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Note: This page contains sample records for the topic "tanks vaporizer units" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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1

Tank 241-BY-107 vapor sampling and analysis tank characterization report  

DOE Green Energy (OSTI)

Tank 241-BY-107 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in {open_quotes}Program Plan for the Resolution of Tank Vapor Issues{close_quotes}. Tank 241-BY-107 was vapor sampled in accordance with {open_quotes}Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution{close_quotes}.

Huckaby, J.L.

1995-05-05T23:59:59.000Z

2

Tank 241-S-102 vapor sampling and analysis tank characterization report  

DOE Green Energy (OSTI)

Tank 241-S-102 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in {open_quotes}Program Plan for the Resolution of Tank Vapor Issues.{close_quotes} Tank 241-S-102 was vapor sampled in accordance with {open_quotes}Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution. {close_quotes}

Huckaby, J.L.

1995-05-31T23:59:59.000Z

3

Waste tank headspace gas and vapor characterization reference guide  

SciTech Connect

This document is to serve as a reference guide for gas and vapor sample results presented in tank characterization reports. It describes sampling equipment, devices, and protocols, and sample collection and analysis methods common to all vapor samples.

Huckaby, J.L.

1995-06-01T23:59:59.000Z

4

Vapor sampling of the headspace of radioactive waste storage tanks  

DOE Green Energy (OSTI)

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

Reynolds, D.A., Westinghouse Hanford

1996-05-22T23:59:59.000Z

5

EA-0881: Tank 241-c-103 Organic Vapor and Liquid Characterization...  

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

881: Tank 241-c-103 Organic Vapor and Liquid Characterization and Supporting Activities, Hanford Site, Richland, Washington EA-0881: Tank 241-c-103 Organic Vapor and Liquid...

6

Worker Protection from Chemical Vapors: Hanford Tank Farms  

Science Conference Proceedings (OSTI)

Chemical vapor emissions from underground hazardous waste storage tanks on the Hanford site in eastern Washington State are a potential concern because workers enter the tank farms on a regular basis for waste retrievals, equipment maintenance, and surveillance. Tank farm contractors are in the process of retrieving all remaining waste from aging single-shell tanks, some of which date to World War II, and transferring it to newer double-shell tanks. During the waste retrieval process, tank farm workers are potentially exposed to fugitive chemical vapors that can escape from tank head-spaces and other emission points. The tanks are known to hold more than 1,500 different species of chemicals, in addition to radionuclides. Exposure assessments have fully characterized the hazards from chemical vapors in half of the tank farms. Extensive sampling and analysis has been done to characterize the chemical properties of hazardous waste and to evaluate potential health hazards of vapors at the ground surface, where workers perform maintenance and waste transfer activities. Worker concerns, risk communication, and exposure assessment are discussed, including evaluation of the potential hazards of complex mixtures of chemical vapors. Concentrations of vapors above occupational exposure limits (OEL) were detected only at exhaust stacks and passive breather filter outlets. Beyond five feet from the sources, vapors disperse rapidly. No vapors have been measured above 50% of their OELs more than five feet from the source. Vapor controls are focused on limited hazard zones around sources. Further evaluations of vapors include analysis of routes of exposure and thorough analysis of nuisance odors. (authors)

Anderson, T.J. [CH2M HILL Hanford Group, Inc. / Environmental Health, Richland, WA (United States)

2007-07-01T23:59:59.000Z

7

LESSONS LEARNED FROM PREVIOUS WASTE STORAGE TANK VAPOR CONTROL ATTEMPTS ON SINGLE SHELL TANK (SST) & DOUBLE SHELL TANK (DST) FARMS  

Science Conference Proceedings (OSTI)

This report forms the basis for a feasibility study and conceptual design to control vapor emissions from waste storage tanks at the Hanford Site. The Carbtrol, Vapor Mixing, and High Efficiency Gas Absorber (HEGA) vapor controls were evaluated to determine the lessons learned from previous failed vapor control attempts. This document illustrates the resulting findings based on that evaluation.

BAKER, D.M.

2004-08-03T23:59:59.000Z

8

Tank 241-BY-104 vapor sampling and analysis tank characterization report  

DOE Green Energy (OSTI)

Tank BY-104 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-104 using the vapor sampling system (VSS) on June 24, 1994 by WHC Sampling and Mobile Laboratories. Air from the tank BY-104 headspace was withdrawn via a heated sampling probe mounted in riser 10A, and transferred via heated tubing to the VSS sampling manifold. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 46 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 10 trip blanks provided by the laboratories.

Huckaby, J.L.

1995-05-10T23:59:59.000Z

9

Tank 241-C-112 vapor sampling and analysis tank characterization report  

DOE Green Energy (OSTI)

Tank C-112 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank C-112 is a single-shell tank which received first-cycle decontamination waste from B Plant and was later used as a settling tank. Samples were collected from Tank C-112 using the vapor sampling system (VSS) on August 11, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 28 C. Air from the Tank C-112 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 4, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 39 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks provided by the laboratories.

Huckaby, J.L.

1995-05-10T23:59:59.000Z

10

Tank 241-BY-110 vapor sampling and analysis tank characterization report  

DOE Green Energy (OSTI)

Tank BY-110 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-110 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-110 using the vapor sampling system (VSS) on November 11, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 27 C. Air from the Tank BY-110 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 12B, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, and Pacific Northwest Laboratories. The 40 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks that accompanied the samples.

Huckaby, J.L.

1995-05-10T23:59:59.000Z

11

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

12

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

13

Tank 241-BY-108 vapor sampling and analysis tank characterization report  

DOE Green Energy (OSTI)

Tank BY-108 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-108 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-108 using the vapor sampling system (VSS) on october 27, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 25.7 C. Air from the Tank BY-108 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 1, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, and Pacific Northwest Laboratories. The 40 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks that accompanied the samples.

Huckaby, J.L.

1995-05-10T23:59:59.000Z

14

Tank 241-C-111 vapor sampling and analysis tank characterization report  

DOE Green Energy (OSTI)

Tank C-111 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Results presented here represent the best available data on the headspace constituents of Tank C-111. Almost all of the data in this report was obtained from samples collected on September 13, 1994.Data from 2 other sets of samples, collected on August 10, 1993 and June 20, 1994, are in generally good agreement with the more recent data. The tank headspace temperature was determined to be 27 C. Air from the Tank C-111 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 6, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 39 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks provided by the laboratories. Tank C-111 is a single shell tank which received first-cycle decontamination waste from B Plant and was later used as a settling tank.

Huckaby, J.L.

1995-05-10T23:59:59.000Z

15

Tank 241-Z-361 vapor sampling and analysis plan  

Science Conference Proceedings (OSTI)

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

BANNING, D.L.

1999-02-23T23:59:59.000Z

16

EA-0881: Tank 241-c-103 Organic Vapor and Liquid Characterization and  

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

81: Tank 241-c-103 Organic Vapor and Liquid Characterization 81: Tank 241-c-103 Organic Vapor and Liquid Characterization and Supporting Activities, Hanford Site, Richland, Washington EA-0881: Tank 241-c-103 Organic Vapor and Liquid Characterization and Supporting Activities, Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts of a proposal to sample the vapor space and liquid waste and perform other supporting activities in Tank 241-C-103 located in the 241-C Tank Farm on the Hanford Site in Richland, Washington. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 10, 1992 EA-0881: Finding of No Significant Impact Tank 241-c-103 Organic Vapor and Liquid Characterization and Supporting Activities, Hanford Site, Richland, Washington August 10, 1992

17

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

DOE Green Energy (OSTI)

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

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

1996-07-01T23:59:59.000Z

18

Estimation of heat load in waste tanks using average vapor space temperatures  

SciTech Connect

This report describes a method for estimating the total heat load in a high-level waste tank with passive ventilation. This method relates the total heat load in the tank to the vapor space temperature and the depth of waste in the tank. Q{sub total} = C{sub f} (T{sub vapor space {minus}} T{sub air}) where: C{sub f} = Conversion factor = (R{sub o}k{sub soil}{sup *}area)/(z{sub tank} {minus} z{sub surface}); R{sub o} = Ratio of total heat load to heat out the top of the tank (function of waste height); Area = cross sectional area of the tank; k{sub soil} = thermal conductivity of soil; (z{sub tank} {minus} z{sub surface}) = effective depth of soil covering the top of tank; and (T{sub vapor space} {minus} T{sub air}) = mean temperature difference between vapor space and the ambient air at the surface. Three terms -- depth, area and ratio -- can be developed from geometrical considerations. The temperature difference is measured for each individual tank. The remaining term, the thermal conductivity, is estimated from the time-dependent component of the temperature signals coming from the periodic oscillations in the vapor space temperatures. Finally, using this equation, the total heat load for each of the ferrocyanide Watch List tanks is estimated. This provides a consistent way to rank ferrocyanide tanks according to heat load.

Crowe, R.D.; Kummerer, M.; Postma, A.K.

1993-12-01T23:59:59.000Z

19

Sampling and Analysis Plan for Catch Tank 241ER311 Vapor  

Science Conference Proceedings (OSTI)

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

NGUYEN, D.M.

