the quality assurance for the MAJORANA DEMONSTRATOR and for the development of the future separation technology required for the Tonne-Scale experiment. A sample of isotopically separated copper was provided by NID to PNNL in January 2011 for isotopic analysis as a test of the NID technology. The results of that analysis are reported here. A second sample of isotopically separated copper was provided by NID to PNNL in August 2011 for isotopic analysis as a test of the NID technology. The results of that analysis are also reported here.

  6. Fluid sampling tool

    DOE Patents [OSTI]

    Garcia, Anthony R.; Johnston, Roger G.; Martinez, Ronald K.

    2000-01-01

    A fluid-sampling tool for obtaining a fluid sample from a container. When used in combination with a rotatable drill, the tool bores a hole into a container wall, withdraws a fluid sample from the container, and seals the borehole. The tool collects fluid sample without exposing the operator or the environment to the fluid or to wall shavings from the container.

  7. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........5 Water Sampling Field Activities Verification ... Groundwater Quality Data Surface Water Quality Data Equipment Blank Data ...

  8. UNDERSTANDING THE AIR SAMPLING DATA

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    For more comparisons, see the millirem comparisons poster. Dose estimates have been calculated based on the low-volume air sampler results. Low-volume air samplers collect samples ...

  9. The Sample Preparation Laboratories | Sample Preparation Laboratories

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cynthia Patty 1 Sam Webb 2 John Bargar 3 Arizona 4 Chemicals 5 Team Work 6 Bottles 7 Glass 8 Plan Ahead! See the tabs above for Laboratory Access and forms you'll need to complete. Equipment and Chemicals tabs detail resources already available on site. Avoid delays! Hazardous materials use may require a written Standard Operating Procedure (SOP) before you work. Check the Chemicals tab for more information. The Sample Preparation Laboratories The Sample Preparation Laboratories provide wet lab

  10. Rain sampling device

    DOE Patents [OSTI]

    Nelson, D.A.; Tomich, S.D.; Glover, D.W.; Allen, E.V.; Hales, J.M.; Dana, M.T.

    1991-05-14

    The present invention constitutes a rain sampling device adapted for independent operation at locations remote from the user which allows rainfall to be sampled in accordance with any schedule desired by the user. The rain sampling device includes a mechanism for directing wet precipitation into a chamber, a chamber for temporarily holding the precipitation during the process of collection, a valve mechanism for controllably releasing samples of the precipitation from the chamber, a means for distributing the samples released from the holding chamber into vessels adapted for permanently retaining these samples, and an electrical mechanism for regulating the operation of the device. 11 figures.

  11. Rain sampling device

    DOE Patents [OSTI]

    Nelson, Danny A.; Tomich, Stanley D.; Glover, Donald W.; Allen, Errol V.; Hales, Jeremy M.; Dana, Marshall T.

    1991-01-01

    The present invention constitutes a rain sampling device adapted for independent operation at locations remote from the user which allows rainfall to be sampled in accordance with any schedule desired by the user. The rain sampling device includes a mechanism for directing wet precipitation into a chamber, a chamber for temporarily holding the precipitation during the process of collection, a valve mechanism for controllably releasing samples of said precipitation from said chamber, a means for distributing the samples released from the holding chamber into vessels adapted for permanently retaining these samples, and an electrical mechanism for regulating the operation of the device.

  12. Explosive Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Explosive National Security Science Latest Issue:April 2016 past issues All Issues » submit Explosive Results Scientists at Los Alamos are solving national security challenges, from the threat of toothpaste-tube bombs on airliners to ensuring the safety of our nuclear stockpile. April 1, 2016 Explosive Results To test whether a travel-toothpaste-tube-sized bomb could bring down an airliner, Los Alamos scientists tried to blow a hole through half-inch-thick aircraft-grade aluminum using an

