National Library of Energy BETA

Sample records for water sampling results

  1. 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,

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Groundwater, Surface Water, and Alternate Water Supply System Sampling at the Riverton, Wyoming, Processing Site December 2013 LMS/RVT/S00913 This page intentionally left blank U.S. Department of Energy DVP-September 2013, Riverton, Wyoming December 2013 RIN 13095603 Page i Contents Sampling Event Summary ...............................................................................................................1 Riverton, Wyoming, Sample Location Map

  7. 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.

  8. 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 identified only naturally occurring or ubiquitous man-made constituents, including beta emitters that are presumably responsible for the elevated gross beta values.

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    February 2015 Groundwater and Surface Water Sampling at the Grand Junction, Colorado, Site April 2015 LMS/GJO/S00215 This page intentionally left blank U.S. Department of Energy DVP-February 2015, Grand Junction, Colorado, Site April 2015 RIN 15026795 Page i Contents Sampling Event Summary ...............................................................................................................1 Grand Junction, Colorado, Site Sample Location Map

  10. September 2004 Water Sampling

    Office of Legacy Management (LM)

    4 Groundwater and Surface Water Sampling at the Gunnison, Colorado, Processing Site September 2014 LMS/GUP/S00414 This page intentionally left blank U.S. Department of Energy DVP-April and June 2014, Gunnison, Colorado September 2014 RIN 14046058 and 14066262 Page i Contents Sampling Event Summary ...............................................................................................................1 Gunnison, Colorado, Processing Site Planned Sampling Map

  11. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Naturita, Colorado Processing Site October 2013 LMS/NAP/S00713 This page intentionally left blank U.S. Department of Energy DVP-July 2013, Naturita, Colorado October 2013 RIN 13075483 Page i Contents Sampling Event Summary ...............................................................................................................1 Naturita, Colorado, Sample Location Map ......................................................................................3

  12. September 2004 Water Sampling

    Office of Legacy Management (LM)

    4 Groundwater and Surface Water Sampling at the Slick Rock, Colorado, Processing Sites December 2014 LMS/SRW/SRE/S00914 This page intentionally left blank U.S. Department of Energy DVP-September 2014, Slick Rock, Colorado December 2014 RIN 14096456 Page i Contents Sampling Event Summary ...............................................................................................................1 Slick Rock, Colorado, Processing Sites, Sample Location Map

  13. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Groundwater and Surface Water Sampling at the Slick Rock, Colorado, Processing Sites January 2016 LMS/SRE/SRW/S00915 This page intentionally left blank U.S. Department of Energy DVP-September 2015, Slick Rock, Colorado January 2016 RINs 15087319 and 15107424 Page i Contents Sampling Event Summary ...............................................................................................................1 Slick Rock, Colorado, Processing Sites, Sample Location Map

  14. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Groundwater and Surface Water Sampling at the Slick Rock East and West, Colorado, Processing Sites November 2013 LMS/SRE/SRW/S0913 This page intentionally left blank U.S. Department of Energy DVP-September 2013, Slick Rock, Colorado November 2013 RIN 13095593 Page i Contents Sampling Event Summary ...............................................................................................................1 Slick Rock East and West, Colorado, Processing Sites, Sample Location Map

  15. 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

  16. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Green River, Utah, Disposal Site August 2014 LMS/GRN/S00614 This page intentionally left blank U.S. Department of Energy DVP-June 2014, Green River, Utah August 2014 RIN 14066228 Page i Contents Sampling Event Summary ...............................................................................................................1 Green River, Utah, Disposal Site Sample Location Map ................................................................5 Data Assessment

  17. September 2004 Water Sampling

    Office of Legacy Management (LM)

    3 Groundwater and Surface Water Sampling at the Monument Valley, Arizona, Processing Site March 2014 LMS/MON/S01213 This page intentionally left blank U.S. Department of Energy DVP-December 2013, Monument Valley, Arizona March 2014 RIN 13125794 Page i Contents Sampling Event Summary ...............................................................................................................1 Monument Valley, Arizona, Processing Site, Sample Location Map

  18. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Monument Valley, Arizona, Processing Site February 2015 LMS/MON/S01214 This page intentionally left blank U.S. Department of Energy DVP-December 2014, Monument Valley, Arizona February 2015 RIN 14126645 Page i Contents Sampling Event Summary ...............................................................................................................1 Monument Valley, Arizona, Disposal Site Sample Location Map ..................................................5

  19. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Monticello, Utah, Processing Site July 2014 LMS/MNT/S00414 This page intentionally left blank U.S. Department of Energy DVP-April 2014, Monticello, Utah July 2014 RIN 14046077 Page i Contents Sampling Event Summary ...............................................................................................................1 Planned Sampling Map, April 2014, Monticello, Utah, Processing Site .........................................5 Data Assessment Summary

  20. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Monticello, Utah, Processing Site July 2015 LMS/MNT/S00415 This page intentionally left blank U.S. Department of Energy DVP-April 2015, Monticello, Utah July 2015 RIN 15046927 Page i Contents Sampling Event Summary ...............................................................................................................1 Monticello, Utah, Processing Site Sample Location Map ...............................................................5 Data Assessment

  1. September 2004 Water Sampling

    Office of Legacy Management (LM)

    3 Water Sampling at the Monticello, Utah, Processing Site January 2014 LMS/MNT/S01013 This page intentionally left blank U.S. Department of Energy DVP-October 2013, Monticello, Utah January 2014 RIN 13105661 and 13105711 Page i Contents Sampling Event Summary ...............................................................................................................1 Planned Sampling Map, Monticello, Utah, Processing and Disposal Site, October 2013 ..............5 Data Assessment Summary

  2. September 2004 Water Sampling

    Office of Legacy Management (LM)

    4 Alternate Water Supply System Sampling at the Riverton, Wyoming, Processing Site May 2014 LMS/RVT/S00314 This page intentionally left blank U.S. Department of Energy DVP-March 2014, Riverton, Wyoming May 2014 RIN 14035986 Page i Contents Sampling Event Summary ...............................................................................................................1 Riverton, WY, Processing Site, Sample Location Map ...................................................................3 Data

  3. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and May 2014 Groundwater and Surface Water Sampling at the Shiprock, New Mexico, Disposal Site June 2014 LMS/SHP/S00314 This page intentionally left blank U.S. Department of Energy DVP-March and May 2014, Shiprock, New Mexico June 2014 RIN 14036011, 14036013, and 14056142 Page i Contents Sampling Event Summary ...............................................................................................................1 Shiprock, New Mexico, Disposal Site, Sample Location Map

  4. September 2004 Water Sampling

    Office of Legacy Management (LM)

    2015 Groundwater and Surface Water Sampling at the Shiprock, New Mexico, Disposal Site June 2015 LMS/SHP/S00315 This page intentionally left blank U.S. Department of Energy DVP-March 2015, Shiprock, New Mexico June 2015 RIN 15036862 and 15036863 Page i Contents Sampling Event Summary ...............................................................................................................1 Planned Sampling Map Shiprock, New Mexico, Disposal Site

  5. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Groundwater and Surface Water Sampling at the Tuba City, Arizona Disposal Site June 2015 LMS/TUB/S00215 This page intentionally left blank U.S. Department of Energy DVP-February 2015, Tuba City, Arizona June 2015 RIN 15026775 Page i Contents Sampling Event Summary ...............................................................................................................1 Planned Sampling Map Tuba City, AZ, Disposal Site February 2015 ............................................5 Data

  6. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Tuba City, Arizona, Disposal Site November 2013 LMS/TUB/S00813 This page intentionally left blank U.S. Department of Energy DVP-August 2013, Tuba City, Arizona November 2013 RIN 13085553 Page i Contents Sampling Event Summary ...............................................................................................................1 Tuba City, Arizona, Disposal Site, Sample Location Map ..............................................................7 Data

  7. Water Sample Concentrator

    ScienceCinema (OSTI)

    Idaho National Laboratory

    2010-01-08

    Automated portable device that concentrates and packages a sample of suspected contaminated water for safe, efficient transport to a qualified analytical laboratory. This technology will help safeguard against pathogen contamination or chemical and biolog

  8. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Green River, Utah, Disposal Site August 2013 LMS/GRN/S00613 This page intentionally left blank U.S. Department of Energy DVP-June 2013, Green River, Utah August 2013 RIN 13065402 Page i Contents Sampling Event Summary ...............................................................................................................1 Data Assessment Summary ..............................................................................................................7 Water Sampling Field Activities

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and September 2013 Groundwater and Surface Water Sampling at the Durango, Colorado, Disposal and Processing Sites March 2014 LMS/DUD/DUP/S00613 This page intentionally left blank U.S. Department of Energy DVP-June and September 2013, Durango, Colorado March 2014 RIN 13055370 and 13085577 Page i Contents Sampling Event Summary ...............................................................................................................1 Durango, Colorado, Disposal Site Sample Location Map-June

  10. 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.

  11. September 2004 Water Sampling

    Office of Legacy Management (LM)

    2014 Groundwater, Surface Water, Produced Water, and Natural Gas Sampling at the Gasbuggy, New Mexico, Site October 2014 LMS/GSB/S00614 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to

  12. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Natural Gas and Produced Water Sampling at the Gasbuggy, New Mexico, Site December 2013 LMS/GSB/S00613 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its

  13. September 2004 Water Sampling

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Rio Blanco, Colorado, Site October 2014 LMS/RBL/S00514 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in

  14. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Groundwater and Surface Water Sampling at the Rio Blanco, Colorado, Site October 2015 LMS/RBL/S00515 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its

  15. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Produced Water Sampling at the Rulison, Colorado, Site May 2015 LMS/RUL/S00115 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in paper,

  16. September 2004 Water Sampling

    Office of Legacy Management (LM)

    5 Groundwater and Surface Water Sampling at the Rulison, Colorado, Site October 2015 LMS/RUL/S00515 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its

  17. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Natural Gas and Produced Water Sampling at the Rulison, Colorado, Site November 2014 LMS/RUL/S00714 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its

  18. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Water Sampling at the Salmon, Mississippi, Site March 2014 Approved for public release; further dissemination unlimited LMS/SAL/S00413 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S.

  19. Water Sampling | Open Energy Information

    Open Energy Info (EERE)

    Water Sampling Details Activities (63) Areas (51) Regions (5) NEPA(2) Exploration Technique Information Exploration Group: Field Techniques Exploration Sub Group: Field Sampling...

  20. Water and Sediment Sampling

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

    L) (Bq/L) Sample of Opportunity * 9/13/2014 Below MDC Below MDC Sample of Opportunity * 9/13/2014 Below MDC Below MDC Sample of Opportunity * 9/13/2014 Below MDC Below MDC Sample of Opportunity (Dupe) * 9/13/2014 Below MDC Below MDC Sample of Opportunity * 9/13/2014 Below MDC Below MDC Sample of Opportunity * 9/13/2014 Below MDC Below MDC Blank 9/13/2014 Below MDC Below MDC Sample of Opportunity * 8/26/2014 Below MDC Below MDC Sample of Opportunity (Dupe) * 8/26/2014 Below MDC Below MDC Sample

  1. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Groundwater Sampling at the Grand Junction, Colorado, Disposal Site November 2014 LMS/GRJ/S00814 This page intentionally left blank U.S. Department of Energy DVP-August 2014, Grand Junction, Colorado November 2014 RIN 14076376 Page i Contents Sampling Event Summary ...............................................................................................................1 Grand Junction, Colorado, Disposal Site Sample Location Map ....................................................3 Data

  2. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Sampling at the Grand Junction, Colorado, Disposal Site November 2013 LMS/GRJ/S00813 This page intentionally left blank U.S. Department of Energy DVP-August 2013, Grand Junction, Colorado November 2013 RIN 13075515 Page i Contents Sampling Event Summary ...............................................................................................................1 Grand Junction, Colorado, Disposal Site Sample Location Map ....................................................3 Data Assessment

  3. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Old and New Rifle, Colorado, Processing Sites August 2013 LMS/RFN/RFO/S00613 This page intentionally left blank U.S. Department of Energy DVP-June 2013, Rifle, Colorado August 2013 RIN 13065380 Page i Contents Sampling Event Summary ...............................................................................................................1 Sample Location Map, New Rifle, Colorado, Processing Site ........................................................5 Sample Location Map, Old Rifle,

  4. 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

  5. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Groundwater Sampling at the Bluewater, New Mexico, Disposal Site February 2015 LMS/BLU/S01114 This page intentionally left blank U.S. Department of Energy DVP-November 2014, Bluewater, New Mexico February 2015 RIN 14116606 Page i Contents Sampling Event Summary ...............................................................................................................1 Bluewater, New Mexico, Disposal Site, Sample Location Map......................................................5 Data

  6. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Sampling at the Shirley Basin South, Wyoming, Disposal Site September 2013 LMS/SBS/S00613 This page intentionally left blank U.S. Department of Energy DVP-June 2013, Shirley Basin South, Wyoming September 2013 RIN 13065426 Page i Contents Sampling Event Summary ...............................................................................................................1 Shirley Basin South, Wyoming, Disposal Site Sample Location Map ............................................3 Data Assessment

  7. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Sampling at the Falls City, Texas, Disposal Site July 2015 LMS/FCT/S00415 This page intentionally left blank U.S. Department of Energy DVP-April 2015, Falls City, Texas July 2015 RIN 15036899 Page i Contents Sampling Event Summary ...............................................................................................................1 Falls City, Texas, Disposal Site Sample Location Map...................................................................3 Data Assessment Summary

  8. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Sampling at the Hallam, Nebraska, Decommissioned Reactor Site September 2014 LMS/HAL/S00614 This page intentionally left blank U.S. Department of Energy DVP-June 2014, Hallam, Nebraska September 2014 RIN 14056211 Page i Contents Sampling Event Summary ...............................................................................................................1 Hallam, Nebraska, Sample Location Map .......................................................................................3 Data

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Sampling at the Sherwood, Washington, Disposal Site October 2013 LMS/SHE/S00713 This page intentionally left blank U.S. Department of Energy DVP-July 2013, Sherwood, Washington October 2013 RIN 13075481 Page i Contents Sampling Event Summary ...............................................................................................................1 Sherwood, Washington, Disposal Site Sample Location Map ........................................................3 Data Assessment Summary

  10. September 2004 Water Sampling

    Office of Legacy Management (LM)

    conducted in accordance with the Sampling and Analysis Plan for the U. S. Department of Energy Office of Legacy Management Sites (LMSPROS04351, continually updated). Monitoring...