1999-11-15T23:59:59.000Z

20

Screening for organic solvents in Hanford waste tanks using total non- methane organic compound vapor concentrations  

SciTech Connect

The potential ignition of organic liquids stored in the Hanford high-level radioactive waste tanks is a safety issue because expanding gases could affect tank dome integrity. This report presents results of a screening test that was applied to 75 passively ventilated waste tanks at Hanford to determine those that might contain a significant amount of organic liquid waste. The screening test is based on a simple model of tank headspace, headspace organic vapor concentrations, and certain tank physical parameters. Analyses indicate that damage to the tank dome is credible only if the organic liquid burn rate is above a threshold value, and this can occur only if the surface area of organic liquid in a tank is above a corresponding threshold value of about one square meter. Twelve tanks were identified as potentially containing at least that amount of semivolatile organic liquid based on conservative estimates. Tank head space organic vapor concentrations and physical parameters required by the screening test have been compiled and are presented for each of the tanks studied. Estimates of the ventilation rates of the waste tanks were revised to reflect recent information obtained from hydrogen monitoring data. A simple analysis of the uncertainty in the test results suggests that the largest current uncertainty in the estimation of organic liquid surface area is that associated with knowledge of the tank ventilation rate. The uncertainty analysis is applied to determine 95% confidence limits for the estimated organic waste surface area in each tank.

Huckaby, J.L.; Glissmeyer, J.A.; Sklarew, D.S.

1997-02-01T23:59:59.000Z

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


21

Screening for organic solvents in Hanford waste tanks using organic vapor concentrations  

SciTech Connect

The potential ignition of organic liquids stored in the Hanford Site high-level radioactive waste tanks has been identified as a safety issue because expanding gases could potentially affect tank dome integrity. Organic liquid waste has been found in some of the waste tanks, but most are thought to contain only trace amounts. Due to the inhomogeneity of the waste, direct sampling of the tank waste to locate organic liquids may not conclusively demonstrate that a given tank is free of risk. However, organic vapors present above the organic liquid waste can be detected with a high degree of confidence and can be used to identify problem tanks. This report presents the results of a screening test that has been applied to 82 passively ventilated high-level radioactive waste tanks at the Hanford Site to identify those that might contain a significant amount of organic liquid waste. It includes seven tanks not addressed in the previous version of this report, Screening for Organic Solvents in Hanford Waste Tanks Using Total Non-Methane Organic Compound Vapor Concentrations. The screening test is based on a simple model of the tank headspace that estimates the effective surface area of semivolatile organic liquid waste in a tank. Analyses indicate that damage to the tank dome is credible only if the organic liquid burn rate is above a threshold value, and this can occur only if the surface area of organic liquid in a tank is above a corresponding threshold value of about one square meter. Thirteen tanks were identified as potentially containing at least that amount of semivolatile organic liquid based on conservative estimates. Most of the tanks identified as containing potentially significant quantities of organic liquid waste are in the 241-BY and 241-C tank farms, which agrees qualitatively with the fact that these tank farms received the majority of the PUREX process organic wash waste and waste organic liquids.

Huckaby, J.L.; Sklarew, D.S.

1997-09-01T23:59:59.000Z

22

Tank 241-S-102 fifth temporal study: Headspace gas and vapor characterization results from samples collected on February 11, 1997. Tank vapor characterization project  

DOE Green Energy (OSTI)

This report presents tile results from analyses of samples taken from the headspace of waste storage tank 241-S-102 (Tank S-102) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurlsys Service Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by tile Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based oil measured sample volumes provided by SESC. Ammonia was determined to be above tile immediate notification limit of 150 ppm as specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank S-102 headspace, determined to be present at approximately 1.150% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <1.624% of the LFL, Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of tile analytical results are provided in Section 3.0.

Mitroshkov, A.V.; Evans, J.C.; Hayes, J.C. [and others

1997-09-01T23:59:59.000Z

23

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

DOE Green Energy (OSTI)

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

Evans, J.C.; Pool, K.H.; Olsen, K.B. [and others

1997-09-01T23:59:59.000Z

24

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

DOE Green Energy (OSTI)

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

Hayes, J.C.; Pool, K.H.; Evans, J.C. [and others

1997-08-01T23:59:59.000Z

25

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

DOE Green Energy (OSTI)

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

Evans, J.C.; Pool, K.H.; Hayes, J.C. [and others

1997-09-01T23:59:59.000Z

26

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

DOE Green Energy (OSTI)

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

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

1997-07-01T23:59:59.000Z

27

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

DOE Green Energy (OSTI)

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

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

1997-08-01T23:59:59.000Z

28

Tank Vapor Characterization Project: Tank 241-C-107 fourth temporal study: Headspace gas and vapor characterization results from samples collected on December 17, 1996  

DOE Green Energy (OSTI)

This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-C-107 (Tank C-107) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Service Corporation (SESC) and were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. No analytes were determined to be above the immediate notification limits specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank C-107 headspace, determined to be present at approximately 2.825% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <2.935% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

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

1997-08-01T23:59:59.000Z

29

Tank 241-BY-108 fourth temporal study: Headspace gas and vapor characterization results from samples collected on November 14, 1997. Tank vapor characterization project  

DOE Green Energy (OSTI)

This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BY-108 (Tank BY-108) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Service Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected nonradioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by SESC. Ammonia was determined to be above the immediate notification limit of 150 ppm specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BY-108 headspace, determined to be present at approximately 1.390% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <2.830% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

Evans, J.C.; Pool, K.H.; Olsen, K.B. [and others

1997-07-01T23:59:59.000Z

30

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

DOE Green Energy (OSTI)

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

Mitroshkov, A.V.; Hayes, J.C.; Evans, J.C. [and others

1997-09-01T23:59:59.000Z

31

Tank Vapor Characterization Project: Tank 241-BX-103 headspace gas and vapor characterization results from samples collected on August 1, 1996  

DOE Green Energy (OSTI)

This report presents the results from analyses of samples taken from headspace of waste storage tank 241-BX-103 (Tank BX-103) at the Hanford Site in Washington State. Tank headspace samples collected by Westinghouse Hanford Company (WHC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by WHC. No analytes were determined to be above the immediate notification limits specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BX-103 headspace, determined to be present at approximately 0.385% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <0.633% if the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

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

1997-08-01T23:59:59.000Z

32

Tank vapor characterization project: Tank 241-S-102 temporal study headspace gas and vapor characterization results from samples collected on September 19, 1996  

DOE Green Energy (OSTI)

This report presents the results from analysis of samples taken from the headspace of waste storage tank 241-S-102 (Tank S-102) at the Hanford Site in Washington State. Tank headspace samples collected by Westinghouse Hanford Company (WHC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by WHC. Ammonia was determined to be above the immediate notification limit of 150 ppm as specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank S-102 headspace, determined to be present at approximately 2.948% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <3.659% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Tables S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

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

1997-08-01T23:59:59.000Z

33

Tank Vapor Characterization Project: Tank 241-BX-104 second temporal study headspace gas and vapor characterization results from samples collected on December 12, 1996  

DOE Green Energy (OSTI)

This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-BX-104 (Tank BX-104) at the Hanford Site in Washington State. Tank headspace samples collected by SGN Eurisys Service Corporation (SESC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample provided by SESC. Ammonia was determined to be above the immediate notification limit specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank BX-104 headspace, determined to be present at approximately 0.248% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <0.645% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

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

1997-08-01T23:59:59.000Z

34

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

Science Conference Proceedings (OSTI)

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

LOCKREM, L.L.

1999-08-13T23:59:59.000Z

35

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

DOE Green Energy (OSTI)

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

TEMPLETON, A.M.

1999-12-07T23:59:59.000Z

36

Results of Vapor Space Monitoring of Flammable Gas Watch List Tanks  

DOE Green Energy (OSTI)

This report documents the measurement of headspace gas concentrations and monitoring results from the Hanford tanks that have continuous flammable gas monitoring. The systems used to monitor the tanks are Standard Hydrogen Monitoring Systems. Further characterization of the tank off-gases was done with Gas Characterization systems and vapor grab samples. The background concentrations of all tanks are below the action level of 6250 ppm. Other information which can be derived from the measurements (such as generation rate, released rate, and ventilation rate) is also discussed.

MCCAIN, D.J.

2000-09-27T23:59:59.000Z

37

Results of vapor space monitoring of flammable gas Watch List tanks  

DOE Green Energy (OSTI)

This report documents the measurement of headspace gas concentrations and monitoring results from the Hanford tanks that have continuous flammable gas monitoring. The systems used to monitor the tanks are Standard Hydrogen Monitoring Systems. Further characterization of the tank off-gases was done with Gas Characterization Systems and vapor grab samples. The background concentrations of all tanks are below the action level of 6250 ppm. Other information which can be derived from the measurements (such as generation rate, release rate, and ventilation rate) is also discussed.

Wilkins, N.E.

1997-09-18T23:59:59.000Z

38

Experimental and Modeling Study of the Flammability of Fuel Tank Headspace Vapors from High Ethanol Content Fuels  

DOE Green Energy (OSTI)

Study determined the flammability of fuel tank headspace vapors as a function of ambient temperature for seven E85 fuel blends, two types of gasoline, and denatured ethanol at a low tank fill level.

Gardiner, D.; Bardon, M.; Pucher, G.