  13. NID Copper Sample Analysis

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Zhu, Zihua

    2011-02-01

    The current focal point of the nuclear physics program at PNNL is the MAJORANA DEMONSTRATOR, and the follow-on Tonne-Scale experiment, a large array of ultra-low background high-purity germanium detectors, enriched in 76Ge, designed to search for zero-neutrino double-beta decay (0νββ). This experiment requires the use of germanium isotopically enriched in 76Ge. The DEMONSTRATOR will utilize 76Ge from Russia, but for the Tonne-Scale experiment it is hoped that an alternate technology under development at Nonlinear Ion Dynamics (NID) will be a viable, US-based, lower-cost source of separated material. Samples of separated material from NID require analysis to determine the isotopic distribution and impurities. The MAJORANA DEMONSTRATOR is a DOE and NSF funded project with a major science impact. DOE is funding NID through an SBIR grant for development of their separation technology for application to the Tonne-Scale experiment. The Environmental Molecular Sciences facility (EMSL), a DOE user facility at PNNL, has the required mass spectroscopy instruments for making these isotopic measurements that are essential to the quality assurance for the MAJORANA DEMONSTRATOR and for the development of the future separation technology required for the Tonne-Scale experiment. A sample of isotopically separated copper was provided by NID to PNNL for isotopic analysis as a test of the NID technology. The results of that analysis are reported here.

  14. Vapor and gas sampling of Single-Shell Tank 241-A-101 using the Vapor Sampling System

    SciTech Connect (OSTI)

    Caprio, G.S.

    1995-11-01

    This document presents sampling data resulting from the June 8, 1995, sampling of SST 241-A-101 using the Vapor Sampling System.

  15. September 2004 Water Sampling

    Office of Legacy Management (LM)

    ... the applicable MDL. Inductively Coupled Plasma Interference Check Sample Analysis ... and background correction factors for all inductively coupled plasma instruments. ...

  16. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........7 Water Sampling Field Activities Verification ... Groundwater Quality Data Static Water Level Data Time-Concentration Graphs ...

  17. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........9 Water Sampling Field Activities Verification ... Data Durango Processing Site Surface Water Quality Data Equipment Blank Data Static ...

  18. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........3 Water Sampling Field Activities Verification ... Groundwater Quality Data Surface Water Quality Data Natural Gas Analysis Data ...

  19. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........5 Water Sampling Field Activities Verification ... Groundwater Quality Data Static Water Level Data Hydrographs Time-Concentration ...

  20. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........5 Water Sampling Field Activities Verification ... Groundwater Quality Data Static Water Level Data Hydrograph Time-Concentration ...

  1. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........5 Water Sampling Field Activities Verification ... Groundwater Quality Data Surface Water Quality Data Time-Concentration Graph ...

  2. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........5 Water Sampling Field Activities Verification ... Quality Data Equipment Blank Data Static Water Level Data Time-Concentration Graphs ...

  3. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........5 Water Sampling Field Activities Verification ... Groundwater Quality Data Static Water Level Data Time-Concentration Graphs ...

  4. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........9 Water Sampling Field Activities Verification ... Groundwater Quality Data Surface Water Quality Data Static Water Level Data ...

  5. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........3 Water Sampling Field Activities Verification ... Groundwater Quality Data Surface Water Quality Data Time-Concentration Graphs ...

  6. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........7 Water Sampling Field Activities Verification ... Groundwater Quality Data Surface Water Quality Data Equipment Blank Data Static ...

  7. September 2004 Water Sampling

    Office of Legacy Management (LM)

    .........5 Water Sampling Field Activities Verification ... Groundwater Quality Data Surface Water Quality Data Equipment Blank Data Static ...

  8. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Water Sampling at the Ambrosia Lake, New Mexico, Disposal Site February 2015 LMS/AMB/S01114 This page intentionally left blank U.S. Department of Energy DVP-November 2014, Ambrosia Lake, New Mexico February 2015 RIN 14116607 Page i Contents Sampling Event Summary ...............................................................................................................1 Ambrosia Lake, NM, Disposal Site Planned Sampling Map...........................................................3 Data

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Sampling at the Ambrosia Lake, New Mexico, Disposal Site March 2016 LMS/AMB/S01215 This page intentionally left blank U.S. Department of Energy DVP-December 2015, Ambrosia Lake, New Mexico March 2016 RIN 15117494 Page i Contents Sampling Event Summary ...............................................................................................................1 Ambrosia Lake, NM, Disposal Site Planned Sampling Map...........................................................3 Data Assessment

  10. September 2004 Water Sampling

    Office of Legacy Management (LM)

    October 2013 Groundwater Sampling at the Bluewater, New Mexico, Disposal Site December 2013 LMS/BLU/S00813 This page intentionally left blank U.S. Department of Energy DVP-August and October 2013, Bluewater, New Mexico December 2013 RIN 13085537 and 13095651 Page i Contents Sampling Event Summary ...............................................................................................................1 Private Wells Sampled August 2013 and October 2013, Bluewater, NM, Disposal Site