  11. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Grand Junction, Colorado, Site April 2014 LMS/GJO/S00214 This page intentionally left blank U.S. Department of Energy DVP-February 2014, Grand Junction, Colorado April 2014 RIN 14025928 Page i Contents Sampling Event Summary ...............................................................................................................1 Grand Junction, Colorado, Site Sample Location Map ...................................................................3 Data Assessment Summary

  12. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Rifle, Colorado, New and Old Processing Sites January 2014 LMS/RFN/RFO/S01113 This page intentionally left blank U.S. Department of Energy DVP-November 2013, Rifle, Colorado January 2014 RIN 13115731 Page i Contents Sampling Event Summary ...............................................................................................................1 New Rifle, Colorado, Processing Site, Sample Location Map ........................................................5 Old Rifle, Colorado, Processing

  13. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Old and New Rifle, Colorado, Processing Sites January 2015 LMS/RFN/RFO/S01114 This page intentionally left blank U.S. Department of Energy DVP-November 2014, Rifle, Colorado January 2015 RINs 14106568 and 14106569 Page i Contents Sampling Event Summary ...............................................................................................................1 New Rifle, Colorado, Processing Site, Planned Sampling Map ......................................................3 Old Rifle,

  14. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Ambrosia Lake, New Mexico, Disposal Site February 2014 LMS/AMB/S01113 This page intentionally left blank U.S. Department of Energy DVP-November 2013, Ambrosia Lake, New Mexico February 2014 RIN 13115745 Page i Contents Sampling Event Summary ...............................................................................................................1 Ambrosia Lake, New Mexico, Disposal Site Sample Location Map ..............................................3 Data Assessment

  15. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Bluewater, New Mexico, Disposal Site February 2014 LMS/BLU/S01113 This page intentionally left blank U.S. Department of Energy DVP-November 2013, Bluewater, New Mexico February 2014 RIN 13115746 Page i Contents Sampling Event Summary ...............................................................................................................1 Bluewater, New Mexico, Disposal Site Sample Location Map.......................................................5 Data Assessment Summary

  16. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Burrell, Pennsylvania, Disposal Site January 2014 LMS/BUR/S01113 This page intentionally left blank U.S. Department of Energy DVP-November 2013, Burrell, Pennsylvania January 2014 RIN 13095638 Page i Contents Sampling Event Summary ...............................................................................................................1 Burrell, Pennsylvania, Disposal Site, Sample Location Map ..........................................................3 Data Assessment Summary

  17. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Canonsburg, Pennsylvania, Disposal Site February 2014 LMS/CAN/S01113 This page intentionally left blank U.S. Department of Energy DVP-November 2013, Canonsburg, Pennsylvania February 2014 RIN 13095639 Page i Contents Sampling Event Summary ...............................................................................................................1 Canonsburg, Pennsylvania, Disposal Site, Sample Location Map ..................................................3 Data Assessment Summary

  18. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Gasbuggy, New Mexico, Site October 2009 LMS/GSB/S00609 This page intentionally left blank U.S. Department of Energy DVP-June 2009, Gasbuggy, New Mexico October 2009 RIN 09062379, 09062380, 09062381 Page i Contents Sampling Event Summary ...............................................................................................................1 Gasbuggy, New Mexico, Sampling Locations ................................................................................2 Data Assessment Summary

  19. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Disposal Site August 2014 LMS/LKD/S00514 This page intentionally left blank U.S. Department of Energy DVP-May 2014, Lakeview, Oregon, Disposal August 2014 RIN 14056157 Page i Contents Sampling Event Summary ...............................................................................................................1 Lakeview, Oregon, Disposal Site, Sample Location Map ...............................................................3 Data Assessment Summary

  20. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Processing Site August 2014 LMS/LKP/S00514 This page intentionally left blank U.S. Department of Energy DVP-May 2014, Lakeview, Oregon, Processing August 2014 RIN 14056157 and 14056158 Page i Contents Sampling Event Summary ...............................................................................................................1 Lakeview, Oregon, Processing Site, Sample Location Map ............................................................3 Data Assessment Summary

  1. September 2004 Water Sampling

    Office of Legacy Management (LM)

    L-Bar, New Mexico, Disposal Site February 2014 LMS/BAR/S01113 This page intentionally left blank U.S. Department of Energy DVP-November 2013, L-Bar, New Mexico February 2014 RIN 13115747 Page i Contents Sampling Event Summary ...............................................................................................................1 L-Bar, New Mexico, Disposal Site Sample Location Map .............................................................3 Data Assessment Summary

  2. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Monticello, Utah, Processing Site January 2015 LMS/MNT/S01014 This page intentionally left blank U.S. Department of Energy DVP-October 2014, Monticello, Utah January 2015 RIN 14106558 Page i Contents Sampling Event Summary ...............................................................................................................1 Monticello, Utah, Processing Site Sample Location Map ...............................................................5 Data Assessment Summary

  3. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Riverton, Wyoming, Processing Site September 2013 LMS/RVT/S00613 This page intentionally left blank U.S. Department of Energy DVP-June 2013, Riverton, Wyoming September 2013 RIN 13065379 Page i Contents Sampling Event Summary ...............................................................................................................1 Riverton, Wyoming, Processing Site, Sample Location Map .........................................................5 Data Assessment Summary

  4. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Shirley Basin South, Wyoming, Disposal Site October 2015 LMS/SBS/S00715 This page intentionally left blank U.S. Department of Energy DVP-Shirley Basin South, Wyoming October 2015 RIN 15067185 Page i Contents Sampling Event Summary ...............................................................................................................1 Shirley Basin South, Wyoming, Disposal Site, Sample Location Map ...........................................3 Data Assessment Summary

  5. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Tuba City, Arizona, Disposal Site May 2014 LMS/TUB/S00214 This page intentionally left blank U.S. Department of Energy DVP-February 2014, Tuba City, Arizona May 2014 RIN 14025914 Page i Contents Sampling Event Summary ...............................................................................................................1 Tuba City, Arizona, Disposal, Site, Sample Location Map .............................................................7 Data Assessment Summary

  6. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Falls City, Texas, Disposal Site April 2014 LMS/FCT/S00214 This page intentionally left blank U.S. Department of Energy DVP-February 2014, Falls City, Texas April 2014 RIN 14025923 Page i Contents Sampling Event Summary ...............................................................................................................1 Falls City, Texas, Disposal Site, Sample Location Map..................................................................3 Data Assessment Summary

  7. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Parkersburg, West Virginia, Disposal Site February 2014 LMS/PKB/S01113 This page intentionally left blank U.S. Department of Energy DVP-November 2013, Parkersburg, West Virginia February 2014 13095640, 13115753 Page i Contents Sampling Event Summary ...............................................................................................................1 Parkersburg, West Virginia, Disposal Site Sample Location Map ..................................................5 Data Assessment Summary

  8. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Sherwood, Washington, Disposal Site July 2014 LMS/SHE/S00514 This page intentionally left blank U.S. Department of Energy DVP-May 2014, Sherwood, Washington July 2014 RIN 14056159 Page i Contents Sampling Event Summary ...............................................................................................................1 Sherwood, Washington, Disposal Site Sample Location Map ........................................................3 Data Assessment Summary

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    4 Groundwater Sampling at the Central Nevada Test Area February 2015 LMS/CNT/S01214 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in

  10. Category:Water Sampling | Open Energy Information

    Open Energy Info (EERE)

    Water Sampling Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermalpower.jpg Looking for the Water Sampling page? For detailed information on Water Sampling as...

  11. Water-Gas Sampling | Open Energy Information

    Open Energy Info (EERE)

    Water-Gas Sampling (Redirected from Water-Gas Samples) Redirect page Jump to: navigation, search REDIRECT Downhole Fluid Sampling Retrieved from "http:en.openei.orgw...

  12. 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

  13. 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. There were 53 recommendations for improving operations recently identified. Some additional considerations or additional details are provided below as recommendations. ? From this point on, IC-Anions analyses of the DSSHT should be part of the monthly routine analysis in order to spot negative trends in the oxalate leaving the MCU system. Care must be taken to monitor the oxalate content to watch for sudden precipitation of oxalate salts in the system. ? Conduct a study to optimize the cleaning strategy at ARP-MCU through decreasing the concentration or entirely eliminating the oxalic acid. ? The contents of the SSFT should remain unagitated. Routine visual observation should be maintained to ensure there is not a large buildup of solids. As water with agitation provided sufficient removal of the solids in the feed tank, it should be considered as a good means for dissolving oxalate solids if they are found in the future. ? Conduct a study to improve prediction of oxalate solubility in salt batch feed materials. As titanium and mercury have been found in various solids in this report, evaluate if either element plays a role in oxalate solubility during processing. ? Salt batch characterization focuses primarily on characterization and testing of unaltered Tank 21H material; however, non-typical feeds are developed through cleaning, washing, and/or sump transfers. As these solutions are processed through MCU, they may precipitate solids or reduce performance. Salt batch characterization and testing should be expanded to encompass a broader range of feeds that may be processed through ARPMCU.

  14. Water Sampling (Healy, 1970) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling (Healy, 1970) Exploration Activity Details Location Unspecified Exploration...

  15. Water Sampling At International Geothermal Area, Philippines...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At International Geothermal Area, Philippines (Wood, 2002) Exploration...

  16. 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.

  17. Surface Water Sampling | Open Energy Information

    Open Energy Info (EERE)

    Surface Water Sampling Details Activities (3) Areas (2) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Field Techniques Exploration Sub Group: Field...

  18. Water Sampling (Lewicki & Oldenburg, 2004) | Open Energy Information

    Open Energy Info (EERE)

    Water Sampling (Lewicki & Oldenburg, 2004) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling (Lewicki & Oldenburg, 2004) Exploration...

  19. Category:Surface Water Sampling | Open Energy Information

    Open Energy Info (EERE)

    Surface Water Sampling Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermalpower.jpg Looking for the Surface Water Sampling page? For detailed information on...

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

    SciTech Connect (OSTI)

    None

    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.

  1. 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.

  2. Water Sampling At Lightning Dock Geothermal Area (Swanberg, 1976...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Lightning Dock Geothermal Area (Swanberg, 1976) Exploration Activity...

  3. Water Sampling At International Geothermal Area, New Zealand...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At International Geothermal Area, New Zealand (Wood, 2002) Exploration...

  4. Water Sampling At Lightning Dock Geothermal Area (Witcher, 2006...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Lightning Dock Geothermal Area (Witcher, 2006) Exploration Activity...

  5. Water Sampling At Mokapu Penninsula Area (Thomas, 1986) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Mokapu Penninsula Area (Thomas, 1986) Exploration Activity Details...

  6. Water Sampling At Blackfoot Reservoir Area (Hutsinpiller & Parry...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Blackfoot Reservoir Area (Hutsinpiller & Parry, 1985) Exploration Activity...

  7. Water Sampling At Valles Caldera - Sulphur Springs Geothermal...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Valles Caldera - Sulphur Springs Geothermal Area (Trainer, 1974)...

  8. UMTRA water sampling and analysis plan, Green River, Utah

    SciTech Connect (OSTI)

    Papusch, R.

    1993-12-01

    The purpose of this water sampling and analysis plan (WSAP) is to provide a basis for groundwater and surface water sampling at the Green River Uranium Mill Tailing Remedial Action (UMTRA) Project site. This WSAP identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the monitoring locations.

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

    Energy Savers [EERE]

    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

  10. Interpretation of Water Sample Analysis, Waunita Hot Spring Project...

    Open Energy Info (EERE)

    of Water Sample Analysis, Waunita Hot Spring Project, Gunnison County, Colorado Author R. H. Carpenter Organization Colorado Geological Survey in Cooperation with the U.S....

  11. Ch. III, Interpretation of water sample analyses Waunita Hot...

    Open Energy Info (EERE)

    of water sample analyses Waunita Hot Springs area Gunnison County, Colorado Author R. H. Carpenter Editor T. G. Zacharakis Published Colorado Geological Survey in Cooperation...

  12. Water Sampling At Dixie Valley Geothermal Area (Wood, 2002) ...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Dixie Valley Geothermal Area (Wood, 2002) Exploration Activity Details...

  13. Water Sampling At Valley Of Ten Thousand Smokes Region Area ...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Valley Of Ten Thousand Smokes Region Area (Keith, Et Al., 1992)...

  14. Water Sampling At Little Valley Area (Wood, 2002) | Open Energy...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Little Valley Area (Wood, 2002) Exploration Activity Details Location...

  15. Water Sampling At Kilauea East Rift Geothermal Area (Thomas,...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Kilauea East Rift Geothermal Area (Thomas, 1986) Exploration Activity...

  16. Water Sampling At Teels Marsh Area (Coolbaugh, Et Al., 2006)...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Teels Marsh Area (Coolbaugh, Et Al., 2006) Exploration Activity Details...

  17. Water Sampling At Yellowstone Region (Hurwitz, Et Al., 2007)...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Yellowstone Region (Hurwitz, Et Al., 2007) Exploration Activity Details...

  18. Water Sampling At Hawthorne Area (Lazaro, Et Al., 2010) | Open...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Hawthorne Area (Lazaro, Et Al., 2010) Exploration Activity Details...

  19. Water Sampling At Hualalai Northwest Rift Area (Thomas, 1986...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Hualalai Northwest Rift Area (Thomas, 1986) Exploration Activity Details...

  20. Water Sampling At Central Nevada Seismic Zone Region (Laney,...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Central Nevada Seismic Zone Region (Laney, 2005) Exploration Activity...

  1. Surface Water Sampling At Raft River Geothermal Area (1973) ...

    Open Energy Info (EERE)

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Surface Water Sampling At Raft River Geothermal Area (1973) Exploration Activity Details Location...

  2. Water Sampling At Alvord Hot Springs Area (Wood, 2002) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Alvord Hot Springs Area (Wood, 2002) Exploration Activity Details Location...

  3. Water Sampling At Beowawe Hot Springs Area (Wood, 2002) | Open...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Beowawe Hot Springs Area (Wood, 2002) Exploration Activity Details...

  4. Water Sampling At Salton Sea Area (Wood, 2002) | Open Energy...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Salton Sea Area (Wood, 2002) Exploration Activity Details Location Salton...

  5. Water Sampling At Rhodes Marsh Area (Coolbaugh, Et Al., 2006...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Rhodes Marsh Area (Coolbaugh, Et Al., 2006) Exploration Activity Details...

  6. Water Sampling At Waunita Hot Springs Geothermal Area (Carpenter...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Waunita Hot Springs Geothermal Area (Carpenter, 1981) Exploration Activity...

  7. Water Sampling At Mccredie Hot Springs Area (Wood, 2002) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Mccredie Hot Springs Area (Wood, 2002) Exploration Activity Details...

  8. Water Sampling At Umpqua Hot Springs Area (Wood, 2002) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Umpqua Hot Springs Area (Wood, 2002) Exploration Activity Details Location...

  9. Water Sampling At Long Valley Caldera Geothermal Area (Sorey...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Long Valley Caldera Geothermal Area (Sorey, Et Al., 1991) Exploration...

  10. Water Sampling At Salt Wells Area (Shevenell & Garside, 2003...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Salt Wells Area (Shevenell & Garside, 2003) Exploration Activity Details...

  11. Surface Water Sampling At Chena Geothermal Area (Holdmann, Et...

    Open Energy Info (EERE)

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Surface Water Sampling At Chena Geothermal Area (Holdmann, Et Al., 2006) Exploration Activity...

  12. Water Sampling At Buffalo Valley Hot Springs Area (Laney, 2005...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Buffalo Valley Hot Springs Area (Laney, 2005) Exploration Activity Details...

  13. Water Sampling At Valles Caldera - Redondo Area (Rao, Et Al....

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Valles Caldera - Redondo Area (Rao, Et Al., 1996) Exploration Activity...

  14. Water Sampling At Mt Princeton Hot Springs Geothermal Area (Olson...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Mt Princeton Hot Springs Geothermal Area (Olson & Dellechaie, 1976)...

  15. Water-Gas Samples At Valles Caldera - Redondo Geothermal Area...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water-Gas Samples At Valles Caldera - Redondo Geothermal Area (Janik & Goff, 2002)...

  16. Water Sampling At Dixie Valley Geothermal Area (Kennedy & Soest...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Dixie Valley Geothermal Area (Kennedy & Soest, 2006) Exploration Activity...

  17. Water Sampling At Long Valley Caldera Geothermal Area (Evans...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Long Valley Caldera Geothermal Area (Evans, Et Al., 2002) Exploration...

  18. Water Sampling At Roosevelt Hot Springs Geothermal Area (Faulder...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Roosevelt Hot Springs Geothermal Area (Faulder, 1991) Exploration Activity...

  19. Water Sampling At Mt Ranier Area (Frank, 1995) | Open Energy...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Mt Ranier Area (Frank, 1995) Exploration Activity Details Location Mt...

  20. Water Sampling At Valles Caldera - Sulphur Springs Geothermal...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Valles Caldera - Sulphur Springs Geothermal Area (Goff, Et Al., 1982)...

  1. Water Sampling At Valles Caldera - Redondo Geothermal Area (Goff...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Valles Caldera - Redondo Geothermal Area (Goff, Et Al., 1982) Exploration...

  2. Water Sampling At Jemez Springs Geothermal Area (Trainer, 1974...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Jemez Springs Geothermal Area (Trainer, 1974) Exploration Activity Details...

  3. Water Sampling At Northern Basin & Range Region (Laney, 2005...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Northern Basin & Range Region (Laney, 2005) Exploration Activity Details...

  4. Water Sampling At Kauai Area (Thomas, 1986) | Open Energy Information

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Kauai Area (Thomas, 1986) Exploration Activity Details Location Kauai Area...

  5. Water Sampling At Walker-Lane Transitional Zone Region (Laney...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Walker-Lane Transitional Zone Region (Laney, 2005) Exploration Activity...

  6. Water Sampling At Zim's Hot Springs Geothermal Area (Wood, 2002...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Zim's Hot Springs Geothermal Area (Wood, 2002) Exploration Activity...

  7. Water Sampling At Heber Area (Wood, 2002) | Open Energy Information

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Heber Area (Wood, 2002) Exploration Activity Details Location Heber Area...

  8. Water Sampling At Nw Basin & Range Region (Laney, 2005) | Open...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Nw Basin & Range Region (Laney, 2005) Exploration Activity Details...

  9. Water Sampling At Breitenbush Hot Springs Area (Wood, 2002) ...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Breitenbush Hot Springs Area (Wood, 2002) Exploration Activity Details...

  10. Water Sampling At Salt Wells Area (Coolbaugh, Et Al., 2006) ...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Salt Wells Area (Coolbaugh, Et Al., 2006) Exploration Activity Details...

  11. Water Sampling At Valles Caldera - Sulphur Springs Area (Rao...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Valles Caldera - Sulphur Springs Area (Rao, Et Al., 1996) Exploration...

  12. Water Sampling At Lualualei Valley Area (Thomas, 1986) | Open...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Lualualei Valley Area (Thomas, 1986) Exploration Activity Details Location...

  13. Water Sampling At Crane Hot Springs Area (Wood, 2002) | Open...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Crane Hot Springs Area (Wood, 2002) Exploration Activity Details Location...