2008-10-01T23:59:59.000Z

39

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

DOE Green Energy (OSTI)

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

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

1997-08-01T23:59:59.000Z

40

Tank Vapor Characterization Project: Tank 241-C-107 temporal study headspace gas and vapor characterization results from samples collected on September 5, 1996  

DOE Green Energy (OSTI)

This report presents the results from analyses of samples taken from the headspace of waste storage tank 241-C-107 at the Hanford Site in Washington State. Tank headspace samples collected by Westinghouse Hanford Company (WHC) were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Vapor concentrations from sorbent trap samples are based on measured sample volumes provided by WHC. No analytes were determined to be above the immediate notification limits specified by the sampling and analysis plan (SAP). Hydrogen was the principal flammable constituent of the Tank C-107 headspace, determined to be present at approximately 1.405% of its lower flammability limit (LFL). Total headspace flammability was estimated to be <1.519% of the LFL. Average measured concentrations of targeted gases, inorganic vapors, and selected organic vapors are provided in Table S.1. A summary of experimental methods, including sampling methodology, analytical procedures, and quality assurance and control methods are presented in Section 2.0. Detailed descriptions of the analytical results are provided in Section 3.0.

Pool, K.H.; Evans, J.C.; Thomas, B.L.; Edwards, J.A.; Silvers, K.L. [and others

1997-08-01T23:59:59.000Z

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


41

A Survey of Vapors in the Headspaces of Single-Shell Waste Tanks  

SciTech Connect

This report summarizes data on the organic vapors in the single-shell high level radioactive waste tanks at the Hanford site to support a forthcoming toxicological study. All data were obtained from the Tank Characterization Database (PNNL 1999). The TCD contains virtually all the available tank headspace characterization data from 1992 to the present, and includes data for 109 different single-shell waste tanks. Each single-shell tank farm and all major waste types are represented. Descriptions of the sampling and analysis methods have been given elsewhere (Huckaby et al. 1995, Huckaby et al. 1996), and references for specific data are available in the TCD. This is a revision of a report with the same title issued on March 1, 2000 (Stock and Huckaby 2000).

Stock, Leon M.; Huckaby, James L.

2000-10-31T23:59:59.000Z

42

Analysis of vapor samples from the Organice PISA high level waste tanks  

SciTech Connect

Analyses for organic materials in vapor samples taken from the eight High Level Waste tanks (26F, 33F, 46F, 11H, 22H, 32H, 39H, and 43H) have been completed. Of these tanks, 26F, 33F, and 43H are designated 'organic'' tanks. Samples were collected on solvent desorption (SD) tubes (containing activated charcoal) from various heights above the tank waste. Tank ventilation was stopped for one hour prior to sampling and was not reinitiated until sample collection was complete. The results indicate that the concentration of organic materials is extremely low in all samples. Some organic materials were found in the vapor samples but in nanogram/liter (ng/L) quantities. These materials were present in the samples within the practical quantitation limit (PQL), which represents a practical and routinely achievable detection limit with a relatively good certainty that any reported value is reliable. Because of the low levels and the fact that no field background analysis was run (laboratory background analyses were run), the researchers cannot absolutely determine whether the materials were actually taken from the waste tanks or whether they are from environmental background. In any case, the quantities of material found are several orders magnitude below that which would comprise a flammability concern.

Swingle, R.F. II

2000-06-01T23:59:59.000Z

43

Proposed Occupational Exposure Limits for Non-Carcinogenic Hanford Waste Tank Vapor Chemicals  

SciTech Connect

A large number of volatile chemicals have been identified in the headspaces of tanks used to store mixed chemical and radioactive waste at the U.S. Department of Energy (DOE) Hanford Site, and there is concern that vapor releases from the tanks may be hazardous to workers. Contractually established occupational exposure limits (OELs) established by the Occupational Safety and Health Administration (OSHA) and American Conference of Governmental Industrial Hygienists (ACGIH) do not exist for all chemicals of interest. To address the need for worker exposure guidelines for those chemicals that lack OSHA or ACGIH OELs, a procedure for assigning Acceptable Occupational Exposure Limits (AOELs) for Hanford Site tank farm workers has been developed and applied to a selected group of 57 headspace chemicals.

Poet, Torka S.; Timchalk, Chuck

2006-03-24T23:59:59.000Z

44

Tank 241-AZ-101 Mixer Pump Test Vapor Sampling and Analysis Plan  

Science Conference Proceedings (OSTI)

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of mixer pumps in tank 241-AZ-101. The primary purpose of the mixer pump test (MPT) is to demonstrate that the two 300 horsepower mixer pumps installed in tank 241-AZ-101 can mobilize the settled sludge so that it can be retrieved for treatment and vitrification. Sampling will be performed in accordance with Tank 241-AZ-101 Mixer Pump Test Data Quality Objective (Banning 1999) and Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis (Mulkey 1999). The sampling will verify if current air emission estimates used in the permit application are correct and provide information for future air permit applications.

TEMPLETON, A.M.

2000-03-06T23:59:59.000Z

45

Tank 241-AZ-101 Mixer Pump Test Vapor Sampling and Analysis Plan  

Science Conference Proceedings (OSTI)

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of mixer pumps in tank 241-AZ-101. The primary purpose of the mixer pump test (MPT) is to demonstrate that the two 300 horsepower mixer pumps installed in tank 241-AZ-101 can mobilize the settled sludge so that it can be retrieved for treatment and vitrification. Sampling will be performed in accordance with Tank 241-AZ-101 Mixer Pump Test Data Quality Objective (Banning 1999) and Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis (Mulkey 1999). The sampling will verify if current air emission estimates used in the permit application are correct and provide information for future air permit applications.

TEMPLETON, A.M.

2000-04-10T23:59:59.000Z

46

Tank 241-AZ-101 Mixer Pump Test Vapor Sampling and Analysis Plan  

SciTech Connect

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of mixer pumps in tank 241-AZ-101. The primary purpose of the mixer pump test (MPT) is to demonstrate that the two 300 horsepower mixer pumps installed in tank 241-AZ-101 can mobilize the settled sludge so that it can be retrieved for treatment and vitrification Sampling will be performed in accordance with Tank 241-AZ-101 Mixer Pump Test Data Quality Objective (Banning 1999) and Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis (Mulkey 1999). The sampling will verify if current air emission estimates used in the permit application are correct and provide information for future air permit applications.

TEMPLETON, A.M.

2000-01-31T23:59:59.000Z

47

THE APPLICATION OF ELECTROCHEMICAL NOISE BASED CORROSION MONITORING TO NUCLEAR WASTE TANK VAPOR SPACE ENVIRONMENTS AT THE HANFORD SITE  

Science Conference Proceedings (OSTI)

Vapor space corrosion data collected by electrochemical noise (EN) based corrosion probes installed in double shell tanks (DSTs) at the Department of Energy's Hanford Site in Richland, Washington have historically been characterized by surprisingly high levels in current. In late 2003, a program was established to assess the significance of archived Hanford DST vapor space EN data. This program showed that the high vapor space current levels are likely the result of crevice corrosion on the vapor space electrodes. The design of DST vapor space electrodes provides tight metal-to-metal and gaskeito-metal interfaces necessary for this type of localized corrosion to occur. In-tank activities (splashing, etc.), or more likely condensation of water vapor in the vapor space, provide the necessary moisture. Because crevice corrosion appears to be active on the vapor space EN electronics, data collected from these electrodes are not likely to be applicable to the large flat metal surfaces that make up the bulk of the DST domes and upper walls. The data do, however, indicate that conditions in the DST vapor spaces are conducive to accelerated crevice corrosion at creviced areas in the tank vapor space (overlapping joints, riser interfaces, equipment penetrations, etc.) under high humidity conditions.

EDGEMON, G.L.

2005-04-04T23:59:59.000Z

48

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

DOE Green Energy (OSTI)

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

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

1997-01-01T23:59:59.000Z

49

Headspace vapor characterization of Hanford waste Tank 241-C-202: Results from samples collected on 06/25/96  

DOE Green Energy (OSTI)

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

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

1997-01-01T23:59:59.000Z

50

Filtration of Tank 48H Contents with a Cells Unit Filter  

Science Conference Proceedings (OSTI)

This report documents the design, operation, and results from tests using a small crossflow filter unit with Tank 48 H material.

Nash, C.A.

2002-02-20T23:59:59.000Z

51

Closure Report for Corrective Action Unit 134: Aboveground Storage Tanks, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 134 is identified in the Federal Facility Agreement and Consent Order (FFACO) as Aboveground Storage Tanks and consists of the following four Corrective Action Sites (CASs), located in Areas 3, 15, and 29 of the Nevada Test Site: CAS 03-01-03, Aboveground Storage Tank CAS 03-01-04, Tank CAS 15-01-05, Aboveground Storage Tank CAS 29-01-01, Hydrocarbon Stain

NSTec Environmental Restoration

2009-06-30T23:59:59.000Z

52

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

DOE Green Energy (OSTI)

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

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

1996-05-01T23:59:59.000Z

53

Advanced Membrane Systems: Recovering Wasteful and Hazardous Fuel Vapors at the Gasoline Tank  

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

Case study covering Compact Membrane Systems, Inc. and its membrane vapor processor that recovers fuel vapors from gasoline refueling.

54

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

DOE Green Energy (OSTI)

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

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

1997-01-01T23:59:59.000Z

55

Preliminary analysis of tank 241-C-106 dryout due to large postulated leak and vaporization  

SciTech Connect

This analysis assumes that there is a hypothetical large leak at the bottom of Tank 241-C-106 which initiates the dryout of the tank. The time required for a tank to dryout after a leak is of interest for safety reasons. As a tank dries out, its temperature is expected to increase which could affect the structural integrity of the concrete tank dome. Hence, it is of interest to know how fast and how high the temperature in a leaky tank increases, so that mitigation procedures can be planned and implemented in a timely manner. This analysis is focused on tank 241-C-106, which is known to be high thermal tank. The objective of the study was to determine how long it would take for tank 241-C-106 to reach 350 degrees Fahrenheit (about 177 degrees Centigrade) after a postulated large leak develops at the bottom center of the tank. The temperature of 350 degrees Fahrenheit is the minimum temperature that can cause structural damage to concrete (ACI 1992). The postulated leak at the bottom of the tank and the resulting dryout of the sludge in the tank make this analysis different from previous thermal analyses of the C-106 tank and other tanks, especially the double-shell tanks which are mostly liquid.

Piepho, M.G.

1994-12-01T23:59:59.000Z

56

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

Science Conference Proceedings (OSTI)

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

Caprio, G.S.

1995-11-01T23:59:59.000Z

57

Vapor and gas sampling of single-shell tank 241-SX-106 using the vapor sampling system  

SciTech Connect

This document presents sampling data resulting from the March 24, 1995, sampling of SST 241-SX-106 using the vapor sampling system.

Caprio, G.S.

1995-09-20T23:59:59.000Z

58

Mathematical analysis of hydrogen mixing and diffusion in the vapor space of a high-level nuclear waste tank  

DOE Green Energy (OSTI)

This paper presents mathematical analyses of the possible accumulation of radiolytically produced hydrogen in the vapor space in a tank storing liquid high-level radioactive waste. Under normal operating conditions, these tanks are continuously ventilated with air to ensure that the concentration of hydrogen never reaches its lower flammability limit (4%). These scenarios are considered in which it is postulated that hydrogen may accumulate and present a flammability hazard. These scenarios are stratification due to gravity, slow mixing when the ventilation system is operating, and slow mixing when the ventilation system is not operating. In all three cases, the analyses indicate that the accumulation of hydrogen is not likely and thus does not present a flammability problem so long as controls are in place to dilute its concentration to less than 4%.

Bibler, N.E. (ed.); Wallace, R.M.

1991-01-01T23:59:59.000Z

59

TESTING VAPOR SPACE AND LIQUID-AIR INTERFACE CORROSION IN SIMULATED ENVIRONMENTS OF HANFORD DOUBLE-SHELLED TANKS  

Science Conference Proceedings (OSTI)

Electrochemical coupon testing were performed on 6 Hanford tank solution simulants and corresponding condensate simulants to evaluate the susceptibility of vapor space and liquid/air interface corrosion. Additionally, partial-immersion coupon testing were performed on the 6 tank solution simulants to compliment the accelerated electrochemical testing. Overall, the testing suggests that the SY-102 high nitrate solution is the most aggressive of the six solution simulants evaluated. Alternatively, the most passive solution, based on both electrochemical testing and coupon testing, was AY-102 solution. The presence of ammonium nitrate in the simulants at the lowest concentration tested (0.001 M) had no significant effect. At higher concentrations (0.5 M), ammonium nitrate appears to deter localized corrosion, suggesting a beneficial effect of the presence of the ammonium ion. The results of this research suggest that there is a threshold concentration of ammonium ions leading to inhibition of corrosion, thereby suggesting the need for further experimentation to identify the threshold.

Hoffman, E.

2013-05-30T23:59:59.000Z

60

Acceptance test procedure for SY Tank Farm replacement exhauster unit  

SciTech Connect

The proper functioning of a new 241-SY Tank Farm replacement exhauster will be acceptance tested, to establish operability and to provide an operational baseline for the equipment. During this test, a verification of all of the alarm and control circuits associated with the exhaust, which provide operating controls and/or signals to local and remote alarm/annunciator panels, shall be performed. Test signals for sensors that provide alarms, warnings, and/or interlocks will be applied to verify that alarm, warning, and interlock setpoints are correct. Alarm and warning lights, controls, and local and remote readouts for the exhauster will be verified to be adequate for proper operation of the exhauster. Testing per this procedure shall be conducted in two phases. The first phase of testing, to verify alarm, warning, and interlock setpoints primarily, will be performed in the MO-566 Fab Shop. The second phase of testing, to verify proper operation and acceptable interface with other tank farm systems, will be conducted after the exhauster and all associated support and monitoring equipment have been installed in the SY Tank Farm. The exhauster, which is mounted on a skid and which will eventually be located in the SY tank farm, receives input signals from a variety of sensors mounted on the skid and associated equipment. These sensors provide information such as: exhauster system inlet vacuum pressure; prefilter and HEPA filter differential pressures; exhaust stack sampler status; exhaust fan status; system status (running/shut down); and radiation monitoring systems status. The output of these sensors is transmitted to the exhauster annunciator panel where the signals are displayed and monitored for out-of-specification conditions.

Becken, G.W.

1994-12-16T23:59:59.000Z

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


61

Advanced Membrane Systems: Recovering Wasteful and Hazardous Fuel Vapors at the Gasoline Tank  

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

CMS to develop a membrane CMS to develop a membrane vapor processor that recovers fuel vapors from gasoline refueling with 99 percent efficiency. This membrane system enables gasoline stations to surpass environmental regulations while reducing fuel losses. Compact Membrane Systems, Inc. (CMS) was founded in 1993 in Wilmington, DE, with the acquisition of rights to certain DuPont polymer membrane patents. CMS focuses

62

Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots'' from the concrete vault, and the drilling removal of the cement-lined vault sump. Field activities began on November 28, 2000, and ended on December 4, 2000. After verification samples were collected, the vault was repaired with cement. The concrete vault sump, soil excavated beneath the sump, and compactable hot line trash were disposed at the Area 23 Sanitary Landfill. The vault interior was field surveyed following the removal of waste to verify that unrestricted release criteria had been achieved. Since the site is closed by unrestricted release decontamination and verification, post-closure care is not required.

D. H. Cox

2001-06-01T23:59:59.000Z

63

Closure Report for Corrective Action Unit 130: Storage Tanks Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 130: Storage Tanks, Nevada Test Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 130 are located within Areas 1, 7, 10, 20, 22, and 23 of the Nevada Test Site. Corrective Action Unit 130 is comprised of the following CASs: 01-02-01, Underground Storage Tank 07-02-01, Underground Storage Tanks 10-02-01, Underground Storage Tank 20-02-03, Underground Storage Tank 20-99-05, Tar Residue 22-02-02, Buried UST Piping 23-02-07, Underground Storage Tank This CR provides documentation supporting the completed corrective action investigations and provides data confirming that the closure objectives for CASs within CAU 130 were met. To achieve this, the following actions were performed: Reviewed the current site conditions, including the concentration and extent of contamination. Implemented any corrective actions necessary to protect human health and the environment. Properly disposed of corrective action and investigation-derived wastes. From August 4 through September 30, 2008, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 130, Storage Tanks, Nevada Test Site, Nevada. The purposes of the activities as defined during the data quality objectives process were: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent, implement appropriate corrective actions, confirm that no residual contamination is present, and properly dispose of wastes. Constituents detected during the closure activities were evaluated against final action levels to identify COCs for CAU 130. Assessment of the data generated from closure activities indicates that no further action is necessary because no COCs were identified at any CAU 130 CAS. Debris removal from these CASs was considered a best management practice because no contamination was detected. The DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: No further corrective action is required at all CAU 130 CASs. A Notice of Completion to DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 130. Corrective Action Unit 130 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

Alfred Wickline

2009-03-01T23:59:59.000Z

64

Dual Tank Fuel System  

DOE Patents (OSTI)

A dual tank fuel system has primary and secondary fuel tanks, with the primary tank including a filler pipe to receive fuel and a discharge line to deliver fuel to an engine, and with a balance pipe interconnecting the primary tank and the secondary tank. The balance pipe opens close to the bottom of each tank to direct fuel from the primary tank to the secondary tank as the primary tank is filled, and to direct fuel from the secondary tank to the primary tank as fuel is discharged from the primary tank through the discharge line. A vent line has branches connected to each tank to direct fuel vapor from the tanks as the tanks are filled, and to admit air to the tanks as fuel is delivered to the engine.

Wagner, Richard William (Albion, NY); Burkhard, James Frank (Churchville, NY); Dauer, Kenneth John (Avon, NY)

1999-11-16T23:59:59.000Z

65

Operable Unit 3-13, Group 7, SFE-20 Hot Waste Tank System Remedial Action Request  

SciTech Connect

This Remedial Action Report summarizes activities undertaken to remediate the Operable Unit 3-13, Group 7, SFE-20 Hot Waste Tank System at the Idaho Nuclear Technology and Engineering Center at the Idaho National Laboratory Site. The site addressed in this report was defined in the Operable Unit 3-13 Record of Decision and subsequent implementing documents. This report concludes that remediation requirements and cleanup goals established for the site have been accomplished and is hereafter considered a No Further Action site.