  14. Water Sampling At Mt St Helens Area (Shevenell & Goff, 1995)...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Mt St Helens Area (Shevenell & Goff, 1995) Exploration Activity Details...

  15. Water Sampling At Kilauea East Rift Geothermal Area (FURUMOTO...

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    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Kilauea East Rift Geothermal Area (FURUMOTO, 1976) Exploration Activity...

  16. Water Sampling At Mickey Hot Springs Area (Wood, 2002) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Mickey Hot Springs Area (Wood, 2002) Exploration Activity Details Location...

  17. Water Sampling At Long Valley Caldera Geothermal Area (Goff,...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Long Valley Caldera Geothermal Area (Goff, Et Al., 1991) Exploration...

  18. 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 above their MDCs. The identification of distributions and the selection of UCL95 procedures generally followed the protocol in Singh, Armbya, and Singh [2010]. When all of an analyte's measurements lie below their MDCs, only a summary of the MDCs can be provided. The measurement results reported by SRNL are listed, and the results of this analysis are reported. The data were generally found to follow a normal distribution, and to be homogenous across composite samples.

  19. 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.

  20. 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.

  1. 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.

  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. UMTRA project water sampling and analysis plan, Tuba City, Arizona

    SciTech Connect (OSTI)

    1996-02-01

    Planned, routine ground water sampling activities at the U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site in Tuba City, Arizona, are described in the following sections of this water sampling and analysis plan (WSAP). This plan identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the stations routinely monitored at the site. The ground water data are used for site characterization and risk assessment. The regulatory basis for routine ground water monitoring at UMTRA Project sites is derived from the U.S. Environmental Protection Agency (EPA) regulations in 40 CFR Part 192 (1994) and the final EPA standards of 1995 (60 FR 2854). Sampling procedures are guided by the UMTRA Project standard operating procedures (SOP) (JEG, n.d.), and the most effective technical approach for the site.

  4. UMTRA project water sampling and analysis plan, Monument Valley, Arizona

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The Monument Valley Uranium Mill Tailings Remedial Action (UMTRA) Project site in Cane Valley is a former uranium mill that has undergone surface remediation in the form of tailings and contaminated materials removal. Contaminated materials from the Monument Valley (Arizona) UMTRA Project site have been transported to the Mexican Hat (Utah) UMTRA Project site for consolidation with the Mexican Hat tailings. Tailings removal was completed in February 1994. Three geologic units at the site contain water: the unconsolidated eolian and alluvial deposits (alluvial aquifer), the Shinarump Conglomerate (Shinarump Member), and the De Chelly Sandstone. Water quality analyses indicate the contaminant plume has migrated north of the site and is mainly in the alluvial aquifer. An upward hydraulic gradient in the De Chelly Sandstone provides some protection to that aquifer. This water sampling and analysis plan recommends sampling domestic wells, monitor wells, and surface water in April and September 1994. The purpose of sampling is to continue periodic monitoring for the surface program, evaluate changes to water quality for site characterization, and provide data for the baseline risk assessment. Samples taken in April will be representative of high ground water levels and samples taken in September will be representative of low ground water levels. Filtered and nonfiltered samples will be analyzed for plume indicator parameters and baseline risk assessment parameters.

  5. RAPID DETERMINATION OF {sup 210} PO IN WATER SAMPLES

    SciTech Connect (OSTI)

    Maxwell, S.

    2013-05-22

    A new rapid method for the determination of {sup 210}Po in water samples has been developed at the Savannah River National Laboratory (SRNL) that can be used for emergency response or routine water analyses. If a radiological dispersive device (RDD) event or a radiological attack associated with drinking water supplies occurs, there will be an urgent need for rapid analyses of water samples, including drinking water, ground water and other water effluents. Current analytical methods for the assay of {sup 210}Po in water samples have typically involved spontaneous auto-deposition of {sup 210}Po onto silver or other metal disks followed by counting by alpha spectrometry. The auto-deposition times range from 90 minutes to 24 hours or more, at times with yields that may be less than desirable. If sample interferences are present, decreased yields and degraded alpha spectrums can occur due to unpredictable thickening in the deposited layer. Separation methods have focused on the use of Sr Resin?, often in combination with 210Pb analysis. A new rapid method for {sup 210}Po in water samples has been developed at the Savannah River National Laboratory (SRNL) that utilizes a rapid calcium phosphate co-precipitation method, separation using DGA Resin? (N,N,N?,N? tetraoctyldiglycolamide extractant-coated resin, Eichrom Technologies or Triskem-International), followed by rapid microprecipitation of {sup 210}Po using bismuth phosphate for counting by alpha spectrometry. This new method can be performed quickly with excellent removal of interferences, high chemical yields and very good alpha peak resolution, eliminating any potential problems with the alpha source preparation for emergency or routine samples. A rapid sequential separation method to separate {sup 210} Po and actinide isotopes was also developed. This new approach, rapid separation with DGA Resin plus microprecipitation for alpha source preparation, is a significant advance in radiochemistry for the rapid determination of {sup 210}Po.

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

    SciTech Connect (OSTI)

    2013-09-01

    The Long-Term Surveillance and Maintenance (LTS&M) Plan for the U.S. Department of Energy (DOE) Office of Legacy Management (LM) Amchitka Island sites describes how LM plans to conduct its mission to protect human health and the environment at the three nuclear test sites located on Amchitka Island, Alaska. Amchitka Island, near the western end of the Aleutian Islands, is approximately 1,340 miles west-southwest of Anchorage, Alaska. Amchitka is part of the Aleutian Island Unit of the Alaska Maritime National Wildlife Refuge, which is administered by the U.S. Fish and Wildlife Service (USFWS). Since World War II, Amchitka has been used by multiple U.S. government agencies for various military and research activities. From 1943 to 1950, it was used as a forward air base for the U.S. Armed Forces. During the middle 1960s and early 1970s, the U.S. Department of Defense (DOD) and the U.S. Atomic Energy Commission (AEC) used a portion of the island as a site for underground nuclear tests. During the late 1980s and early 1990s, the U.S. Navy constructed and operated a radar station on the island. Three underground nuclear tests were conducted on Amchitka Island. DOD, in conjunction with AEC, conducted the first nuclear test (named Long Shot) in 1965 to provide data that would improve the United States' capability of detecting underground nuclear explosions. The second nuclear test (Milrow) was a weapons-related test conducted by AEC in 1969 as a means to study the feasibility of detonating a much larger device. Cannikin, the third nuclear test on Amchitka, was a weapons-related test detonated on November 6, 1971. With the exception of small concentrations of tritium detected in surface water shortly after the Long Shot test, radioactive fission products from the tests remain in the subsurface at each test location As a continuation of the environmental monitoring that has taken place on Amchitka Island since before 1965, LM in the summer of 2011 collected biological and 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. DUS II SOIL GAS SAMPLING AND AIR INJECTION TEST RESULTS

    SciTech Connect (OSTI)

    Noonkester, J.; Jackson, D.; Jones, W.; Hyde, W.; Kohn, J.; Walker, R.

    2012-09-20

    Soil vapor extraction (SVE) and air injection well testing was performed at the Dynamic Underground Stripping (DUS) site located near the M-Area Settling Basin (referred to as DUS II in this report). The objective of this testing was to determine the effectiveness of continued operation of these systems. Steam injection ended on September 19, 2009 and since this time the extraction operations have utilized residual heat that is present in the subsurface. The well testing campaign began on June 5, 2012 and was completed on June 25, 2012. Thirty-two (32) SVE wells were purged for 24 hours or longer using the active soil vapor extraction (ASVE) system at the DUS II site. During each test five or more soil gas samples were collected from each well and analyzed for target volatile organic compounds (VOCs). The DUS II site is divided into four parcels (see Figure 1) and soil gas sample results show the majority of residual VOC contamination remains in Parcel 1 with lesser amounts in the other three parcels. Several VOCs, including tetrachloroethylene (PCE) and trichloroethylene (TCE), were detected. PCE was the major VOC with lesser amounts of TCE. Most soil gas concentrations of PCE ranged from 0 to 60 ppmv with one well (VEW-22A) as high as 200 ppmv. Air sparging (AS) generally involves the injection of air into the aquifer through either vertical or horizontal wells. AS is coupled with SVE systems when contaminant recovery is necessary. While traditional air sparging (AS) is not a primary component of the DUS process, following the cessation of steam injection, eight (8) of the sixty-three (63) steam injection wells were used to inject air. These wells were previously used for hydrous pyrolysis oxidation (HPO) as part of the DUS process. Air sparging is different from the HPO operations in that the air was injected at a higher rate (20 to 50 scfm) versus HPO (1 to 2 scfm). . At the DUS II site the air injection wells were tested to determine if air sparging affected VOC soil gas concentrations during ASVE. Five (5) SVE wells that were located closest to the air injection wells were used as monitoring points during the air sparging tests. The air sparging tests lasted 48 hours. Soil gas sample results indicate that sparging did not affect VOC concentrations in four of the five sparging wells, while results from one test did show an increase in soil gas concentrations.

  8. 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.

  9. Yosemite Waters Vehicle Evaluation Report: Final Results

    SciTech Connect (OSTI)

    Eudy, L.; Barnitt, R.; Alleman, T. L.

    2005-08-01

    Document details the evaluation of Fischer-Tropsch diesel, a gas-to-liquid fuel, in medium-duty delivery vehicles at Yosemite Waters. The study was conducted by NREL at the company's Fullerton, California, bottling headquarters.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  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 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.

  18. 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 {sup 242m}Am is above the target in Listed in Attachment 8.4 of the Saltstone WAC. (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{sup 5} 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. (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 50.

  19. Radiochemical Analyses of Water Samples from Selected Streams

    Office of Legacy Management (LM)

    > : , - ' and Precipitation Collected in - Connection with Calibration-Test Flaring of Gas From Test Well, - I August 15-October 13, 197,0,, Project Rulison-8, 197 1 HGS 9 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. UNITED STATES DEPARTMENT OF THE INTERIOR GEOLOGICAL SURVEY Federal center, Denver, Colorado 80225 RADIOCHEMICAL ANALYSES OF WATER SAMPLES FROM SELECTED STREAMS AND PRECIPITATION

  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 50.

  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 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 3. (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 {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. (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.

  4. 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.

  5. 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.

  6. 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 somewhat more effective in dissolving radionuclides than the water leach. In contrast to the water leaching results, most constituents continued to dissolve during subsequent cycles of oxalic acid leaching. The somewhat higher dissolution found in the oxalic acid leaching test versus the water leaching test might be offset by the tendency of the oxalic acid solutions to take on a gel-like consistency. The filtered solids left behind after three oxalic acid contacts were sticky and formed large clumps after drying. These two observations could indicate potential processing difficulties with solutions and solids from oxalic acid leaching. The gel formation might be avoided by using larger volumes of the acid. Further testing would be recommended before using oxalic acid to dissolve the Tank 16H annulus waste to ensure no processing difficulties are encountered in the full scale process.

  7. 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.

  8. 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.

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

    Office of Scientific and Technical Information (OSTI)

    Sampling System for Hot Cell Aqueous Processing Streams (Conference) | SciTech Connect Recent Results of the Investigation of a Microfluidic Sampling Chip and Sampling System for Hot 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 Aqueous Processing Streams A Fuel Cycle Research and Development project has investigated an innovative sampling method that could evolve

  10. Recent Results of the Investigation of a Microfluidic Sampling Chip and

    Office of Scientific and Technical Information (OSTI)

    Sampling System for Hot Cell Aqueous Processing Streams (Conference) | SciTech Connect Conference: Recent Results of the Investigation of a Microfluidic Sampling Chip and Sampling System for Hot 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 Aqueous Processing Streams A Fuel Cycle Research and Development project has investigated an innovative sampling method that

  11. Water-Gas Samples At Fenton Hill Hdr Geothermal Area (Goff &...

    Open Energy Info (EERE)

    Water-Gas Samples At Fenton Hill Hdr Geothermal Area (Goff & Janik, 2002) Redirect page Jump to: navigation, search REDIRECT Surface Gas Sampling At Fenton Hill Hdr Geothermal...

  12. Yosemite Waters Vehicle Evaluation Report: Final Results (Brochure)

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Results Prepared for South Coast Air Quality Management District by the National Renewable Energy Laboratory CRD-01-098 Fischer-Tropsch Synthetic Fuel Demonstration in a Southern California Vehicle Fleet Yosemite Waters Vehicle Evaluation Report Yosemite Waters Vehicle Evaluation Report i Alternative Fuel Trucks YOSEMITE WATERS VEHICLE EVALUATION REPORT Authors Leslie Eudy, National Renewable Energy Laboratory (NREL) Robb Barnitt, NREL Teresa L. Alleman, NREL August 2005 Acknowledgements This

  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. Diffusion Multilayer Sampling of Ground Water in Five Wells at the Tuba

    Office of Environmental Management (EM)

    City, Arizona, Site | Department of Energy Diffusion Multilayer Sampling of Ground Water in Five Wells at the Tuba City, Arizona, Site Diffusion Multilayer Sampling of Ground Water in Five Wells at the Tuba City, Arizona, Site Diffusion Multilayer Sampling of Ground Water in Five Wells at the Tuba City, Arizona, Site PDF icon Diffusion Multilayer Sampling of Ground Water in Five Wells at the Tuba City, Arizona, Site More Documents & Publications Analysis of MSE Cores Tuba City, Arizona,

  15. 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{sup +}). Concentrated mineral acids and elevated temperature were required to dissolve all of these solids. The refractory nature of some of the solids is consistent with the presence of metal oxides such as aluminosilicates (observed as a minor phase by XRD). Characterization of the water wash solutions and the digested solids confirmed the presence of oxalate salts in both solid samples. Sulfate enrichment was also observed in the Tank 26F solids wash solution, indicating the presence of sulfate precipitates such as burkeite. OLI modeling of the Tank 26F filtered supernatant composition revealed that sodium oxalate has a very low solubility in this solution. The model predicts that the sodium oxalate solubility in the Tank 26F supernatant is only 0.0011 M at 50 C. The results indicate that the highly concentrated nature of the evaporator feed solution and the addition of oxalate anion to the waste stream each contribute to the formation of insoluble solids in the 2F evaporator system.

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

    Office of Scientific and Technical Information (OSTI)

    Sampling System for Hot Cell Aqueous Processing Streams (Conference) | SciTech Connect Recent Results of the Investigation of a Microfluidic Sampling Chip and Sampling System for Hot 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 Aqueous Processing Streams × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product

  17. Water Quality Sampling Locations Along the Shoreline of the Columbia River, Hanford Site, Washington

    SciTech Connect (OSTI)

    Peterson, Robert E.; Patton, Gregory W.

    2009-12-14

    As environmental monitoring evolved on the Hanford Site, several different conventions were used to name or describe location information for various sampling sites along the Hanford Reach of the Columbia River. These methods range from handwritten descriptions in field notebooks to the use of modern electronic surveying equipment, such as Global Positioning System receivers. These diverse methods resulted in inconsistent archiving of analytical results in various electronic databases and published reports because of multiple names being used for the same site and inaccurate position data. This document provides listings of sampling sites that are associated with groundwater and river water sampling. The report identifies names and locations for sites associated with sampling: (a) near-river groundwater using aquifer sampling tubes; (b) riverbank springs and springs areas; (c) pore water collected from riverbed sediment; and (d) Columbia River water. Included in the listings are historical names used for a particular site and the best available geographic coordinates for the site, as of 2009. In an effort to create more consistency in the descriptive names used for water quality sampling sites, a naming convention is proposed in this document. The convention assumes that a unique identifier is assigned to each site that is monitored and that this identifier serves electronic database management requirements. The descriptive name is assigned for the convenience of the subsequent data user. As the historical database is used more intensively, this document may be revised as a consequence of discovering potential errors and also because of a need to gain consensus on the proposed naming convention for some water quality monitoring sites.

  18. RAPID METHOD FOR DETERMINATION OF {sup 228}Ra IN WATER SAMPLES

    SciTech Connect (OSTI)

    Maxwell, S.

    2012-09-05

    A new rapid method for the determination of {sup 228}Ra in natural water samples has been developed at the SRNL/EBL (Savannah River National Lab/ Environmental Bioassay Laboratory) that can be used for emergency response or routine samples. While gamma spectrometry can be employed with sufficient detection limits to determine {sup 228}Ra in solid samples (via {sup 228}Ac) , radiochemical methods that employ gas flow proportional counting techniques typically provide lower MDA (Minimal Detectable Activity) levels for the determination of {sup 228}Ra in water samples. Most radiochemical methods for {sup 228}Ra collect and purify {sup 228}Ra and allow for {sup 228}Ac daughter ingrowth for ~36 hours. In this new SRNL/EBL approach, {sup 228}Ac is collected and purified from the water sample without waiting to eliminate this delay. The sample preparation requires only about 4 hours so that {sup 228}Ra assay results on water samples can be achieved in < 6 hours. The method uses a rapid calcium carbonate precipitation enhanced with a small amount of phosphate added to enhance chemical yields (typically >90%), followed by rapid cation exchange removal of calcium. Lead, bismuth, uranium, thorium and protactinium isotopes are also removed by the cation exchange separation. {sup 228}Ac is eluted from the cation resin directly onto a DGA Resin cartridge attached to the bottom of the cation column to purify {sup 228}Ac. DGA Resin also removes lead and bismuth isotopes, along with Sr isotopes and {sup 90}Y. La is used to determine {sup 228}Ac chemical yield via ICP-MS, but {sup 133}Ba can also be used instead if ICP-MS assay is not available. Unlike some older methods, no lead or strontium holdback carriers or continual readjustment of sample pH is required.