L. Davison

2009-06-30T23:59:59.000Z

66

Operable Unit 3-13, Group 7, SFE-20 Hot Waste Tank System Remedial Action Report  

SciTech Connect

This Remedial Action Report summarizes activities undertaken to remediate the Operable Unit 3-13, Group 7, SFE-20 Hot Waste Tank System at the Idaho Nuclear Technology and Engineering Center at the Idaho National Laboratory Site. The site addressed in this report was defined in the Operable Unit 3-13 Record of Decision and subsequent implementing documents. This report concludes that remediation requirements and cleanup goals established for the site have been accomplished and is hereafter considered a No Further Action site.

Lee Davison

2009-06-30T23:59:59.000Z

67

Experimental and Modeling Study of the Flammability of Fuel Tank Headspace Vapors from Ethanol/Gasoline Fuels; Phase 3: Effects of Winter Gasoline Volatility and Ethanol Content on Blend Flammability; Flammability Limits of Denatured Ethanol  

DOE Green Energy (OSTI)

This study assessed differences in headspace flammability for summertime gasolines and new high-ethanol content fuel blends. The results apply to vehicle fuel tanks and underground storage tanks. Ambient temperature and fuel formulation effects on headspace vapor flammability of ethanol/gasoline blends were evaluated. Depending on the degree of tank filling, fuel type, and ambient temperature, fuel vapors in a tank can be flammable or non-flammable. Pure gasoline vapors in tanks generally are too rich to be flammable unless ambient temperatures are extremely low. High percentages of ethanol blended with gasoline can be less volatile than pure gasoline and can produce flammable headspace vapors at common ambient temperatures. The study supports refinements of fuel ethanol volatility specifications and shows potential consequences of using noncompliant fuels. E85 is flammable at low temperatures; denatured ethanol is flammable at warmer temperatures. If both are stored at the same location, one or both of the tanks' headspace vapors will be flammable over a wide range of ambient temperatures. This is relevant to allowing consumers to splash -blend ethanol and gasoline at fueling stations. Fuels compliant with ASTM volatility specifications are relatively safe, but the E85 samples tested indicate that some ethanol fuels may produce flammable vapors.

Gardiner, D. P.; Bardon, M. F.; Clark, W.

2011-07-01T23:59:59.000Z

68

Tank 241-BY-110 Headspace Gas and Vapor Characterization Results for Samples Collected in November 1994. Revision 2  

Science Conference Proceedings (OSTI)

Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories.

Huckaby, J.L. [Pacific Northwest Lab., Washington, DC (United States); Bratzel, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1995-09-01T23:59:59.000Z

69

Tank 241-U-111 tank characterization plan  

Science Conference Proceedings (OSTI)

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-U-111.

Carpenter, B.C.

1995-01-24T23:59:59.000Z

70

Record of Decision for Tank Farm Soil and INTEC Groundwater, Operable Unit 3-14  

Science Conference Proceedings (OSTI)

This decision document presents the selected remedy for Operable Unit (OU) 3-14 tank farm soil and groundwater at the Idaho Nuclear Technology and Engineering Center (INTEC), which is located on the Idaho National Laboratory (INL) Site. The tank farm was initially evaluated in the OU 3-13 Record of Decision (ROD), and it was determined that additional information was needed to make a final decision. Additional information has been obtained on the nature and extent of contamination in the tank farm and on the impact to groundwater. The selected remedy was chosen in accordance with the Comprehensive Environmental Response, Liability and Compensation Act of 1980 (CERCLA) (42 USC 9601 et seq.), as amended by the Superfund Amendments and Reauthorization Act of 1986 (Public Law 99-499) and the National Oil and Hazardous Substances Pollution Contingency Plan (40 CFR 300). The selected remedy is intended to be the final action for tank farm soil and groundwater at INTEC. The response action selected in this ROD is necessary to protect the public health, welfare, or the environment from actual or threatened releases of hazardous substances into the environment. Such a release or threat of release may present an imminent and substantial endangerment to public health, welfare, or the environment. The remedial actions selected in this ROD are designed to reduce the potential threats to human health and the environment to acceptable levels. In addition, DOE-ID, EPA, and DEQ (the Agencies) have determined that no action is necessary under CERCLA to protect public health, welfare, or the environment at 16 sites located outside the tank farm boundary. The purposes of the selected remedy are to (1) contain contaminated soil as the radionuclides decay in place, (2) isolate current and future workers and biological receptors from contact with contaminated soil, and (3) restore the portion of Snake River Plain Aquifer contaminated by INTEC releases to Idaho Ground Water Quality standards (same as maximum contaminant levels) by reducing water infiltration through strontium-90 contaminated perched water and interbeds. In addition, the remedy will prevent future drinking water wells from being drilled into the contaminated portion of the aquifer that is in and near the INTEC facility until such time as the water is restored to maximum contaminant levels or below.

L. S. Cahn

2007-05-16T23:59:59.000Z

71

Fiscal Year 2009 Annual Report for Operable Unit 3-14, Tank Farm Soil and INTEC Groundwater  

SciTech Connect

This annual report summarizes maintenance, monitoring, and inspection activities performed to implement the selected remedy for Waste Area Group 3, Operable Unit 3-14, Tank Farm soil and groundwater at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory Site. Results from monitoring perched water and groundwater at the Idaho Nuclear Technology and Engineering Center are also presented.

Forsythe, Howard S.

2010-04-10T23:59:59.000Z

72

Screening values for Non-Carcinogenic Hanford Waste Tank Vapor Chemicals that Lack Established Occupational Exposure Limits  

SciTech Connect

Over 1,500 different volatile chemicals have been reported in the headspaces of tanks used to store high-level radioactive waste at the U.S. Department of Energy's Hanford Site. Concern about potential exposure of tank farm workers to these chemicals has prompted efforts to evaluate their toxicity, identify chemicals that pose the greatest risk, and incorporate that information into the tank farms industrial hygiene worker protection program. Established occupation exposure limits for individual chemicals and petroleum hydrocarbon mixtures have been used elsewhere to evaluate about 900 of the chemicals. In this report headspace concentration screening values were established for the remaining 600 chemicals using available industrial hygiene and toxicological data. Screening values were intended to be more than an order of magnitude below concentrations that may cause adverse health effects in workers, assuming a 40-hour/week occupational exposure. Screening values were compared to the maximum reported headspace concentrations.

Poet, Torka S.; Mast, Terryl J.; Huckaby, James L.

2006-02-06T23:59:59.000Z

73

Closure Report for Corrective Action Unit 124, Storage Tanks, Nevada Test Site, Nevada with Errata Sheet, Revision 0  

Science Conference Proceedings (OSTI)

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 124, Storage Tanks, Nevada Test Site (NTS), Nevada. This report complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996; as amended January 2007). This CR provides documentation and justification for the closure of CAU 124 without further corrective action. This justification is based on process knowledge and the results of the investigative activities conducted in accordance with the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 124: Storage Tanks, Nevada Test Site, Nevada (NNSA/NSO, 2007). The SAFER Plan provides information relating to site history as well as the scope and planning of the investigation. Therefore, this information will not be repeated in this CR.

Alfred Wickline

2008-01-01T23:59:59.000Z

74

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

Science Conference Proceedings (OSTI)

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

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

1995-10-01T23:59:59.000Z

75

Savannah River Site - Tank 48 SRS Review Report  

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

ETR-2 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Tank 48 at the Savannah River Site (SRS) Why DOE-EM Did This Review Tank 48 is a 1.3 million gallon tank with full secondary containment, located and interconnected within the SRS tank system that will play a very important role in removal and processing of high-level waste (HLW) in the years ahead. However, the tank is currently isolated from the system and unavailable for use, because its contents. It contains approximately 250,000 gallons of salt solution containing Cesium-137 and other radioisotopes which are contaminated with significant quantities of tetraphenylborate (TPB), a material which can release benzene vapor to the tank head space in

76

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 134: Aboveground Storage Tanks, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 134, Aboveground Storage Tanks. CAU 134 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996; as amended February 2008) and consists of four Corrective Action Sites (CASs) located in Areas 3, 15, and 29 of the Nevada Test Site (NTS) (Figure 1): (1) CAS 03-01-03, Aboveground Storage Tank; (2) CAS 03-01-04, Tank; (3) CAS 15-01-05, Aboveground Storage Tank; and (4) CAS 29-01-01, Hydrocarbon Stain. CAS 03-01-03 consists of a mud tank that is located at the intersection of the 3-07 and the 3-12 Roads in Area 3 of the NTS. The tank and its contents are uncontaminated and will be dispositioned in accordance with applicable federal, state, and local regulations. This CAS will be closed by taking no further action. CAS 03-01-04 consists of a potable water tank that is located at the Core Complex in Area 3 of the NTS. The tank will be closed by taking no further action. CAS 15-01-05 consists of an aboveground storage tank (AST) and associated impacted soil, if any. This CAS is located on a steep slope near the Climax Mine in Area 15 of the NTS. The AST is empty and will be dispositioned in accordance with applicable federal, state, and local regulations. Soil below the AST will be sampled to identify whether it has been impacted by chemicals at concentrations exceeding the action levels. It appears that the tank is not at its original location. Soil will also be sampled at the original tank location, if it can be found. If soil at either location has been impacted at concentrations that exceed the action levels, then the extent of contamination will be identified and a use restriction (UR) will be implemented. The site may be clean closed if contamination is less than one cubic yard in extent and can be readily excavated. If action levels are not exceeded, then no further action is required. CAS 29-01-01 consists of soil that has been impacted by a release or operations from an active diesel AST that fuels the generator at the Shoshone Receiver Site in Area 29 of the NTS. Soil below the AST will be sampled to identify whether it has been impacted at concentrations exceeding the action levels. If it is, then the extent of contamination will be identified and a UR will be implemented. The site may be clean closed if contamination is less than one cubic yard in extent, can be readily excavated, and it is determined that clean closure is feasible based upon site conditions. If action levels are not exceeded, then no further action is required. Based on review of the preliminary assessment information for CAU 134 and recent site inspections, there is sufficient process knowledge to close CAU 134 using the SAFER process.