  19. 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. The Cr oxidation front (depth to which soluble Cr was detected) for the Cast Stone sample exposed for 68 days to ambient outdoor temperatures and humid air (total age of sample was 131 days) was determined to be about 35 mm below the top sample surface exposed. The Tc oxidation front, depth at which Tc was insoluble, was not determined. Interpretation of the results indicates that the oxidation front is at least 38 mm below the exposed surface. The sample used for this measurement was exposed to ambient laboratory conditions and humid air for 50 days. The total age of the sample was 98 days. Technetium appears to be more easily oxidized than Cr in the Cast Stone matrix. The oxidized forms of Tc and Cr are soluble and therefore leachable. Longer exposure times are required for both the Cr and Tc spiked samples to better interpret the rate of oxidation. Tc spiked subsamples need to be taken further from the exposed surface to better define and interpret the leachable Tc profile. Finally Tc(VII) reduction to Tc(IV) appears to occur relatively fast. Results demonstrated that about 95 percent of the Tc(VII) was reduced to Tc(IV) during the setting and very early stage setting for a Cast Stone sample cured 10 days. Additional testing at longer curing times is required to determine whether additional time is required to reduce 100 % of the Tc(VII) in Cast Stone or whether the Tc loading exceeded the ability of the waste form to reduce 100 % of the Tc(VII). Additional testing is required for samples cured for longer times. Depth discrete subsampling in a nitrogen glove box is also required to determine whether the 5 percent Tc extracted from the subsamples was the result of the sampling process which took place in air. Reduction capacity measurements (per the Angus-Glasser method) performed on depth discrete samples could not be correlated with the amount of chromium or technetium leached from the depth discrete subsamples or with the oxidation front inferred from soluble chromium and technetium (i.e., effective Cr and Tc oxidation fronts). Residual reduction capacity in the oxidized region of the test samples indicates that the remaining reduction capacity is not effective in re-reducing Cr(VI) or Tc(VII) in the presence of oxygen. Depth discrete sampling and leaching is a useful for evaluating Cast Stone and other chemically reducing waste forms containing ground granulated blast furnace slag (GGBFS) or other reduction / sequestration reagents to control redox sensitive contaminant chemistry and leachability in the near surface disposal environment. Based on results presented in this report, reduction capacity measured by the Angus-Glasser Ce(IV) method is not an appropriate or meaningful parameter for determining or predicting Tc and Cr oxidation / retentions, speciation, or solubilities in cementitious materials such as Cast Stone. A model for predicting Tc(IV) oxidation to soluble Tc(VII) should consider the waste form porosity (pathway for oxygen ingress), oxygen source, and the contaminant specific oxidation rates and oxidation fronts. Depth discrete sampling of materials exposed to realistic conditions in combination with short term leaching of crushed samples has potential for advancing the understanding of factors influencing performance. This information can be used to support conceptual model development.

  20. 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.

  1. 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).

  2. 384 Power plant waste water sampling and analysis plan

    SciTech Connect (OSTI)

    Hagerty, K.J.; Knotek, H.M.

    1995-01-01

    This document presents the 384 Power House Sampling and Analysis Plan. The Plan describes sampling methods, locations, frequency, analytes, and stream descriptions. The effluent streams from 384, were characterized in 1989, in support of the Stream Specific Report (WHC-EP-0342, Addendum 1).

  3. Investigation of the effects of various water mediums on desulfurization and deashing of a coal sample by flotation

    SciTech Connect (OSTI)

    Ayhan, F.D. [Dicle University, Diyarbakir (Turkey)

    2009-08-15

    The aim of this study was to investigate the effects of various water mediums on desulfurization and deashing of a coal sample using flotation. For this purpose, experimental studies were conducted on a coal sample containing high ash and sulfur contents. The effects of pH, solid concentration, collector amount and frother amount on the flotation were investigated separately in Mediterranean Sea water, Cermik thermal spring water, snow water and tap water. Flotation, results indicated that, when comparing the various water mediums, the following order for the ash content was obtained: snow water < Cermik thermal spring water < tap water < the Mediterranean Sea water. For the reduction of total sulfur, the following order was obtained: snow water > Cermik thermal spring water > Mediterranean Sea water > tap water. When snow water was used as a flotation medium, it was found that a concentrate containing 3.01% total sulfur and 27.64% ash with a total sulfur reduction of 57.06% was obtained from a feed containing 7.01% total sulfur and 4.1.17% ash.

  4. June 2011 Natural Gas and Produced Water Sampling at the Gasbuggy, New Mexico, Site

    SciTech Connect (OSTI)

    2011-10-01

    Annual natural gas and produced water monitoring was conducted for gas wells adjacent to Section 36, where the Gasbuggy test was conducted, in accordance with the draft Long-Term Surveillance and Maintenance Plan for the Gasbuggy Site, Rio Arriba County, New Mexico. Sampling and analysis were conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PLN/S04351, continually updated). Natural gas samples were collected for tritium and carbon-14 analyses. Produced water samples were collected and analyzed for tritium, gamma-emitting radionuclides (by high-resolution gamma spectrometry), gross alpha, and gross beta. A duplicate produced water sample was collected from well 30-039-21743. Produced water samples were not collected at locations 30-039-30161 and 30-039-21744 because of the lack of water. Samples were not collected from location 30-039-29988 because the well was shut-in.

  5. Water Sampling At Fenton Hill HDR Geothermal Area (Rao, Et Al...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Fenton Hill HDR Geothermal Area (Rao, Et Al., 1996) Exploration Activity...

  6. Water Sampling At Jemez Springs Area (Rao, Et Al., 1996) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Jemez Springs Area (Rao, Et Al., 1996) Exploration Activity Details...

  7. Water Sampling At Coso Geothermal Area (1977-1978) | Open Energy...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Coso Geothermal Area (1977-1978) Exploration Activity Details Location...

  8. Water Sampling At Silver Peak Area (Henkle, Et Al., 2005) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Silver Peak Area (Henkle, Et Al., 2005) Exploration Activity Details...

  9. Water-Gas Samples At Long Valley Caldera Geothermal Area (Farrar...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water-Gas Samples At Long Valley Caldera Geothermal Area (Farrar, Et Al., 2003) Exploration...

  10. Water-Gas Sampling At Fenton Hill HDR Geothermal Area (Janik...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water-Gas Sampling At Fenton Hill HDR Geothermal Area (Janik & Goff, 2002) Exploration...

  11. Water Sampling At Salt Wells Area (Henkle, Et Al., 2005) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Salt Wells Area (Henkle, Et Al., 2005) Exploration Activity Details...

  12. Water Sampling At Reese River Area (Henkle, Et Al., 2005) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Reese River Area (Henkle, Et Al., 2005) Exploration Activity Details...

  13. Water Sampling At Long Valley Caldera Geothermal Area (McKenzie...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Long Valley Caldera Geothermal Area (McKenzie & Truesdell, 1977)...

  14. Water Sampling At Jemez Springs Area (Goff, Et Al., 1981) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Jemez Springs Area (Goff, Et Al., 1981) Exploration Activity Details...

  15. Water Sampling At Hot Lake Area (Wood, 2002) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Hot Lake Area (Wood, 2002) Exploration Activity Details Location Hot Lake...

  16. Water Sampling At Belknap-Foley-Bigelow Hot Springs Area (Wood...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Belknap-Foley-Bigelow Hot Springs Area (Wood, 2002) Exploration Activity...

  17. Water Sampling At Twenty-Nine Palms Area (Page, Et Al., 2010...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Twenty-Nine Palms Area (Page, Et Al., 2010) Exploration Activity Details...

  18. 400 area secondary cooling water sampling and analysis plan

    SciTech Connect (OSTI)

    Penn, L.L.

    1996-10-29

    This is a total rewrite of the Sampling and Analysis Plan in response to, and to ensure compliance with, the State Waste Discharge Permit ST 4501 issued on July 31, 1996. This revision describes changes in facility status and implements requirements of the permit.

  19. July 2010 Natural Gas and Produced Water Sampling at the Gasbuggy, New Mexico, Site

    SciTech Connect (OSTI)

    None

    2011-01-01

    Annual natural gas and produced water monitoring was conducted for gas wells adjacent to Section 36, where the Gasbuggy test was conducted, in accordance with the draft Long-Term Surveillance and Maintenance Plan for the Gasbuggy Site, Rio Arriba County, New Mexico. Sampling and analysis was conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites. (LMS/PLN/S04351, continually updated). Natural gas samples were collected for tritium and carbon-14 analysis. Produced water samples were collected and analyzed for tritium, gamma-emitting radionuclides (by high-resolution gamma spectrometry), gross alpha, and gross beta. An additional water sample was collected from well 29-6 Water Hole for analysis of tritium and gamma-emitting radionuclides. A duplicate produced water sample was collected from well 30-039-21743.

  20. Microsoft Word - 2014 2 26 WIPP Employees Notified of Preliminary Sample Results

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

    4DR0214 / 001NWPR0214 NWP Media Contacts: Donavan Mager Nuclear Waste Partnership LLC (575) 234-7586 www.wipp.energy.gov For Immediate Release WIPP Employees Notified of Preliminary Sample Results CARLSBAD, N.M., February 26, 2014 - Today, the Department of Energy's Waste Isolation Pilot Plant (WIPP) and Nuclear Waste Partnership LLC, (NWP) the WIPP contractor, notified 13 employees of positive preliminary bioassay results. The results are based on samples taken as a precautionary measure from

  1. 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.

  2. 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.

  3. NVO-410-16 ENVIRONMENTAL SURVEILLANCE SAMPLING RESULTS AT THE. NEVADA TEST SITE

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

    6 ENVIRONMENTAL SURVEILLANCE SAMPLING RESULTS AT THE. NEVADA TEST SITE July, 1968 through June, 1969 REYNOLDS ELECTRICAL & ENGINEERING CO., INC. ENVIRONMENTAL SCIENCES DEPARTMENT LAS VEGAS, NEVADA 89114 October. 1971 ,PREPARED FOR THE U. S. ATOMIC ENERGY COMMISSION, NEVADA OPERATIONS OFFICE UNDER CONTRACT NO. AT(26-l)-410 NVO-410-16 ENVIRONMENTAL SURVEILLANCE SAMPLING RESULTS AT THE NEVADA TEST SITE JULY, 1968 THROUGH JUNE, 1969 BY THE STAFF OF THE ENVIRONMENTAL SURVEILLANCE GROUP

  4. 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.

  5. 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.

  6. 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 ?m, but Phragmites grass seeds ~1 mm in size, were observed on the tops of the Hope Creek canisters. At both sites, the surface dust could be divided into fractions generated by manufacturing processes and by natural processes. The fraction from manufacturing processes consisted of variably-oxidized angular and spherical particles of stainless steel and iron, generated by machining and welding/cutting processes, respectively. Dust from natural sources consisted largely of detrital quartz and aluminosilicates (feldspars and clays) at both sites. At Hope Creek, soluble salts were dominated by sulfates and nitrates, mostly of calcium. Chloride was a trace component and the only chloride mineral observed by SEM was NaCl. Chloride surface loads measured by the Saltsmart™ sensors were very low, less than 60 mg m{sup –2} on the canister top, and less than 10 mg m{sup –2} on the canister sides. At Diablo Canyon, sea-salt aggregates of NaCl and Mg-SO{sub 4}, with minor K and Ca, were abundant in the dust, in some cases dominating the observed dust assemblage. Measured Saltsmart™ chloride surface loads were very low (<5 mg m{sup –2}); however, high canister surface temperatures damaged the Saltsmart™ sensors, and, in view of the SEM observations of abundant sea-salts on the package surfaces, the measured surface loads may not be valid. Moreover, the more heavily-loaded canister tops at Diablo Canyon were not sampled with the Saltsmart™ sensors. The observed low surface loads do not preclude chloride-induced stress corrosion cracking (CISCC) at either site, because (1) the measured data may not be valid for the Diablo Canyon canisters; (2) the surface coverage was not complete (for instance, the 45º offset between the outlet and inlet vents means that near-inlet areas, likely to have heavier dust and salt loads, were not sampled); and (3) CISCC has been experimentally been observed at salt loads as low as 5-8 mg/m{sup 2}. Experimental efforts at SNL to assess corrosion of interim storage canister materials include three tasks in FY14. First, a full-diameter canister mockup, made using materials and techniques identical to those used to make interim st

  7. Water Power Program: Program Plans, Implementation, and Results

    Energy Savers [EERE]

    Water Power Program HOME ABOUT RESEARCH & DEVELOPMENT FINANCIAL OPPORTUNITIES INFORMATION RESOURCES NEWS EVENTS EERE Water Power Program About Key Activities Plans,...

  8. May and June 2015 Groundwater and Surface Water Sampling at the bluewater, New Mexico, Disposal Site

    Office of Legacy Management (LM)

    May and June 2015 Groundwater and Surface Water Sampling at the Bluewater, New Mexico, Disposal Site August 2015 LMS/BLU/S00515 This page intentionally left blank U.S. Department of Energy DVP-May and June 2015, Bluewater, New Mexico August 2015 RIN 15057015 and 15067154 Page i Contents Sampling Event Summary ...............................................................................................................1 Bluewater, New Mexico, Disposal Site, Sample Location

  9. August 2015 Groundwater and Surface Water Sampling at the Tuba City, Arizona, Disposal Site

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Tuba City, Arizona, Disposal Site November 2015 LMS/TUB/S00815 This page intentionally left blank U.S. Department of Energy DVP-August 2015, Tuba City, Arizona, Disposal Site November 2015 RIN 15087262 Page i Contents Sampling Event Summary ...............................................................................................................1 Tuba City, Arizona, Disposal Site, Sample Location Map

  10. 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 &

  11. 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.

  12. 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.

  13. UMTRA project water sampling and analysis plan, Naturita, Colorado. Revision 1

    SciTech Connect (OSTI)

    1995-09-01

    Planned, routine ground water sampling activities for calendar year 1995 to 1997 at the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site near Naturita, Colorado, are described in this water sampling and analysis plan. The following plan identifies and justifies the sampling locations, analytical parameters, detection limits, sampling frequency, and specific rationale for each routine monitoring station at the site. The regulatory basis for routine ground water monitoring at UMTRA Project sites is derived from the US Environmental Protection Agency (EPA) regulations in 40 CFR Part 192. Sampling procedures are guided by the UMTRA Project standard operating procedures (SOP) (JEG, n.d.), the Technical Approach Document (TAD) (DOE, 1989), and the most effective technical approach for the site.

  14. 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.

  15. May 2013 Groundwater and Surface Water Sampling at the Rio Blanco, Colorado, Site (Data Validation Package)

    SciTech Connect (OSTI)

    2013-10-01

    Annual sampling was conducted at the Rio Blanco, Colorado, site for the Long-Term Hydrologic Monitoring Program May 14-16, 2013, to monitor groundwater and surface water for potential radionuclide contamination. Sampling and analyses were conducted as specified in Sampling and Analysis Plan for the U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated). A duplicate sample was collected from location CER #1 Black Sulphur. Samples were analyzed for gamma-emitting radionuclides by high-resolution gamma spectrometry and for tritium using the conventional and enrichment methods.

  16. Analysis of core soil and water samples from the Cactus Crater Disposal Site at Enewetak atoll

    SciTech Connect (OSTI)

    Robison, W.L.; Noshkin, V.E.

    1981-02-18

    Core soil samples and water samples were collected from the Cactus Crater Disposal Site at Enewetak for analysis of /sup 137/Cs, /sup 90/Sr, /sup 239 +240/Pu and /sup 241/Am by both gamma spectroscopy and, through a contractor laboratory, by wet chemistry procedures. The samples processing methods, the analytical methods and the analytical quality control are all procedures developed for the continuing Marshall Island radioecology and dose assessment work.

  17. Aqueous Processing of Atmospheric Organic Particles in Cloud Water Collected via Aircraft Sampling

    SciTech Connect (OSTI)

    Boone, Eric J.; Laskin, Alexander; Laskin, Julia; Wirth, Christopher; Shepson, Paul B.; Stirm, Brian H.; Pratt, Kerri A.