NSTec Environmental Restoration

2008-05-31T23:59:59.000Z

77

Closure Report for Corrective Action Unit 330: Areas 6, 22, and 23 Tanks and Spill Sites, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

This Closure Report (CR) documents the activities performed to close Corrective Action Unit (CAU) 330: Areas 6, 22, and 23 Tanks and Spill Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO of 1996), and the Nevada Division of Environmental Protection (NDEP)-approved Streamlined Approach for Environmental Restoration (SAFER) Plan for CAU 330: Areas 6, 22, and 23 Tanks and Spill Sites, Nevada Test Site (NTS), Nevada (U.S. Department of Energy, National Nuclear Security Administration Nevada Operation Office [NNSA/NV], 2001). CAU 330 consists of the following four Corrective Action Sites (CASs): 06-02-04, 22-99-06, 23-01-02, and 23-25-05 (Figure 1).

A. T. Urbon

2003-07-01T23:59:59.000Z

78

Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada  

SciTech Connect

The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved.

D. H. Cox

2000-07-01T23:59:59.000Z

79

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 130: Storage Tanks, Nevada Test Site, Nevada, Revision 0  

Science Conference Proceedings (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 130, Storage Tanks, identified in the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended February 2008). Corrective Action Unit 130 consists of the seven following corrective action sites (CASs) located in Areas 1, 7, 10, 20, 22, and 23 of the Nevada Test Site: 01-02-01, Underground Storage Tank 07-02-01, Underground Storage Tanks 10-02-01, Underground Storage Tank 20-02-03, Underground Storage Tank 20-99-05, Tar Residue 22-02-02, Buried UST Piping 23-02-07, Underground Storage Tank This plan provides the methodology for field activities needed to gather the necessary information for closing each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 130 using the SAFER process. Additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible recommendation that no further corrective action is necessary. This will be presented in a Closure Report that will be prepared and submitted to the Nevada Division of Environmental Protection (NDEP) for review and approval. The sites will be investigated based on the data quality objectives (DQOs) finalized on April 3, 2008, by representatives of NDEP; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for each CAS in CAU 130. The DQO process developed for this CAU identified the following expected closure options: (1) investigation and confirmation that no contamination exists above the final action levels, leading to a no further action declaration; (2) characterization of the nature and extent of contamination, leading to closure in place with use restrictions; or (3) clean closure by remediation and verification. The following text summarizes the SAFER activities that will support the closure of CAU 130: Perform site preparation activities (e.g., utilities clearances, geophysical surveys). Move or remove and dispose of debris at various CASs, as required. Collect environmental samples from designated target populations (e.g., stained soil) to confirm or disprove the presence of contaminants of concern (COCs) as necessary to supplement existing information. If no COCs are present at a CAS, establish no further action as the corrective action. If COCs exist, collect environmental samples from designated target populations (e.g., clean soil adjacent to contaminated soil) and submit for laboratory analyses to define the extent of COC contamination. If a COC is present at a CAS, either: - Establish clean closure as the corrective action. The material to be remediated will be removed, disposed of as waste, and verification samples will be collected from remaining soil, or - Establish closure in place as the corrective action and implement the appropriate use restrictions. Obtain consensus from NDEP that the preferred closure option is sufficient to protect human health and the environment. Close the underground storage tank(s) and their contents, if any, in accordance with Nevada Administrative Code regulations. Remove the lead brick(s) found at any CAS in accordance with the Resource Conservation and Recovery Act.

Alfred Wickline

2008-07-01T23:59:59.000Z

80

Resource Conservation and Recovery Act (RCRA) Part B permit application for tank storage units at the Oak Ridge Y-12 Plant  

SciTech Connect

In compliance with the Resource Conservation and Recovery Act (RCRA), this report discusses information relating to permit applications for three tank storage units at Y-12. The storage units are: Building 9811-1 RCRA Tank Storage Unit (OD-7); Waste Oil/Solvent Storage Unit (OD-9); and Liquid Organic Solvent Storage Unit (OD-10). Numerous sections discuss the following: Facility description; waste characteristics; process information; groundwater monitoring; procedures to prevent hazards; contingency plan; personnel training; closure plan, post closure plan, and financial requirements; record keeping; other federal laws; organic air emissions; solid waste management units; and certification. Sixteen appendices contain such items as maps, waste analyses and forms, inspection logs, equipment identification, etc.

Not Available

1994-05-01T23:59:59.000Z

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


81

On the Potential Change in Surface Water Vapor Deposition over the Continental United States due to Increases in Atmospheric Greenhouse Gases  

Science Conference Proceedings (OSTI)

Characteristics of surface water vapor deposition (WVD) over the continental United States under the present climate and a future climate scenario reflecting the mid-twenty-first-century increased greenhouse gas concentrations were evaluated by ...

Zaitao Pan; Moti Segal; Charles Graves

2006-04-01T23:59:59.000Z

82

Experimental and Modeling Study of the Flammability of Fuel Tank Headspace Vapors from Ethanol/Gasoline Fuels, Phase 2: Evaluations of Field Samples and Laboratory Blends  

DOE Green Energy (OSTI)

Study to measure the flammability of gasoline/ethanol fuel vapors at low ambient temperatures and develop a mathematical model to predict temperatures at which flammable vapors were likely to form.

Gardiner, D. P.; Bardon, M. F.; LaViolette, M.

2010-04-01T23:59:59.000Z

83

Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks Nevada Test Site, Nevada  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO, CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites (FFACO, 1996). Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU 135, Area 25 Underground Storage Tanks (USTs), which is located on the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada.

U.S. Department of Energy, Nevada Operations Office

1999-05-05T23:59:59.000Z

84

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 121: Storage Tanks and Miscellaneous Sites, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 121, Storage Tanks and Miscellaneous Sites. CAU 121 is currently listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO, 1996) and consists of three Corrective Action Sites (CASs) located in Area 12 of the Nevada Test Site (NTS): CAS 12-01-01, Aboveground Storage Tank; CAS 12-01-02, Aboveground Storage Tank; and CAS 12-22-26, Drums; 2 AST's. CASs 12-01-01 and 12-01-02 are located to the west of the Area 12 Camp, and CAS 12-22-26 is located near the U-12g Tunnel, also known as G-tunnel, in Area 12 (Figure 1). The aboveground storage tanks (ASTs) present at CASs 12-01-01 and 12-01-02 will be removed and disposed of at an appropriate facility. Soil below the ASTs will be sampled to identify whether it has been impacted with chemicals or radioactivity above action levels. If impacted soil above action levels is present, the soil will be excavated and disposed of at an appropriate facility. The CAS 12-22-26 site is composed of two overlapping areas, one where drums had formerly been stored, and the other where an AST was used to dispense diesel for locomotives used at G-tunnel. This area is located above an underground radioactive materials area (URMA), and within an area that may have elevated background radioactivity because of containment breaches during nuclear tests and associated tunnel reentry operations. CAS 12-22-26 does not include the URMA or the elevated background radioactivity. An AST that had previously been used to store liquid magnesium chloride (MgCl) was properly disposed of several years ago, and releases from this tank are not an environmental concern. The diesel AST will be removed and disposed of at an appropriate facility. Soil at the former drum area and the diesel AST area will be sampled to identify whether it has been impacted by releases, from the drums or the AST, with chemicals or radioactivity above action levels. CAS 12-22-26 has different potential closure pathways that are dependent upon the concentrations and chemicals detected. If only petroleum hydrocarbons are detected above action levels, then the area will be use-restricted. It will not be excavated because of the more significant hazard of excavating within a URMA. Similarly, polychlorinated biphenyls (PCBs) will only be excavated for concentrations of 50 parts per million (ppm) or greater, if there are no other factors that require excavation. For PCBs at concentrations above 1 ppm, the area will be use-restricted as required by Title 40, Code of Federal Regulations (CFR) Part 761 for PCBs (CFR, 2006), in the ''Toxic Substances Control Act'' (TSCA). Other chemicals at concentrations above the final action levels (FALs) will be excavated. If radioactivity is above action levels, then the soil will be excavated only to a depth of 1 foot (ft) below ground surface (bgs) and replaced with clean fill. This action is intended to remove the ''hot spot'' on the surface caused by leakage from a drum, and not to remediate the URMA.

NSTec Environmental Restoration

2007-06-01T23:59:59.000Z

85

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  

Science Conference Proceedings (OSTI)

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).

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

2012-10-25T23:59:59.000Z

86

Tank Closure  

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

Topics 3 Overview of SRS Tank Closure Program Two Tank Farms - F Area and H Area Permitted by SC as Industrial Wastewater Facilities under the Pollution Control...