    2015-07-21

    Cloud water and below-cloud atmospheric particle samples were collected onboard a research aircraft during the Southern Oxidant and Aerosol Study (SOAS) over a forested region of Alabama in June 2013. The organic molecular composition of the samples was studied to gain insights into the aqueous-phase processing of organic compounds within cloud droplets. High resolution mass spectrometry with nanospray desorption electrospray ionization and direct infusion electrospray ionization were utilized to compare the organic composition of the particle and cloud water samples, respectively. Isoprene and monoterpene-derived organosulfates and oligomers were identified in both the particles and cloud water, showing the significant influence of biogenic volatile organic compound oxidation above the forested region. While the average O:C ratios of the organic compounds were similar between the atmospheric particle and cloud water samples, the chemical composition of these samples was quite different. Specifically, hydrolysis of organosulfates and formation of nitrogen-containing compounds were observed for the cloud water when compared to the atmospheric particle samples, demonstrating that cloud processing changes the composition of organic aerosol.

  18. Site-Wide Integrated Water Monitoring -- Defining and Implementing Sampling Objectives to Support Site Closure

    SciTech Connect (OSTI)

    Wilborn, Bill; Marutzky, Sam; Knapp, Kathryn

    2013-02-24

    The Underground Test Area (UGTA) activity is responsible for assessing and evaluating the effects of the underground nuclear weapons tests on groundwater at the Nevada National Security Site (NNSS), formerly the Nevada Test Site (NTS), and implementing a corrective action closure strategy. The UGTA strategy is based on a combination of characterization, modeling studies, monitoring, and institutional controls (i.e., monitored natural attenuation). The closure strategy verifies through appropriate monitoring activities that contaminants of concern do not exceed the SDWA at the regulatory boundary and that adequate institutional controls are established and administered to ensure protection of the public. Other programs conducted at the NNSS supporting the environmental mission include the Routine Radiological Environmental Monitoring Program (RREMP), Waste Management, and the Infrastructure Program. Given the current programmatic and operational demands for various water-monitoring activities at the same locations, and the ever-increasing resource challenges, cooperative and collaborative approaches to conducting the work are necessary. For this reason, an integrated sampling plan is being developed by the UGTA activity to define sampling and analysis objectives, reduce duplication, eliminate unnecessary activities, and minimize costs. The sampling plan will ensure the right data sets are developed to support closure and efficient transition to long-term monitoring. The plan will include an integrated reporting mechanism for communicating results and integrating process improvements within the UGTA activity as well as between other U.S. Department of Energy (DOE) Programs.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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-absorption effects. The microscopy analysis compares different filter loadings and shows that smaller particle sizes (under 10 micron) can readily be seen on the more lightly loaded filters. At higher loadings, however, the particle size is harder to differentiate. This study provides data on actual stack emission samples showing a range of mass loading conditions and visual evidence of particle size and distribution and also presents the difficulties in quantifying self-absorption effects using actual samples.

  4. 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 weapons testing at that time. The age results for this component are in agreement using both {sup 242}Pu and {sup 151}Sm normalizations, although the errors for the {sup 151}Sm correction are currently larger due to the greater uncertainty of their measurements. Additional efforts to develop a concordant {sup 241}Pu-{sup 241}Am dating method for environmental collections are underway with emphasis on soil cores.

  5. 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.

  6. 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.

  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 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. Microsoft Word - S05869_2009SampleResultsRpt.doc

    Office of Legacy Management (LM)

    Hydrologic and Natural Gas Sampling and Analysis Results for 2009 November 2009 Approved for public release; further dissemination unlimited LMS/GSB/S05869 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a

  14. 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.

  15. 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.

  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. Geochemical and isotopic results for groundwater, drainage waters, snowmelt, permafrost, precipitation in Barrow, Alaska (USA) 2012-2013

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Wilson, Cathy; Newman, Brent; Heikoop, Jeff

    Data include a large suite of analytes (geochemical and isotopic) for samples collected in Barrow, Alaska (2012-2013). Sample types are indicated, and include soil pore waters, drainage waters, snowmelt, precipitation, and permafrost samples.

  18. Geochemical and isotopic results for groundwater, drainage waters, snowmelt, permafrost, precipitation in Barrow, Alaska (USA) 2012-2013

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Wilson, Cathy; Newman, Brent; Heikoop, Jeff

    2012-07-18

    Data include a large suite of analytes (geochemical and isotopic) for samples collected in Barrow, Alaska (2012-2013). Sample types are indicated, and include soil pore waters, drainage waters, snowmelt, precipitation, and permafrost samples.

  19. Analysis of deformed palladium cathodes resulting from heavy water electrolysis

    SciTech Connect (OSTI)

    An, H.K.; Jeong, E.J.; Hong, J.H.; Lee, Y.

    1995-07-01

    Earlier experiments suggested that large differences in heat release between the two sides of a palladium electrode coated with gold on one side and manganese oxide on the other cause observed electrode deformation with high-pressure D{sub 2} gas loading in an electrolysis-like cell. Similar experiments were repeated using heavy water electrolysis. Palladium/titanium coatings on one side and gold coating on the other were made for the preparation of the palladium electrodes. Biaxial bending, partial discoloration, and microcracks of palladium electrodes were observed after 18 days of electrolysis. Analysis of the deformed palladium cathodes was performed. It was discovered that to convert this configuration to a practical energy-producing cell, a coating technique must be found to reduce outward diffusion of deuterium, i.e., to maintain a high D/Pd ratio over longer periods of time. 33 refs., 7 figs., 1 tab.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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}.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. Analytical Data Report of Water Samples Collected For I-129 Analysis

    SciTech Connect (OSTI)

    Lindberg, Michael J.

    2009-10-26

    This is an analytical data report for samples received from the central plateau contractor. The samples were analyzed for iodine-129.

  6. A suspended-particle rosette multi-sampler for discrete biogeochemical sampling in low-particle-density waters

    SciTech Connect (OSTI)

    Breier, J. A.; Rauch, C. G.; McCartney, K.; Toner, B. M.; Fakra, S. C.; White, S. N.; German, C. R.

    2010-06-22

    To enable detailed investigations of early stage hydrothermal plume formation and abiotic and biotic plume processes we developed a new oceanographic tool. The Suspended Particulate Rosette sampling system has been designed to collect geochemical and microbial samples from the rising portion of deep-sea hydrothermal plumes. It can be deployed on a remotely operated vehicle for sampling rising plumes, on a wire-deployed water rosette for spatially discrete sampling of non-buoyant hydrothermal plumes, or on a fixed mooring in a hydrothermal vent field for time series sampling. It has performed successfully during both its first mooring deployment at the East Pacific Rise and its first remotely-operated vehicle deployments along the Mid-Atlantic Ridge. It is currently capable of rapidly filtering 24 discrete large-water-volume samples (30-100 L per sample) for suspended particles during a single deployment (e.g. >90 L per sample at 4-7 L per minute through 1 {mu}m pore diameter polycarbonate filters). The Suspended Particulate Rosette sampler has been designed with a long-term goal of seafloor observatory deployments, where it can be used to collect samples in response to tectonic or other events. It is compatible with in situ optical sensors, such as laser Raman or visible reflectance spectroscopy systems, enabling in situ particle analysis immediately after sample collection and before the particles alter or degrade.

  7. June-July 2015 Groundwater and Surface Water Sampling at the Old and New Rifle, Colorado, Processing Sites

    Office of Legacy Management (LM)

    June-July 2015 Groundwater and Surface Water Sampling at the Old and New Rifle, Colorado, Processing Sites November 2015 LMS/RFL/S00615 This page intentionally left blank U.S. Department of Energy DVP-June and July 2015, Old and New Rifle, Colorado November 2015 RINs 15067100, 15067101, and 15077206 Page i Contents Sampling Event Summary ...............................................................................................................1 New Rifle, Colorado, Processing Site, Planned

  8. April 2012 Groundwater and Surface Water Sampling at the Salmon, Mississippi, Site (Data Validation Package)

    SciTech Connect (OSTI)

    2012-10-12

    Sampling and analysis were conducted on April 16-19, 2012, as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office Of Legacy Management Sites (LMS/PLN/S04351, continually updated). Duplicate samples were collected from locations SA1-1-H, HMH-5R, SA3-4-H, SA1-2-H, Pond W of GZ, and SA5-4-4. One trip blank was collected during this sampling event.

  9. Evaluation of repeated measurements of radon-222 concentrations in well water sampled from bedrock aquifers of the Piedmont near Richmond, Virginia, USA: Effects of lithology and well characteristics

    SciTech Connect (OSTI)

    Harris, Shelley A. . E-mail: saharris@vcu.edu; Billmeyer, Ernest R.; Robinson, Michael A.

    2006-07-15

    Radon ({sup 222}Rn) concentrations in 26 ground water wells of two distinct lithologies in the Piedmont of Virginia were measured to assess variation in ground water radon concentrations (GWRC), to evaluate differences in concentrations related to well characteristics, lithology, and spatial distributions, and to assess the feasibility of predicting GWRC. Wells were sampled in accordance with American Public Health Association Method 7500 Rn-B, with modifications to include a well shaft profile analysis that determined the minimum purge time sufficient to remove the equivalent of one column of water from each well. Statistically significant differences in GWRC were found in the Trssu (1482{+-}1711 pCi/L) and Mpg (7750{+-}5188 pCi/L) lithologies, however, no significant differences were found among GWRC at each well over time. Using multiple regression, 86% of the variability (R {sup 2}) in the GWRC was explained by the lithology, latitudinal class, and water table elevation of the wells. The GWRC in a majority of the wells studied exceed US Environmental Protection Agency designated maximum contaminant level and AMCL. Results support modifications to sampling procedures and indicate that, in previous studies, variations in GWRC concentrations over time may have been due in part to differences in sampling procedures and not in source water.

  10. Sampling and analysis plan for treatment water and creek water for the Lower East Fork Poplar Creek Operable Unit, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    This document provides the Environmental Restoration Program with information about the methodology, organizational structure, quality assurance and health and safety practices to be employed during the water sampling and analysis activities associated with the remediation of the Lower East Fork Poplar Creek Operable Unit during remediation of the National Oceanic and Atmospheric Administration and Bruner sites.

  11. Water-Gas Samples At Long Valley Caldera Area (Goff & Janik,...

    Open Energy Info (EERE)

    Area (Goff & Janik, 2002) Redirect page Jump to: navigation, search REDIRECT Surface Gas Sampling At Long Valley Caldera Area (Goff & Janik, 2002) Retrieved from "http:...

  12. 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.

  13. Evaluation of an ambient air sampling system for tritium (as tritiated water vapor) using silica gel adsorbent columns

    SciTech Connect (OSTI)

    Patton, G.W.; Cooper, A.T.; Tinker, M.R.

    1995-08-01

    Ambient air samples for tritium analysis (as the tritiated water vapor [HTO] content of atmospheric moisture) are collected for the Hanford Site Surface Environmental Surveillance Project (SESP) using the solid adsorbent silica gel. The silica gel has a moisture sensitive indicator which allows for visual observation of moisture movement through a column. Despite using an established method, some silica gel columns showed a complete change in the color indicator for summertime samples suggesting that breakthrough had occurred; thus a series of tests was conducted on the sampling system in an environmental chamber. The purpose of this study was to determine the maximum practical sampling volume and overall collection efficiency for water vapor collected on silica gel columns. Another purpose was to demonstrate the use of an impinger-based system to load water vapor onto silica gel columns to provide realistic analytical spikes and blanks for the Hanford Site SESP. Breakthrough volumes (V{sub b}) were measured and the chromatographic efficiency (expressed as the number of theoretical plates [N]) was calculated for a range of environmental conditions. Tests involved visual observations of the change in the silica gel`s color indicator as a moist air stream was drawn through the column, measurement of the amount of a tritium tracer retained and then recovered from the silica gel, and gravimetric analysis for silica gel columns exposed in the environmental chamber.

  14. 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.

  15. Monte Carlo electron-photon transport using GPUs as an accelerator: Results for a water-aluminum-water phantom

    SciTech Connect (OSTI)

    Su, L.; Du, X.; Liu, T.; Xu, X. G.

    2013-07-01

    An electron-photon coupled Monte Carlo code ARCHER - Accelerated Radiation-transport Computations in Heterogeneous Environments - is being developed at Rensselaer Polytechnic Institute as a software test bed for emerging heterogeneous high performance computers that utilize accelerators such as GPUs. In this paper, the preliminary results of code development and testing are presented. The electron transport in media was modeled using the class-II condensed history method. The electron energy considered ranges from a few hundred keV to 30 MeV. Moller scattering and bremsstrahlung processes above a preset energy were explicitly modeled. Energy loss below that threshold was accounted for using the Continuously Slowing Down Approximation (CSDA). Photon transport was dealt with using the delta tracking method. Photoelectric effect, Compton scattering and pair production were modeled. Voxelised geometry was supported. A serial ARHCHER-CPU was first written in C++. The code was then ported to the GPU platform using CUDA C. The hardware involved a desktop PC with an Intel Xeon X5660 CPU and six NVIDIA Tesla M2090 GPUs. ARHCHER was tested for a case of 20 MeV electron beam incident perpendicularly on a water-aluminum-water phantom. The depth and lateral dose profiles were found to agree with results obtained from well tested MC codes. Using six GPU cards, 6x10{sup 6} histories of electrons were simulated within 2 seconds. In comparison, the same case running the EGSnrc and MCNPX codes required 1645 seconds and 9213 seconds, respectively, on a CPU with a single core used. (authors)

  16. Water Use in Parabolic Trough Power Plants: Summary Results from WorleyParsons' Analyses

    SciTech Connect (OSTI)

    Turchi, C. S.; Wagner, M. J.; Kutscher, C. F.

    2010-12-01

    The National Renewable Energy Laboratory (NREL) contracted with WorleyParsons Group, Inc. to examine the effect of switching from evaporative cooling to alternative cooling systems on a nominal 100-MW parabolic trough concentrating solar power (CSP) plant. WorleyParsons analyzed 13 different cases spanning three different geographic locations (Daggett, California; Las Vegas, Nevada; and Alamosa, Colorado) to assess the performance, cost, and water use impacts of switching from wet to dry or hybrid cooling systems. NREL developed matching cases in its Solar Advisor Model (SAM) for each scenario to allow for hourly modeling and provide a comparison to the WorleyParsons results.Our findings indicate that switching from 100% wet to 100% dry cooling will result in levelized cost of electricity (LCOE) increases of approximately 3% to 8% for parabolic trough plants throughout most of the southwestern United States. In cooler, high-altitude areas like Colorado's San Luis Valley, WorleyParsons estimated the increase at only 2.5%, while SAM predicted a 4.4% difference. In all cases, the transition to dry cooling will reduce water consumption by over 90%. Utility time-of-delivery (TOD) schedules had similar impacts for wet- and dry-cooled plants, suggesting that TOD schedules have a relatively minor effect on the dry-cooling penalty.

  17. 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.

  18. Stable water isotope simulation by current land-surface schemes:Results of IPILPS phase 1

    SciTech Connect (OSTI)

    Henderson-Sellers, A.; Fischer, M.; Aleinov, I.; McGuffie, K.; Riley, W.J.; Schmidt, G.A.; Sturm, K.; Yoshimura, K.; Irannejad, P.

    2005-10-31

    Phase 1 of isotopes in the Project for Intercomparison of Land-surface Parameterization Schemes (iPILPS) compares the simulation of two stable water isotopologues ({sup 1}H{sub 2} {sup 18}O and {sup 1}H{sup 2}H{sup 16}O) at the land-atmosphere interface. The simulations are off-line, with forcing from an isotopically enabled regional model for three locations selected to offer contrasting climates and ecotypes: an evergreen tropical forest, a sclerophyll eucalypt forest and a mixed deciduous wood. Here we report on the experimental framework, the quality control undertaken on the simulation results and the method of intercomparisons employed. The small number of available isotopically-enabled land-surface schemes (ILSSs) limits the drawing of strong conclusions but, despite this, there is shown to be benefit in undertaking this type of isotopic intercomparison. Although validation of isotopic simulations at the land surface must await more, and much more complete, observational campaigns, we find that the empirically-based Craig-Gordon parameterization (of isotopic fractionation during evaporation) gives adequately realistic isotopic simulations when incorporated in a wide range of land-surface codes. By introducing two new tools for understanding isotopic variability from the land surface, the Isotope Transfer Function and the iPILPS plot, we show that different hydrological parameterizations cause very different isotopic responses. We show that ILSS-simulated isotopic equilibrium is independent of the total water and energy budget (with respect to both equilibration time and state), but interestingly the partitioning of available energy and water is a function of the models' complexity.

  19. Comparing Simulation Results with Traditional PRA Model on a Boiling Water Reactor Station Blackout Case Study

    SciTech Connect (OSTI)

    Zhegang Ma; Diego Mandelli; Curtis Smith

    2011-07-01

    A previous study used RELAP and RAVEN to conduct a boiling water reactor station black-out (SBO) case study in a simulation based environment to show the capabilities of the risk-informed safety margin characterization methodology. This report compares the RELAP/RAVEN simulation results with traditional PRA model results. The RELAP/RAVEN simulation run results were reviewed for their input parameters and output results. The input parameters for each simulation run include various timing information such as diesel generator or offsite power recovery time, Safety Relief Valve stuck open time, High Pressure Core Injection or Reactor Core Isolation Cooling fail to run time, extended core cooling operation time, depressurization delay time, and firewater injection time. The output results include the maximum fuel clad temperature, the outcome, and the simulation end time. A traditional SBO PRA model in this report contains four event trees that are linked together with the transferring feature in SAPHIRE software. Unlike the usual Level 1 PRA quantification process in which only core damage sequences are quantified, this report quantifies all SBO sequences, whether they are core damage sequences or success (i.e., non core damage) sequences, in order to provide a full comparison with the simulation results. Three different approaches were used to solve event tree top events and quantify the SBO sequences: “W” process flag, default process flag without proper adjustment, and default process flag with adjustment to account for the success branch probabilities. Without post-processing, the first two approaches yield incorrect results with a total conditional probability greater than 1.0. The last approach accounts for the success branch probabilities and provides correct conditional sequence probabilities that are to be used for comparison. To better compare the results from the PRA model and the simulation runs, a simplified SBO event tree was developed with only four top events and eighteen SBO sequences (versus fifty-four SBO sequences in the original SBO model). The estimated SBO sequence conditional probabilities from the original SBO model were integrated to the corresponding sequences in the simplified SBO event tree. These results were then compared with the simulation run results.

  20. 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).

  1. 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.

  2. 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.

  3. Y-12 Groundwater Protection Program Groundwater And Surface Water Sampling And Analysis Plan For Calendar Year 2012

    SciTech Connect (OSTI)

    Elvado Environmental, LLC

    2011-09-01

    This plan provides a description of the groundwater and surface water quality monitoring activities planned for calendar year (CY) 2012 at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) that will be managed by the Y-12 Groundwater Protection Program (GWPP). Groundwater and surface water monitoring performed by the GWPP during CY 2012 is in accordance with the following goals: (1) to protect the worker, the public, and the environment; (2) to maintain surveillance of existing and potential groundwater contamination sources; (3) to provide for the early detection of groundwater contamination and determine the quality of groundwater and surface water where contaminants are most likely to migrate beyond the Oak Ridge Reservation property line; (4) to identify and characterize long-term trends in groundwater quality at Y-12; and (5) to provide data to support decisions concerning the management and protection of groundwater resources. Groundwater and surface water monitoring will be performed in three hydrogeologic regimes at Y-12: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), and the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek and East Fork regimes are located in Bear Creek Valley and the Chestnut Ridge Regime is located south of Y-12 (Figure A.1). Additional surface water monitoring will be performed north of Pine Ridge along the boundary of the Oak Ridge Reservation. Modifications to the CY 2012 monitoring program may be necessary during implementation. Changes in programmatic requirements may alter the analytes specified for selected monitoring wells or may add or remove wells from the planned monitoring network. Each modification to the monitoring program will be approved by the Y-12 GWPP manager and documented as an addendum to this sampling and analysis plan. The following sections of this report provide details regarding the CY 2012 groundwater and surface water monitoring activities. Section 2 describes the monitoring locations in each regime and the processes used to select the sampling locations. A description of the field measurements and laboratory analytes is provided in Section 3. Sample collection methods and procedures are described in Section 4, and Section 5 lists the documents cited for more detailed operational and technical information. The narrative sections of the report reference several appendices. Figures (maps and diagrams) and tables (excluding a data summary table presented in Section 4) are in Appendix A and Appendix B, respectively. Groundwater Monitoring Schedules (when issued throughout CY 2012) will be inserted in Appendix C, and addenda to this plan (if issued) will be inserted in Appendix D. Laboratory requirements (bottle lists, holding times, etc.) are provided in Appendix E, and an approved Waste Management Plan is provided in Appendix F.

  4. Side-by-Side Testing of Water Heating Systems: Results from the 2009-2010 Evaluation

    Broader source: Energy.gov [DOE]

    The performance of seven differing types of residential water heating systems was compared in a side-by-side test configuration over a full year period. The Hot Water System Laboratory (HWS Lab) test facility at the Florida Solar Energy Center (FSEC) in Cocoa, FL was used for the tests.

  5. Performance of Charcoal Cookstoves for Haiti Part 1: Results from the Water Boiling Test

    SciTech Connect (OSTI)

    Booker, Kayje; Han, Tae Won; Granderson, Jessica; Jones, Jennifer; Lsk, Kathleen; Yang, Nina; Gadgil, Ashok

    2011-06-01

    In April 2010, a team of scientists and engineers from Lawrence Berkeley National Lab (LBNL) and UC Berkeley, with support from the Darfur Stoves Project (DSP), undertook a fact-finding mission to Haiti in order to assess needs and opportunities for cookstove intervention. Based on data collected from informal interviews with Haitians and NGOs, the team, Scott Sadlon, Robert Cheng, and Kayje Booker, identified and recommended stove testing and comparison as a high priority need that could be filled by LBNL. In response to that recommendation, five charcoal stoves were tested at the LBNL stove testing facility using a modified form of version 3 of the Shell Foundation Household Energy Project Water Boiling Test (WBT). The original protocol is available online. Stoves were tested for time to boil, thermal efficiency, specific fuel consumption, and emissions of CO, CO{sub 2}, and the ratio of CO/CO{sub 2}. In addition, Haitian user feedback and field observations over a subset of the stoves were combined with the experiences of the laboratory testing technicians to evaluate the usability of the stoves and their appropriateness for Haitian cooking. The laboratory results from emissions and efficiency testing and conclusions regarding usability of the stoves are presented in this report.

  6. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Central Nevada Test Area March 2014 Approved for public release; further dissemination unlimited LMS/CNT/S01113 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy

  7. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Gnome-Coach, New Mexico, Site October 2013 LMS/GNO/S00113 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  8. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Gnome-Coach, New Mexico, Site July 2014 LMS/GNO/S00214 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  9. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Rio Blanco, Colorado, Site February 2014 LMS/RBL/S00509 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  10. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Rio Blanco, Colorado Site October 2013 LMS/RBL/S00513 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  11. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Rulison, Colorado, Site February 2014 LMS/RUL/S00509 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  12. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Rulison, Colorado, Site October 2013 LMS/RUL/S00513 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  13. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Project Shoal, Nevada, Site December 2013 LMS/SHL/S00513 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  14. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Shoal, Nevada, Site July 2014 LMS/SHL/S00514 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of Energy

  15. September 2004 Water Sampling

    Office of Legacy Management (LM)

    Salmon, Mississippi, Site June 2015 LMS/SAL/S01014 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/scitech/ Available for a processing fee to U.S. Department of Energy and its contractors, in paper, from: U.S. Department of

  16. 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.

  17. 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.

  18. Removing Arsenic from Contaminated Drinking Water in Rural Bangladesh: Recent Fieldwork Results and Policy Implications

    SciTech Connect (OSTI)

    Mathieu, Johanna L.; Gadgil, Ashok J.; Kowolik, Kristin; Addy, Susan E.A.

    2009-09-17

    ARUBA (Arsenic Removal Using Bottom Ash) has proven effective at removing high concentrations of arsenic from drinking water in Bangladesh. During fieldwork in four sub-districts of the country, ARUBA reduced arsenic levels ranging from 200 to 900 ppb to below the Bangladesh standard of 50 ppb. The technology is cost-effective because the substrate--bottom ash from coal fired power plants--is a waste material readily available in South Asia. In comparison to similar technologies, ARUBA uses less media for arsenic removal due to its high surface area to volume ratio. Hence, less waste is produced. A number of experiments were conducted in Bangladesh to determine the effectiveness of various water treatment protocols. It was found that (1) ARUBA removes more than half of the arsenic from water within five minutes of treatment, (2) ARUBA, that has settled at the bottom of a treatment vessel, continues to remove arsenic for 2-3 days, (3) ARUBA's arsenic removal efficiency can be improved through sequential partial dosing (adding a given amount of ARUBA in fractions versus all at once), and (4) allowing water to first stand for two to three days followed by treatment with ARUBA produced final arsenic levels ten times lower than treating water directly out of the well. Our findings imply a number of tradeoffs between ARUBA's effective arsenic removal capacity, treatment system costs, and waste output. These tradeoffs, some a function of arsenic-related policies in Bangladesh (e.g., waste disposal regulations), must be considered when designing an arsenic removal system. We propose that the most attractive option is to use ARUBA in communityscale water treatment centers, installed as public-private partnerships, in Bangladeshi villages.

  19. Results of a ground-water and DNAPL recovery and containment strategy

    SciTech Connect (OSTI)

    Mazierski, P.F.; Connor, J.M. )

    1993-10-01

    Ground-water contamination and dense nonaqueous phase liquids (DNAPL) were discovered at the DuPont Necco Park Landfill in Niagara Falls, New York, shortly after the facility was closed in the late 1970s. The facility received a variety of solid and liquid process wastes, including chlorinated volatile and semivolatile organic compounds. A number of proactive response activities--including the operation of a ground-water recovery system, installation of a grout curtain, and DNAPL recovery--were implemented by DuPont concurrent with site characterization. These efforts minimized off-site contaminant migration and removed most of the recoverable free-phase DNAPL prior to completion of the full site characterization. Site investigations to characterize hydrogeologic controls over occurrence and migration of ground water and DNAPL revealed with distinct water-bearing zones beneath the site. A DNAPL recovery program, using gas-driven pump assemblies, was initiated in early 1989 at a small group of wells where DNAPL was frequently observed. The volume of recovered DNAPL declined over the next four years from a peak of 397 gallons per month in 1989 to little or no recovery in recent months.

  20. Modeling transport and dilution of produced water and the resulting uptake and biomagnification in marine biota

    SciTech Connect (OSTI)

    Rye, H.; Reed, M.; Slagstad, D.

    1996-12-31

    The paper explains the numerical modelling efforts undertaken in order to study possible marine biological impacts caused by releases of produced water from the Haltenbanken area outside the western coast of Norway. Acute effects on marine life from releases of produced water appear to be relatively small and confined to areas rather lose to the release site. Biomagnification may however be experienced for relatively low concentrations at larger distances from the release point. Such effects can he modeled by performing a step-wise approach which includes: The use of 3-D hydrodynamic models to determine the ocean current fields; The use of 3-D multi-source numerical models to determine the concentration fields from the produced water releases, given the current field; and The use of biologic models to simulate the behavior of and larvae (passive marine biota) and fish (active marine biota) and their interaction with the concentration field. The paper explains the experiences gained by using this approach for the calculation of possible influences on marine life below the EC{sub 50} or LC{sub 50} concentration levels. The models are used for simulating concentration fields from 5 simultaneous sources at the Haltenbank area and simulation of magnification in some marine species from 2 simultaneous sources in the same area. Naphthalenes and phenols, which are both present in the produced water, were used as the chemical substances in the simulations.

  1. Site characterization summary report for dry weather surface water sampling upper East Fork Poplar Creek characterization area Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-08-01

    This report describes activities associated with conducting dry weather surface water sampling of Upper East Fork Poplar Creek (UEFPC) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. This activity is a portion of the work to be performed at UEFPC Operable Unit (OU) 1 [now known as the UEFPC Characterization Area (CA)], as described in the RCRA Facility Investigation Plan for Group 4 at the Oak- Ridge Y-12 Plant, Oak Ridge, Tennessee and in the Response to Comments and Recommendations on RCRA Facility Investigation Plan for Group 4 at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Volume 1, Operable Unit 1. Because these documents contained sensitive information, they were labeled as unclassified controlled nuclear information and as such are not readily available for public review. To address this issue the U.S. Department of Energy (DOE) published an unclassified, nonsensitive version of the initial plan, text and appendixes, of this Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) Plan in early 1994. These documents describe a program for collecting four rounds of wet weather and dry weather surface water samples and one round of sediment samples from UEFPC. They provide the strategy for the overall sample collection program including dry weather sampling, wet weather sampling, and sediment sampling. Figure 1.1 is a schematic flowchart of the overall sampling strategy and other associated activities. A Quality Assurance Project Plan (QAPJP) was prepared to specifically address four rounds of dry weather surface water sampling and one round of sediment sampling. For a variety of reasons, sediment sampling has not been conducted and has been deferred to the UEFPC CA Remedial Investigation (RI), as has wet weather sampling.

  2. 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.

  3. 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 used to monitor inorganic carryover.

  4. Radiochemical procedures for analysis of Pu, Am, Cs and Sr in water, soil, sediments and biota samples

    SciTech Connect (OSTI)

    Wong, K.M.; Jokela, T.A.; Noshkin, V.E.

    1994-02-01

    The Environmental Radioactivity Analysis Laboratory (ERAL) was established as an analytical facility. The primary function of ERAL is to provide fast and accurate radiological data of environmental samples. Over the years, many radiochemical procedures have been developed by the staffs of ERAL. As result, we have found that our procedures exist in many different formats and in many different notebooks, documents and files. Therefore, in order to provide for more complete and orderly documentation of the radiochemical procedures that are being used by ERAL, we have decided to standardize the format and compile them into a series of reports. This first report covers procedures we have developed and are using for the radiochemical analysis of Pu, Am, Cs, and Sr in various matrices. Additional analytical procedures and/or revisions for other elements will be reported as they become available through continuation of these compilation efforts.

  5. Method for determination of .sup.18 O/.sup.16 O and .sup.2 H/.sup.1 H ratios and .sup.3 H (tritium) concentrations of xylem waters and subsurface waters using time series sampling

    DOE Patents [OSTI]

    Smith, Brian (1126 Delaware St., Berkeley, CA 94702); Menchaca, Leticia (1126 Delaware St., Berkeley, CA 94702)

    1999-01-01

    A method for determination of .sup.18 O/.sup.16 O and .sup.2 H/.sup.1 H ratios and .sup.3 H concentrations of xylem and subsurface waters using time series sampling, insulating sampling chambers, and combined .sup.18 O/.sup.16 O, .sup.2 H/.sup.1 H and .sup.3 H concentration data on transpired water. The method involves collecting water samples transpired from living plants and correcting the measured isotopic compositions of oxygen (.sup.18 O/.sup.16 O) and hydrogen (.sup.2 H/.sup.1 H and/or .sup.3 H concentrations) to account for evaporative isotopic fractionation in the leafy material of the plant.

  6. Y-12 Groundwater Protection Program Groundwater And Surface Water Sampling And Analysis Plan For Calendar Year 2014

    SciTech Connect (OSTI)

    2013-09-01

    This plan provides a description of the groundwater and surface water quality monitoring activities planned for calendar year (CY) 2014 at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) that will be managed by the Y-12 Groundwater Protection Program (GWPP). Groundwater and surface water monitoring is performed by the GWPP during CY 2014 to achieve the following goals: 􀁸 to protect the worker, the public, and the environment; 􀁸 to maintain surveillance of existing and potential groundwater contamination sources; 􀁸 to provide for the early detection of groundwater contamination and determine the quality of groundwater and surface water where contaminants are most likely to migrate beyond the Oak Ridge Reservation property line; 􀁸 to identify and characterize long-term trends in groundwater quality at Y-12; and 􀁸 to provide data to support decisions concerning the management and protection of groundwater resources. Groundwater and surface water monitoring will be performed in three hydrogeologic regimes at Y-12.

  7. Method and apparatus utilizing ionizing and microwave radiation for saturation determination of water, oil and a gas in a core sample

    DOE Patents [OSTI]

    Maerefat, Nicida L. (Sugar Land, TX); Parmeswar, Ravi (Marlton, NJ); Brinkmeyer, Alan D. (Tulsa, OK); Honarpour, Mehdi (Bartlesville, OK)

    1994-01-01

    A system for determining the relative permeabilities of gas, water and oil in a core sample has a microwave emitter/detector subsystem and an X-ray emitter/detector subsystem. A core holder positions the core sample between microwave absorbers which prevent diffracted microwaves from reaching a microwave detector where they would reduce the signal-to-noise ratio of the microwave measurements. The microwave emitter/detector subsystem and the X-ray emitter/detector subsystem each have linear calibration characteristics, allowing one subsystem to be calibrated with respect to the other subsystem. The dynamic range of microwave measurements is extended through the use of adjustable attenuators. This also facilitates the use of core samples with wide diameters. The stratification characteristics of the fluids may be observed with a windowed cell separator at the outlet of the core sample. The condensation of heavy hydrocarbon gas and the dynamic characteristics of the fluids are observed with a sight glass at the outlet of the core sample.