87

Standard guide for sampling radioactive tank waste  

E-Print Network (OSTI)

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

88

Corrective Action Decision Document/Closure Report for Corrective Action Unit 557: Spills and Tank Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 557, Spills and Tank Sites, in Areas 1, 3, 6, and 25 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order. Corrective Action Unit 557 comprises the following corrective action sites (CASs): 01-25-02, Fuel Spill 03-02-02, Area 3 Subdock UST 06-99-10, Tar Spills 25-25-18, Train Maintenance Bldg 3901 Spill Site The purpose of this Corrective Action Decision Document/Closure Report is to identify and provide the justification and documentation that supports the recommendation for closure of the CAU 557 CASs with no further corrective action. To achieve this, a corrective action investigation (CAI) was conducted from May 5 through November 24, 2008. The CAI activities were performed as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 557: Spills and Tank Sites, Nevada Test Site, Nevada.

Alfred Wickline

2009-05-01T23:59:59.000Z

89

Closure Report for Corrective Action Unit 127: Areas 25 and 26 Storage Tanks, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

CAU 127, Areas 25 and 26 Storage Tanks, consists of twelve CASs located in Areas 25 and 26 of the NTS. The closure alternatives included no further action, clean closure, and closure in place with administrative controls. The purpose of this Closure Report is to provide a summary of the completed closure activities, documentation of waste disposal, and analytical data to confirm that the remediation goals were met.

NSTec Environmental Restoration

2008-02-01T23:59:59.000Z

90

Operable Unit 3-14, Tank Farm Soil and INTEC Groundwater Remedial Design/Remedial Action Scope of Work  

SciTech Connect

This Remedial Design/Remedial Action (RD/RA) Scope of Work pertains to OU 3-14 Idaho Nuclear Technology and Engineering Center and the Idaho National Laboratory and identifies the remediation strategy, project scope, schedule, and budget that implement the tank farm soil and groundwater remediation, in accordance with the May 2007 Record of Decision. Specifically, this RD/RA Scope of Work identifies and defines the remedial action approach and the plan for preparing the remedial design documents.

D. E. Shanklin

2007-07-25T23:59:59.000Z

91

Comparative safety analysis of LNG storage tanks  

Science Conference Proceedings (OSTI)

LNG storage tank design and response to selected release scenarios were reviewed. The selection of the scenarios was based on an investigation of potential hazards as cited in the literature. A review of the structure of specific LNG storage facilities is given. Scenarios initially addressed included those that most likely emerge from the tank facility itself: conditions of overfill and overflow as related to liquid LNG content levels; over/underpressurization at respective tank vapor pressure boundaries; subsidence of bearing soil below tank foundations; and crack propagation in tank walls due to possible exposure of structural material to cryogenic temperatures. Additional scenarios addressed include those that result from external events: tornado induced winds and pressure drops; exterior tank missile impact with tornado winds and rotating machinery being the investigated mode of generation; thermal response due to adjacent fire conditions; and tank response due to intense seismic activity. Applicability of each scenario depended heavily on the specific tank configurations and material types selected. (PSB)

Fecht, B.A.; Gates, T.E.; Nelson, K.O.; Marr, G.D.

1982-07-01T23:59:59.000Z

92

Nevada test site underground storage tank number 12-13-1: Nevada division of emergency management case number H931130E corrective action unit 450. Closure report  

Science Conference Proceedings (OSTI)

The project site was identified as an abandoned Underground Storage Tank (UST) to be closed under the Department of Energy/Nevada Operations Office (DOE/NV) Environmental Restoration Division (ERD) Program during Fiscal Year 1993. The United States Environmental Protection Agency (EPA) requires that before permanent closure is completed an assessment of the site must take place. The Nevada Division of Environmental Protection (NDEP) requires assessment and corrective actions for a petroleum substance in the soil which exceeds 100 milligrams per kilogram (mg/kg). Subsequent to the tank removal, a hydrocarbon release was identified at the site. The release was reported to the NDEP by DOE/NV on November 30, 1993. Nevada Division of Environmental Management (NDEM) Case Number H931130E was assigned. This final closure report documents the assessment and corrective actions taken for the hydrocarbon release identified at the site. The Notification of Closure, EPA Form 7530-1 dated March 22, 1994, is provided in Appendix A. A 45-day report documenting the notification for a hydrocarbon release was submitted to NDEP on April 6, 1994.

NONE

1997-01-01T23:59:59.000Z

93

Corrective Action Investigation Plan for Corrective Action Unit 127: Areas 25 and 26 Storage Tanks, Nevada Test Site, Nevada (Rev. No.: 0, August 2002)  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Offices's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 127 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 127 is located on the Nevada Test Site approximately 65 miles northwest of Las Vegas, Nevada. This CAU is comprised of 12 Corrective Action Sites (CASs) located at Test Cell C; the Engine Maintenance, Assembly, and Disassembly (E-MAD) Facility; the X-Tunnel in Area 25; the Pluto Disassembly Facility; the Pluto Check Station; and the Port Gaston Training Facility in Area 26. These CASs include: CAS 25-01-05, Aboveground Storage Tank (AST); CAS 25-02-02, Underground Storage Tank (UST); CAS 25-23-11, Contaminated Materials; CAS 25-12-01, Boiler; CAS 25-01-06, AST; CAS 25-01-07, AST; CAS 25-02-13, UST; CAS 26- 01-01, Filter Tank (Rad) and Piping; CAS 26-01-02, Filter Tank (Rad); CAS 26-99-01, Radioactively Contaminated Filters; CAS 26-02-01, UST; CAS 26-23-01, Contaminated Liquids Spreader. Based on site history, process knowledge, and previous field efforts, contaminants of potential concern for CAU 127 include radionuclides, metals, total petroleum hydrocarbons, volatile organic compounds, asbestos, and polychlorinated biphenyls. Additionally, beryllium may be present at some locations. The sources of potential releases are varied, but releases of contaminated liquids may have occurred and may have migrated into and impacted soil below and surrounding storage vessels at some of the CASs. Also, at several CASs, asbestos-containing materials may be present on the aboveground structures and may be friable. Exposure pathways are limited to ingestion, inhalation, and dermal contact (adsorption) of soils/sediments or liquids, or inhalation of contaminants by site workers due to disturbance of contaminated materials. Future land-use scenarios limit subsequent uses of the CASs to various nonresidential (i.e., industrial) activities. Field activities will consist of radiological walkover and screening surveys, and field-screening and collecting of both tank content and soil samples, and further sample testing as appropriate. A two-step data quality objective strategy will be followed: (1) Phase I will be to collect environmental samples for laboratory analysis to confirm the presence or absence of contaminants at concentrations exceeding preliminary action levels; and (2) Phase II will be to collect additional environmental samples for laboratory analysis to determine the extent of contamination identified in Phase I. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NV

2002-08-27T23:59:59.000Z

94

Tank Closure  

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

Closure Closure Sherri Ross Waste Removal and Tank Closure Waste Disposition Project Programs Division Savannah River Operations Office Presentation to the DOE HLW Corporate Board 2  Overview and Status of SRS Tank Closure Program  Issues/Challenges  Communications  Schedule Performance  Ceasing Waste Removal  Compliance with SC Water Protection Standards  Questions? Topics 3 Overview of SRS Tank Closure Program  Two Tank Farms - F Area and H Area  Permitted by SC as Industrial Wastewater Facilities under the Pollution Control Act  Three agency Federal Facility Agreement (FFA)  DOE, SCDHEC, and EPA  51 Tanks  24 old style tanks (Types I, II and IV)  Do not have full secondary containment  FFA commitments to close by 2022  2 closed in 1997

95

Memorandum of Understanding Between the United States Department of Energy and the Washington State Department of Ecology for Development of the Hanford Site Tank Closure and Waste Management EIS ("TC&WM EIS")  

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

THE THE UNITED STATES DEPARTMENT OF ENERGY, AND THE WASHINGTON STATE DEPARTMENT OF ECOLOGY, FOR DEVELOPMENT OF THE HANFORD SITE TANK CLOSURE AND WASTE MANAGEMENT EIS ("TC&WM EIS") I. INTRODUCTION The U.S. Department of Energy (DOE) and Washington State Department of Ecology (Ecology) have mutual responsibilities for accomplishing cleanup of the Hanford Site as well as continuing ongoing waste management activities consistent with applicable federal and state laws and regulations. The Hanford Federal Facility Agreement and Consent Order (otherwise called the "Tri-Party Agreement", or "TPA") contains various enforceable milestones that apply to tank waste management activities. DOE is also required to comply with applicable requirements of

96

Streamlined approach for environmental restoration closure report for Corrective Action Unit No. 456: Underground storage tank release site 23-111-1, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

The underground storage tank (UST) release site 23-111-1 is located in Mercury, Nevada. The site is in Area 23 of the Nevada Test Site, (NTS) located on the north side of Building 111. The tank associated with the release was closed in place using cement grout on September 6, 1990. The tank was not closed by removal due to numerous active underground utilities, a high-voltage transformer pad, and overhead power lines. Soil samples collected below the tank bottom at the time of tank closure activities exceeded the Nevada Administrative Code Action Level of 100 milligrams per kilogram (mg/kg) for petroleum hydrocarbons. Maximum concentrations detected were 119 mg/kg. Two passive venting wells were subsequently installed at the tank ends to monitor the progress of biodegradation at the site. Quarterly air sampling from the wells was completed for approximately one year, but was discontinued since data indicated that considerable biodegradation was not occurring at the site.