  8. Method and apparatus utilizing ionizing and microwave radiation for saturation determination of water, oil and a gas in a core sample

    DOE Patents [OSTI]

    Maerefat, N.L.; Parmeswar, R.; Brinkmeyer, A.D.; Honarpour, M.

    1994-08-23

    A system is described for determining the relative permeabilities of gas, water and oil in a core sample has a microwave emitter/detector subsystem and an X-ray emitter/detector subsystem. A core holder positions the core sample between microwave absorbers which prevent diffracted microwaves from reaching a microwave detector where they would reduce the signal-to-noise ratio of the microwave measurements. The microwave emitter/detector subsystem and the X-ray emitter/detector subsystem each have linear calibration characteristics, allowing one subsystem to be calibrated with respect to the other subsystem. The dynamic range of microwave measurements is extended through the use of adjustable attenuators. This also facilitates the use of core samples with wide diameters. The stratification characteristics of the fluids may be observed with a windowed cell separator at the outlet of the core sample. The condensation of heavy hydrocarbon gas and the dynamic characteristics of the fluids are observed with a sight glass at the outlet of the core sample. 11 figs.

  9. [Environmental investigation of ground water contamination at Wright-Patterson Air Force Base, Ohio]. Volume 3, Sampling and analysis plan (SAP): Phase 1, Task 4, Field Investigation: Draft

    SciTech Connect (OSTI)

    Not Available

    1991-10-01

    In April 1990, Wright-Patterson Air Force Base (WPAFB), initiated an investigation to evaluate a potential Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) removal action to prevent, to the extent practicable, the offsite migration of contaminated ground water from WPAFB. WPAFB retained the services of the Environmental Management Operations (EMO) and its principle subcontractor, International Technology Corporation (IT) to complete Phase 1 of the environmental investigation of ground-water contamination at WPAFB. Phase 1 of the investigation involves the short-term evaluation and potential design for a program to remove ground-water contamination that appears to be migrating across the western boundary of Area C, and across the northern boundary of Area B along Springfield Pike. Primarily, Task 4 of Phase 1 focuses on collection of information at the Area C and Springfield Pike boundaries of WPAFB. This Sampling and Analysis Plan (SAP) has been prepared to assist in completion of the Task 4 field investigation and is comprised of the Quality Assurance Project Plan (QAPP) and the Field Sampling Plan (FSP).

  10. Search results | Department of Energy

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

    boiling water. Students will compare their two samples on four criteria-color, clarity, smell and taste-rate which they prefer, and graph the results of the experiment as a class....

  11. Search results | Department of Energy

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

    boiling water. Students will compare their two samples on four criteria-color, clarity, smell and taste-rate which they prefer, and graph the results of the experiment as a...

  12. Search results | Department of Energy

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

    tea brewed by boiling water. Students will compare their two samples on four criteria-color, clarity, smell and taste-rate which they prefer, and graph the results of the...

  13. 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.

  14. Colloid characterization and quantification in groundwater samples

    SciTech Connect (OSTI)

    K. Stephen Kung

    2000-06-01

    This report describes the work conducted at Los Alamos National Laboratory for studying the groundwater colloids for the Yucca Mountain Project in conjunction with the Hydrologic Resources Management Program (HRMP) and the Underground Test Area (UGTA) Project. Colloidal particle size distributions and total particle concentration in groundwater samples are quantified and characterized. Colloid materials from cavity waters collected near underground nuclear explosion sites by HRMP field sampling personnel at the Nevada Test Site (NTS) were quantified. Selected colloid samples were further characterized by electron microscope to evaluate the colloid shapes, elemental compositions, and mineral phases. The authors have evaluated the colloid size and concentration in the natural groundwater sample that was collected from the ER-20-5 well and stored in a 50-gallon (about 200-liter) barrel for several months. This groundwater sample was studied because HRMP personnel have identified trace levels of radionuclides in the water sample. Colloid results show that even though the water sample had filtered through a series of Millipore filters, high-colloid concentrations were identified in all unfiltered and filtered samples. They had studied the samples that were diluted with distilled water and found that diluted samples contained more colloids than the undiluted ones. These results imply that colloids are probably not stable during the storage conditions. Furthermore, results demonstrate that undesired colloids have been introduced into the samples during the storage, filtration, and dilution processes. They have evaluated possible sources of colloid contamination associated with sample collection, filtrating, storage, and analyses of natural groundwaters. The effects of container types and sample storage time on colloid size distribution and total concentration were studied to evaluate colloid stability by using J13 groundwater. The data suggests that groundwater samples should be analyzed for colloid size and concentration shortly after they have been collected. A prolonged waiting period after sampling will affect the colloid size distribution as well as colloid concentration resulting from the changes of water chemical properties. The data also shows that sample containers, filter materials, and labware that are used for colloid analyses should be cleaned by specially treated low-colloid-containing water. Water used for sample dilution should be verified for total colloidal particle concentration. They then analyzed freshly collected groundwater from NTS wells ER-20-5{number_sign}1 and {number_sign}3. Results show that these groundwater samples have similar colloid concentrations and particle size distributions. For the particle size range between 50- and 200-nm, about ten trillion (1E10) colloidal particles per liter are present in these water samples. Most of these colloidal particles are less than 100 mm in size. For example, more than 98% of the colloids are smaller than 100 nm in size in the ER-20-5 {number_sign}1 sample. Furthermore, it was found that the smaller the sizes of colloid, the higher the colloid concentration present in the water. For another site at NTS, Cheshire, they had analyzed two zones of groundwater samples. For water samples collected from the lower water zone (near the underground detonation cavity about 3,700 feet of slanted depth from the surface), the colloid concentration was about 5E12 particles per liter. About 20 times less than the lower zone of total colloids was found in water samples collected from the upper aquifer (around 2,511 feet of slanted depth), although colloid size distributions from these two zones appear to be rather similar.

  15. Effect of Fuel Wobbe Number on Pollutant Emissions from Advanced Technology Residential Water Heaters: Results of Controlled Experiments

    SciTech Connect (OSTI)

    Rapp, Vi H.; Singer, Brett C.

    2014-03-01

    The research summarized in this report is part of a larger effort to evaluate the potential air quality impacts of using liquefied natural gas in California. A difference of potential importance between many liquefied natural gas blends and the natural gas blends that have been distributed in California in recent years is the higher Wobbe number of liquefied natural gas. Wobbe number is a measure of the energy delivery rate for appliances that use orifice- or pressure-based fuel metering. The effect of Wobbe number on pollutant emissions from residential water heaters was evaluated in controlled experiments. Experiments were conducted on eight storage water heaters, including five with “ultra low-NO{sub X}” burners, and four on-demand (tankless) water heaters, all of which featured ultra low-NO{sub X} burners. Pollutant emissions were quantified as air-free concentrations in the appliance flue and fuel-based emission factors in units of nanogram of pollutant emitter per joule of fuel energy consumed. Emissions were measured for carbon monoxide (CO), nitrogen oxides (NO{sub X}), nitrogen oxide (NO), formaldehyde and acetaldehyde as the water heaters were operated through defined operating cycles using fuels with varying Wobbe number. The reference fuel was Northern California line gas with Wobbe number ranging from 1344 to 1365. Test fuels had Wobbe numbers of 1360, 1390 and 1420. The most prominent finding was an increase in NO{sub X} emissions with increasing Wobbe number: all five of the ultra low-NO{sub X} storage water heaters and two of the four ultra low-NO{sub X} on-demand water heaters had statistically discernible (p<0.10) increases in NO{sub X} with fuel Wobbe number. The largest percentage increases occurred for the ultra low-NO{sub X} water heaters. There was a discernible change in CO emissions with Wobbe number for all four of the on-demand devices tested. The on-demand water heater with the highest CO emissions also had the largest CO increase with increasing fuel Wobbe number.

  16. Energy - Water Nexus -- Meeting the Energy and Water Needs of the Snake/Columbia River Basin in the 21st CenturyScience and Technology SummitConference Results

    SciTech Connect (OSTI)

    Paul L. Wichlacz; Gerald Sehlke

    2008-02-01

    In June 2007, representatives from federal, state, and academic institutions met to discuss the role of innovative science, technology, and policy in meeting future energy and water demands in the Snake-Columbia River Basin. Conference members assessed the state-of-the-science, technology, and associated research to develop cost-effective and environmentally sound methodologies and technologies to maximize the production of energy and availability of water and to minimize the consumption of both water and energy in the Snake-Columbia River system. Information on all phases of science and technology development, theoretical analysis, laboratory experiments, pilot tests, and field applications were relevant topics for discussion. An overview of current management needs was presented the first day. On the second day, five focus groups were created: ? Energy Generation and Use ? Water Allocation and Use ? Energy/Water Storage ? Environmental Considerations ? Social, Economic, Political, and Regulatory Considerations. Each group started with a list of status items and trends, and discussed the future challenges and research needed to reach four goals: ? Balance energy production and resource consumption ? Balance water availability and competing needs ? Balance water consumption/energy production and competing needs ? Balance environmental impacts and water use/energy production ? Balance costs and benefits of water use. The resulting initiatives were further broken down into three categories of importance: critical, important, and nice to do but could be delayed. Each initiative was assigned a number of dots to show a more refined ranking. The results of each focus group are given in the pages that follow. These results are intended to help local and regional researchers 1. Develop a technical strategy for developing cost-effective science and technology to predict, measure, monitor, purify, conserve, and store water and to maximize power generation, storage, and efficiency in the region 2. Evaluate methods and technologies for reducing the impacts of energy and water development and use on the environment.

  17. Cerro Grande Fire Impact to Water Quality and Stream Flow near Los Alamos National Laboratory: Results of Four Years of Monitoring

    SciTech Connect (OSTI)

    B.M. Gallaher; R.J. Koch

    2004-09-15

    In May 2000, the Cerro Grande fire burned about 7400 acres of mixed conifer forest on the Los Alamos National Laboratory (LANL), and much of the 10,000 acres of mountainside draining onto LANL was severely burned. The resulting burned landscapes raised concerns of increased storm runoff and transport of contaminants by runoff in the canyons traversing LANL. The first storms after the fire produced runoff peaks that were more than 200 times greater than prefire levels. Total runoff volume for the year 2000 increased 50% over prefire years, despite a decline in total precipitation of 13% below normal and a general decrease in the number of monsoonal thunderstorms. The majority of runoff in 2000 occurred in the canyons at LANL south of Pueblo Canyon (70%), where the highest runoff volume occurred in Water Canyon and the peak discharge occurred in Pajarito Canyon. This report describes the observed effects of the Cerro Grande fire and related environmental impacts to watersheds at and near Los Alamos National Laboratory (LANL) for the first four runoff seasons after the fire, from 2000 through 2003. Spatial and temporal trends in radiological and chemical constituents that were identified as being associated with the Cerro Grande fire and those that were identified as being associated with historic LANL discharges are evaluated with regard to impacts to the Rio Grande and area reservoirs downstream of LANL. The results of environmental sampling performed by LANL, the New Mexico Environment Department (NMED), and U.S. Geological Survey (USGS) after the Cerro Grande fire are included in the evaluation. Effects are described for storm runoff, baseflow, stream sediments, and area regional reservoir sediment.

  18. 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

  19. 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.

  20. 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.

  1. Light Water Reactor Sustainability Program: Computer-based procedure for field activities: results from three evaluations at nuclear power plants

    SciTech Connect (OSTI)

    Oxstrand, Johanna; Bly, Aaron; LeBlanc, Katya

    2014-09-01

    Nearly all activities that involve human interaction with the systems of a nuclear power plant are guided by procedures. The paper-based procedures (PBPs) currently used by industry have a demonstrated history of ensuring safety; however, improving procedure use could yield tremendous savings in increased efficiency and safety. One potential way to improve procedure-based activities is through the use of computer-based procedures (CBPs). Computer-based procedures provide the opportunity to incorporate context driven job aids, such as drawings, photos, just-in-time training, etc into CBP system. One obvious advantage of this capability is reducing the time spent tracking down the applicable documentation. Additionally, human performance tools can be integrated in the CBP system in such way that helps the worker focus on the task rather than the tools. Some tools can be completely incorporated into the CBP system, such as pre-job briefs, placekeeping, correct component verification, and peer checks. Other tools can be partly integrated in a fashion that reduces the time and labor required, such as concurrent and independent verification. Another benefit of CBPs compared to PBPs is dynamic procedure presentation. PBPs are static documents which limits the degree to which the information presented can be tailored to the task and conditions when the procedure is executed. The CBP system could be configured to display only the relevant steps based on operating mode, plant status, and the task at hand. A dynamic presentation of the procedure (also known as context-sensitive procedures) will guide the user down the path of relevant steps based on the current conditions. This feature will reduce the user’s workload and inherently reduce the risk of incorrectly marking a step as not applicable and the risk of incorrectly performing a step that should be marked as not applicable. As part of the Department of Energy’s (DOE) Light Water Reactors Sustainability Program, researchers at Idaho National Laboratory (INL) along with partners from the nuclear industry have been investigating the design requirements for computer-based work instructions (including operations procedures, work orders, maintenance procedures, etc.) to increase efficiency, safety, and cost competitiveness of existing light water reactors.

  2. 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).

  3. PPPL News sample:

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

    News sample:

  4. 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

  5. Groundwater Sampling | Open Energy Information

    Open Energy Info (EERE)

    500 mL), whereas analysis for stable isotopes that are present in greater abundance in natural samples requires less water to be sampled by a full order of magnitude (approximately...

  6. 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...

  7. Feasibility assessment of the water energy resources of the United States for new low power and small hydro classes of hydroelectric plants: Appendix B - Assessment results by state

    SciTech Connect (OSTI)

    Hall, Douglas

    2006-01-01

    Water energy resource sites identified in the resource assessment study reported in Water Energy Resources of the United States with Emphasis on Low Head/Low Power Resources, DOE/ID-11111, April 2004 were evaluated to identify which could feasibly be developed using a set of feasibility criteria. The gross power potential of the sites estimated in the previous study was refined to determine the realistic hydropower potential of the sites using a set of development criteria assuming they are developed as low power (less than 1 MWa) or small hydro (between 1 and 30 MWa) projects. The methodologies for performing the feasibility assessment and estimating hydropower potential are described. The results for the country in terms of the number of feasible sites, their total gross power potential, and their total hydropower potential are presented. The spatial distribution of the feasible potential projects is presented on maps of the conterminous U.S. and Alaska and Hawaii. Results summaries for each of the 50 states are presented in Appendix B. The results of the study are also viewable using a Virtual Hydropower Prospector geographic information system application accessible on the Internet at: http://hydropower.inl.gov/prospector.

  8. Category:Field Sampling | Open Energy Information

    Open Energy Info (EERE)

    Technique Subcategories This category has the following 2 subcategories, out of 2 total. G + Gas Sampling (3 categories) 4 pages W + Water Sampling (2 categories) 3...

  9. Sampling box

    DOE Patents [OSTI]

    Phillips, Terrance D. (617 Chestnut Ct., Aiken, SC 29803); Johnson, Craig (100 Midland Rd., Oak Ridge, TN 37831-0895)

    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.

  10. Computation Results from a Parametric Study to Determine Bounding Critical Systems of Homogeneously Water-Moderated Mixed Plutonium--Uranium Oxides

    SciTech Connect (OSTI)

    Shimizu, Y.

    2001-01-11

    This report provides computational results of an extensive study to examine the following: (1) infinite media neutron-multiplication factors; (2) material bucklings; (3) bounding infinite media critical concentrations; (4) bounding finite critical dimensions of water-reflected and homogeneously water-moderated one-dimensional systems (i.e., spheres, cylinders of infinite length, and slabs that are infinite in two dimensions) that were comprised of various proportions and densities of plutonium oxides and uranium oxides, each having various isotopic compositions; and (5) sensitivity coefficients of delta k-eff with respect to critical geometry delta dimensions were determined for each of the three geometries that were studied. The study was undertaken to support the development of a standard that is sponsored by the International Standards Organization (ISO) under Technical Committee 85, Nuclear Energy (TC 85)--Subcommittee 5, Nuclear Fuel Technology (SC 5)--Working Group 8, Standardization of Calculations, Procedures and Practices Related to Criticality Safety (WG 8). The designation and title of the ISO TC 85/SC 5/WG 8 standard working draft is WD 14941, ''Nuclear energy--Fissile materials--Nuclear criticality control and safety of plutonium-uranium oxide fuel mixtures outside of reactors.'' Various ISO member participants performed similar computational studies using their indigenous computational codes to provide comparative results for analysis in the development of the standard.

  11. 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.

  12. Sampling apparatus

    DOE Patents [OSTI]

    Gordon, Norman R. (Kennewick, WA); King, Lloyd L. (Benton, WA); Jackson, Peter O. (Richland, WA); Zulich, Alan W. (Bel Air, MD)

    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.

  13. Search results | Department of Energy

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

    energy-moving-water-11-activities Current search Search found 1 item Electricity Remove Electricity filter Water Remove Water filter Filter by Resource Type All Results (1)...

  14. Search results | Department of Energy

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

    energy-moving-water-11-activities Current search Search found 1 item Water Remove Water filter Electricity Remove Electricity filter Filter by Resource Type All Results (1)...

  15. Environmental surveillance master sampling schedule

    SciTech Connect (OSTI)

    Bisping, L.E.

    1995-02-01

    Environmental surveillance of the Hanford Site and surrounding areas is conducted by the Pacific Northwest Laboratory (PNL) for the U.S. Department of Energy (DOE). This document contains the planned 1994 schedules for routine collection of samples for the Surface Environmental Surveillance Project (SESP), Drinking Water Project, and Ground-Water Surveillance Project. Samples are routinely collected for the SESP and analyzed to determine the quality of air, surface water, soil, sediment, wildlife, vegetation, foodstuffs, and farm products at Hanford Site and surrounding communities. The responsibility for monitoring onsite drinking water falls outside the scope of the SESP. PNL conducts the drinking water monitoring project concurrent with the SESP to promote efficiency and consistency, utilize expertise developed over the years, and reduce costs associated with management, procedure development, data management, quality control, and reporting. The ground-water sampling schedule identifies ground-water sampling .events used by PNL for environmental surveillance of the Hanford Site. Sampling is indicated as annual, semi-annual, quarterly, or monthly in the sampling schedule. Some samples are collected and analyzed as part of ground-water monitoring and characterization programs at Hanford (e.g. Resources Conservation and Recovery Act (RCRA), Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), or Operational). The number of samples planned by other programs are identified in the sampling schedule by a number in the analysis column and a project designation in the Cosample column. Well sampling events may be merged to avoid redundancy in cases where sampling is planned by both-environmental surveillance and another program.

  16. Monitoring Environmental Recovery at Terminated Produced Water Discharge Sites in Coastal Louisiana Waters

    SciTech Connect (OSTI)

    Continental Shelf Associates, Inc.

    1999-08-16

    This report presents the results of a study of terminated produced water discharge sites in the coastal waters of Louisiana. Environmental recovery at the sites is documented by comparing pre-termination and post-termination (six months and one year) data. Produced water, sediments, and sediment interstitial water samples were analyzed for radionuclides, metals, and hydrocarbons. Benthic infauna were identified from samples collected in the vicinity of the discharge and reference sites. Radium isotope activities were determined in fish and crustacean samples. In addition, an environmental risk assessment is made on the basis of the concentrations of metals and hydrocarbons determined in the samples.

  17. Search results | Department of Energy

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

    results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using either photovoltaics or a...

  18. Search results | Department of Energy

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

    Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using either...

  19. Search results | Department of Energy

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

    4 Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using either...

  20. Search results | Department of Energy

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

    2 Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using either...

  1. Search results | Department of Energy

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

    Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Page Hydropower Basics How does water power energy work? Water turbine http:energy.goveerewater...

  2. Search results | Department of Energy

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

    results Search results Enter terms Search Showing 1 - 1 of 1 result. Page Hydropower Basics How does water power energy work? Water turbine http:energy.goveerewater...

  3. Search results | Department of Energy

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

    Energy Sources Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using either...

  4. Search results | Department of Energy

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

    Hydrogen & Fuel Cells Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using...

  5. Search results | Department of Energy

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

    Storage Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using either...

  6. Search results | Department of Energy

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

    Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Download Electrolysis of Water Students observe the electrolysis of water using either photovoltaics...

  7. Field-deployable, nano-sensing approach for real-time detection of free mercury, speciation and quantification in surface stream waters and groundwater samples at the U.S. Department of Energy contaminated sites

    SciTech Connect (OSTI)

    Campiglia, Andres D.; Hernandez, Florencio E.

    2014-08-28

    The detrimental effects on human health caused by long-term exposure to trace contamination of toxic metals have been documented in numerous epidemiological and toxicological studies. The fact that metals are non-biodegradable and accumulate in the food chain poses a severe threat to the environment and human health. Their monitoring in drinking water, aquatic ecosystems, food and biological fluids samples is then essential for global sustainability. While research efforts employing established methodology continue to advance conceptual/computational models of contaminant behavior, the increasing awareness and public concern with environmental and occupational exposure to toxic metals calls for sensing devices capable to handle on-site elemental analysis in short analysis time. Field analysis with potable methodology prevents unnecessary scrutiny of un-contaminated samples via laboratory-bound methods, reduces analysis cost and expedites turnaround time for decision making and remediation purposes. Of particular toxicological interest are mercury and its species. Mercury is recognized as a major environmental pollution issue. The field-portable sensor developed in this project provides a unique and valuable tool for the on-site, real-time determination of inorganic mercury in surface waters. The ability to perform on-site analysis of mercury should prove useful in remote locations with difficult accessibility. It should facilitate data collection from statistically meaningful population sizes for a better understanding of the dose-effect role and the water-soil-plant-animal-human transfer mechanisms. The acquired knowledge should benefit the development of efficient environmental remediation processes, which is extremely relevant for a globally sustainable environment.

  8. Search results | Department of Energy

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

    Search results Enter terms Search Showing 11 - 20 of 11 results. Page Hydropower Basics How does water power energy work? Water turbine http:energy.goveerewater...

  9. Water Energy Resources of the United States with Emphasis on Low Head/Low Power Resources: Appendix A - Assessment Results by Hydrologic Region

    SciTech Connect (OSTI)

    Hall, Douglas

    2004-04-01

    Analytical assessments of the water energy resources in the 20 hydrologic regions of the United States were performed using state-of-the-art digital elevation models and geographic information system tools. The principal focus of the study was on low head (less than 30 ft)/low power (less than 1 MW) resources in each region. The assessments were made by estimating the power potential of all the stream segments in a region, which averaged 2 miles in length. These calculations were performed using hydrography and hydraulic heads that were obtained from the U.S. Geological Survey’s Elevation Derivatives for National Applications dataset and stream flow predictions from a regression equation or equations developed specifically for the region. Stream segments excluded from development and developed hydropower were accounted for to produce an estimate of total available power potential. The total available power potential was subdivided into high power (1 MW or more), high head (30 ft or more)/low power, and low head/low power total potentials. The low head/low power potential was further divided to obtain the fractions of this potential corresponding to the operating envelopes of three classes of hydropower technologies: conventional turbines, unconventional systems, and microhydro (less than 100 kW). Summing information for all the regions provided total power potential in various power classes for the entire United States. Distribution maps show the location and concentrations of the various classes of low power potential. No aspect of the feasibility of developing these potential resources was evaluated. Results for each of the 20 hydrologic regions are presented in Appendix A

  10. Water Energy Resources of the United States with Emphasis on Low Head/Low Power Resources: Appendix B - Assessment Results by State

    SciTech Connect (OSTI)

    Hall, Douglas

    2004-04-01

    Analytical assessments of the water energy resources in the 20 hydrologic regions of the United States were performed using state-of-the-art digital elevation models and geographic information system tools. The principal focus of the study was on low head (less than 30 ft)/low power (less than 1 MW) resources in each region. The assessments were made by estimating the power potential of all the stream segments in a region, which averaged 2 miles in length. These calculations were performed using hydrography and hydraulic heads that were obtained from the U.S. Geological Survey’s Elevation Derivatives for National Applications dataset and stream flow predictions from a regression equation or equations developed specifically for the region. Stream segments excluded from development and developed hydropower were accounted for to produce an estimate of total available power potential. The total available power potential was subdivided into high power (1 MW or more), high head (30 ft or more)/low power, and low head/low power total potentials. The low head/low power potential was further divided to obtain the fractions of this potential corresponding to the operating envelopes of three classes of hydropower technologies: conventional turbines, unconventional systems, and microhydro (less than 100 kW). Summing information for all the regions provided total power potential in various power classes for the entire United States. Distribution maps show the location and concentrations of the various classes of low power potential. No aspect of the feasibility of developing these potential resources was evaluated. Results for for each of the 50 states are made in Appendix B.

  11. Analytical laboratory and mobile sampling platform

    SciTech Connect (OSTI)

    Stetzenbach, K.; Smiecinski, A.

    1996-04-30

    This is the final report for the Analytical Laboratory and Mobile Sampling Platform project. This report contains only major findings and conclusions resulting from this project. Detailed reports of all activities performed for this project were provided to the Project Office every quarter since the beginning of the project. This report contains water chemistry data for samples collected in the Nevada section of Death Valley National Park (Triangle Area Springs), Nevada Test Site springs, Pahranagat Valley springs, Nevada Test Site wells, Spring Mountain springs and Crater Flat and Amargosa Valley wells.

  12. Search results | Department of Energy

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

    groups conduct an investigation into the similarities and differences between solar tea and tea brewed by boiling water. Students will compare their two samples on four...

  13. CHARACTERIZATION OF TANK 16H ANNULUS SAMPLES

    SciTech Connect (OSTI)

    Hay, M.; Reboul, S.

    2012-04-16

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

  14. DWPF SMECT PVV SAMPLE CHARACTERIZATION AND REMEDIATION

    SciTech Connect (OSTI)

    Bannochie, C.; Crawford, C.

    2013-06-18

    On April 2, 2013, a solid sample of material collected from the Defense Waste Processing Facility’s Process Vessel Vent (PVV) jumper for the Slurry Mix Evaporator Condensate Tank (SMECT) was received at the Savannah River National Laboratory (SRNL). DWPF has experienced pressure spikes within the SMECT and other process vessels which have resulted in processing delays while a vacuum was re-established. Work on this sample was requested in a Technical Assistance Request (TAR). This document reports the results of chemical and physical property measurements made on the sample, as well as insights into the possible impact to the material using DWPF’s proposed remediation methods. DWPF was interested in what the facility could expect when the material was exposed to either 8M nitric acid or 90% formic acid, the two materials they have the ability to flush through the PVV line in addition to process water once the line is capped off during a facility outage.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. Water Analytical Data Tables for 1CQ11.xls

    Office of Legacy Management (LM)

    Analytical Results for Water Samples-First Quarter CY 2011 This page intentionally left blank Appendix C1 Analytical Results for Water Samples - First Quarter CY 2011 LOCATION_CODE LOCATION_TYPE DATE SAMPLED LAB REQUISITION NUMBER CAS ANALYTE SAMPLE ID RESULT UNITS LAB QUALIFIERS SAMPLE TYPE DETECTION LIMIT UNCER- TAINTY DATA VALIDATION QUALIFIERS A4 POND SL 1/12/2011 11013559 NO3+NO2 AS N Nitrate + Nitrite as Nitrogen N001 0.043 mg/L J F 0.019 valid A4 POND SL 1/12/2011 11013559 7440-61-1

  20. Water Analytical Data Tables for 1CQ12.xls

    Office of Legacy Management (LM)

    C Analytical Results for Water Samples-First Quarter CY 2012 This page intentionally left blank Appendix C1 Analytical Results for Water Samples - First Quarter CY 2012 LOCATION_CODE LOCATION_TYPE DATE SAMPLED LAB REQUISITION NUMBER CAS ANALYTE SAMPLE ID RESULT UNITS LAB QUALIFIERS SAMPLE TYPE DETECTION LIMIT UNCER- TAINTY DATA VALIDATION QUALIFIERS 70193 WL 2/16/2012 12024361 71-55-6 1,1,1-Trichloroethane N001 0.16 ug/L U F 0.16 F 70193 WL 2/16/2012 12024361 79-34-5 1,1,2,2-Tetrachloroethane

  1. Amphiphilic mediated sample preparation for micro-flow cytometry

    DOE Patents [OSTI]

    Clague, David S. (Livermore, CA); Wheeler, Elizabeth K. (Livermore, CA); Lee, Abraham P. (Irvine, CA)

    2006-07-25

    A flow cytometer includes a flow cell for detecting the sample, an oil phase in the flow cell, a water phase in the flow cell, an oil-water interface between the oil phase and the water phase, a detector for detecting the sample at the oil-water interface, and a hydrophobic unit operatively connected to the sample. The hydrophobic unit is attached to the sample. The sample and the hydrophobic unit are placed in an oil and water combination. The sample is detected at the interface between the oil phase and the water phase.

  2. Amphiphilic mediated sample preparation for micro-flow cytometry

    DOE Patents [OSTI]

    Clague, David S. (Livermore, CA); Wheeler, Elizabeth K. (Livermore, CA); Lee, Abraham P. (Irvine, CA)

    2009-03-17

    A flow cytometer includes a flow cell for detecting the sample, an oil phase in the flow cell, a water phase in the flow cell, an oil-water interface between the oil phase and the water phase, a detector for detecting the sample at the oil-water interface, and a hydrophobic unit operatively connected to the sample. The hydrophobic unit is attached to the sample. The sample and the hydrophobic unit are placed in an oil and water combination. The sample is detected at the interface between the oil phase and the water phase.

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  7. Gas Sampling At Wister Area (DOE GTP) | Open Energy Information

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  8. Surface Gas Sampling At Lightning Dock Area (Norman & Moore,...

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  9. Gas Sampling At Colrado Area (DOE GTP) | Open Energy Information

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  10. Northern Marshall Islands radiological survey: sampling and analysis summary

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    Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

    1981-07-23

    A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for /sup 241/Am, 6569 for /sup 137/Cs, 4535 for /sup 239 +240/Pu, 4431 for /sup 90/Sr, 1146 for /sup 238/Pu, 269 for /sup 241/Pu, and 114 each for /sup 239/Pu and /sup 240/Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included.

  11. Microsoft Word - S08153_Results

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    Natural Gas and Produced Water Sampling and Analysis Results for 2011 September 2011 Approved for public release; further dissemination unlimited LMS/GSB/S08153 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Road Alexandria, VA 22312 Telephone: 800.553.6847 Fax: 703.605.6900 E-mail: orders@ntis.gov Online Ordering: http://www.ntis.gov/help/ordermethods.aspx Available electronically at http://www.osti.gov/bridge Available

  12. Examination of Hydrate Formation Methods: Trying to Create Representative Samples

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    Kneafsey, T.J.; Rees, E.V.L.; Nakagawa, S.; Kwon, T.-H.

    2011-04-01

    Forming representative gas hydrate-bearing laboratory samples is important so that the properties of these materials may be measured, while controlling the composition and other variables. Natural samples are rare, and have often experienced pressure and temperature changes that may affect the property to be measured [Waite et al., 2008]. Forming methane hydrate samples in the laboratory has been done a number of ways, each having advantages and disadvantages. The ice-to-hydrate method [Stern et al., 1996], contacts melting ice with methane at the appropriate pressure to form hydrate. The hydrate can then be crushed and mixed with mineral grains under controlled conditions, and then compacted to create laboratory samples of methane hydrate in a mineral medium. The hydrate in these samples will be part of the load-bearing frame of the medium. In the excess gas method [Handa and Stupin, 1992], water is distributed throughout a mineral medium (e.g. packed moist sand, drained sand, moistened silica gel, other porous media) and the mixture is brought to hydrate-stable conditions (chilled and pressurized with gas), allowing hydrate to form. This method typically produces grain-cementing hydrate from pendular water in sand [Waite et al., 2004]. In the dissolved gas method [Tohidi et al., 2002], water with sufficient dissolved guest molecules is brought to hydrate-stable conditions where hydrate forms. In the laboratory, this is can be done by pre-dissolving the gas of interest in water and then introducing it to the sample under the appropriate conditions. With this method, it is easier to form hydrate from more soluble gases such as carbon dioxide. It is thought that this method more closely simulates the way most natural gas hydrate has formed. Laboratory implementation, however, is difficult, and sample formation is prohibitively time consuming [Minagawa et al., 2005; Spangenberg and Kulenkampff, 2005]. In another version of this technique, a specified quantity of gas is placed in a sample, then the sample is flooded with water and cooled [Priest et al., 2009]. We have performed a number of tests in which hydrate was formed and the uniformity of the hydrate formation was examined. These tests have primarily used a variety of modifications of the excess gas method to make the hydrate, although we have also used a version of the excess water technique. Early on, we found difficulties in creating uniform samples with a particular sand/ initial water saturation combination (F-110 Sand, {approx} 35% initial water saturation). In many of our tests we selected this combination intentionally to determine whether we could use a method to make the samples uniform. The following methods were examined: Excess gas, Freeze/thaw/form, Freeze/pressurize/thaw, Excess gas followed by water saturation, Excess water, Sand and kaolinite, Use of a nucleation enhancer (SnoMax), and Use of salt in the water. Below, each method, the underlying hypothesis, and our results are briefly presented, followed by a brief conclusion. Many of the hypotheses investigated are not our own, but were presented to us. Much of the data presented is from x-ray CT scanning our samples. The x-ray CT scanner provides a three-dimensional density map of our samples. From this map and the physics that is occurring in our samples, we are able to gain an understanding of the spatial nature of the processes that occur, and attribute them to the locations where they occur.

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