NONE

1998-04-01T23:59:59.000Z

97

FLAMMABILITY AND CONSEQUENCE ANALYSIS FOR MCU WASTE TANKS  

DOE Green Energy (OSTI)

The Savannah River Site of Department of Energy will use the new Modular Caustic Side Solvent Extraction Unit (MCU) to process the waste stream by removing/reducing Cs-137 using Caustic Side Solvent Extraction (CSSX) technology. The CSSX technology utilizes multicomponent organic solvent and annular centrifugal contactors to extract Cs-137 from waste salt solution. Due to the radiolysis of the aqueous nuclear wastes, hydrogen generation is expected in the MCU holding tanks. The hydrogen from radiolysis and the vapor from the organic component of the solvent, Isopar-L, may form a composite flammable gas mixture, resulting in a shorter time to flammability than that of a pure hydrogen environment. It has been found that the time-to-Lower Flammability Limit (LFL) and stoichiometric concentration (SC) vary greatly from tank to tank, and could be decreased significantly by the presence of the Isopar-L. However, neither the deflagration nor the detonation event would challenge the Evaluation Guideline for any of the tanks at any liquid level.

Knight, J; Mukesh Gupta, M

2007-02-13T23:59:59.000Z

98

Development of Occupational Exposure Limits for the Hanford Tank Farms  

SciTech Connect

Production of plutonium for the United States nuclear weapons program from the 1940s to the 1980s generated 53 million gallons of radioactive chemical waste, which is storedin 177 underground tanks at the Hanford Site in southeastern W 18 ashington State. Recent 19 attempts to begin the retrieval and treatment of these wastes require moving the waste to 20 more modern tanks results in potential exposure of the workers to unfamiliar odors 21 emanating from headspace in the tanks. Given the unknown risks involved, workers 22 were placed on supplied air respiratory protection. CH2M HILL, the managers of the 23 Hanford Site Tank Farms, asked an Independent Toxicology Panel (ITP) to assist them in issues relating to an Industrial Hygiene and risk assessment problem. The ITP was called upon to help determine the risk of exposure to vapors from the tanks, and in general develop a strategy for solution of the problem. This paper presents the methods used to determine the chemicals of potential concern (COPC) and the resultant development of screening values and Acceptable Occupational Exposure Limits (AOELs) for these COPCs. A total of 1,826 chemicals were inventoried and evaluated. Over 1,500 chemicals were identified in the waste tanks headspaces and more than 600 of these were assigned screening values; 72 of these compounds were recommended for AOEL development. Included in this list of 72 were 57 COPCs identified by the ITP and of these 47 were subsequently assigned AOELs. An exhaustive exposure assessment strategy was developed by the CH2M HILL industrial hygiene department to evaluate these COPCs.

Still, Kenneth; Gardner, Donald; Snyder, Robert; Anderson, Thomas; Honeyman, James; Timchalk, Charles

2010-04-01T23:59:59.000Z

99

Corrective Action Decision Document for Corrective Action Unit 127: Areas 25 and 26 Storage Tanks, Nevada Test Site, Nevada: Revision 0  

Science Conference Proceedings (OSTI)

This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of recommended corrective action alternatives (CAAs) appropriate to facilitate the closure of Corrective Action Unit (CAU) 127: Areas 25 and 26 Storage Tanks, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 127 consists of twelve corrective action sites (CASs). Corrective action investigation (CAI) activities were performed from February 24, 2003, through May 2, 2003, with additional sampling conducted on June 6, 2003, June 9, 2003, and June 24, 2003. Analytes detected during these investigation activities were evaluated against preliminary action levels to identify contaminants of concern (COCs) for each CAS, resulting in the determination that only two of the CASs did not have COCs exceeding regulatory levels. Based on the evaluation of analytical data from the CAI, review of future and current operations in Areas 25 and 26 of the Nevada Test Site, and the detailed and comparative analysis of the potential CAAs, the following alternatives were developed for consideration: (1) No Further Action is the preferred corrective action for the two CASs (25-02-13, 26-02-01) identified with no COCs; (2) Clean Closure is the preferred corrective action for eight of the CASs (25-01-05, 25-23-11, 25-12-01, 25-01-06, 26-01-01, 26-01-02, 26-99-01, 26-23-01); and (3) Closure in Place is the preferred corrective action for the remaining two CASs (25-01-07, 25-02-02). These three alternatives were judged to meet all requirements for the technical components evaluated. Additionally, these alternatives meet all applicable state and federal regulations for closure of the sites at CAU 127 and will reduce potential future exposure pathways to the contaminated media.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-09-26T23:59:59.000Z

100

Corrective Action Investigation Plan for Corrective Action Unit 557: Spills and Tank Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

Corrective Action Unit (CAU) 557 is located in Areas 1, 3, 6, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada, and is comprised of the four corrective action sites (CASs) listed below: 01-25-02, Fuel Spill 03-02-02, Area 3 Subdock UST 06-99-10, Tar Spills 25-25-18, Train Maintenance Bldg 3901 Spill Site These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 3, 2008, by representatives of the Nevada Division of Environmental Protection (NDEP); U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 557. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 557 includes the following activities: Move surface debris and/or materials, as needed, to facilitate sampling. Conduct radiological survey at CAS 25-25-18. Perform field screening. Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern are present. If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. Collect samples of investigation-derived waste, as needed, for waste management purposes.

Alfred Wickline

2008-07-01T23:59:59.000Z

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


101

Waste tank safety program annual status report for FY 1993, Task 5: Toxicology and epidemiology  

Science Conference Proceedings (OSTI)

A toxicology team independently reviewed analytical data and provided advice concerning potential health effects associated with exposure to tank-vapor constituents at the Hanford site. Most of the emphasis was directed toward Tank 241-C-103, but a preliminary assessment was also made of the toxicologic implication of the cyanide levels in the headspace of Tank 241-C-108. The objectives of this program are to (1) review procedures used for sampling vapors from various tanks, (2) identify constituents in tank-vapor samples that could be related to symptoms reported by waste-tank workers, (3) evaluate the toxicologic implications of those constituents by comparison to established toxicologic data bases, (4) provide advice for additional analytical efforts, and (5) support other activities as requested by the project manager and the cognizant Westinghouse Hanford Company Tank Vapor Issues Safety Resolution Manager.

Mahlum, D.D.; Young, J.Y.

1993-09-01T23:59:59.000Z

102

Vapor Degreasing  

Science Conference Proceedings (OSTI)

Table 6   Applications of vapor degreasing by vapor-spray-vapor systems...hardware Brass 2270 5000 Buffing compound; rouge Lacquer spray Racked work on continuous monorail Acoustic ceiling tile Steel 2720 6000 Light oil (stamping lubricant) Painting Monorail conveyor Gas meters Terneplate 4540 10,000 Light oil Painting Monorail conveyor Continuous strip, 0.25??4.1 mm...

103

Radioactive tank waste remediation focus area  

SciTech Connect

EM`s Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form.

1996-08-01T23:59:59.000Z

104

Vapor Characterization  

Science Conference Proceedings (OSTI)

... thermodynamics (that is, vapor liquid equilibrium) as ... of solids and low volatility liquids is extraordinarily ... such situations is the gas saturation method ...

2013-12-10T23:59:59.000Z

105

Numerical simulation of cloud droplet formation in a tank  

Science Conference Proceedings (OSTI)

Using the computational fluid dynamics (CFD) code FLUENT 6 together with the fine particle model (FPM), numerical simulations of droplet dynamics in a 12.4m^3 cloud tank were conducted. The coupled fields of water vapor, temperature, flow velocity, particle ... Keywords: Cloud droplet formation, Particle-dynamics modeling, Stirred tank, Turbulence

Matthias Schtze; Frank Stratmann

2008-09-01T23:59:59.000Z

106

Addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: This page that refers the reader to the SIR document for additional information The cover, title, and signature pages of the SIR document The NDEP approval letter The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: 25-25-09, Spill H940825C (from UST 25-3101-1) 25-25-14, Spill H940314E (from UST 25-3102-3) 25-25-15, Spill H941020E (from UST 25-3152-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Grant Evenson

2009-05-01T23:59:59.000Z

107

Addendum 2 to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: This page that refers the reader to the SIR document for additional information The cover, title, and signature pages of the SIR document The NDEP approval letter The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: 12-25-08, Spill H950524F (from UST 12-B-1) 12-25-10, Spill H950919A (from UST 12-COMM-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Grant Evenson

2009-05-01T23:59:59.000Z

108

Characterization and Potential Remediation Approaches for Vadose Zone Contamination at Hanford 241-SX Tank Farm  

Science Conference Proceedings (OSTI)

Unplanned releases of radioactive and hazardous wastes have occurred at the 241-SX Tank Farm on the U.S. Department of Energy Hanford Site in southeast Washington State. Interim and long-term mitigation efforts are currently under evaluation for 241-SX Tank Farm. Two contiguous interim surface barriers have been designed for deployment at 241-SX Tank Farm to reduce future moisture infiltration; however, construction of the surface barriers has been deferred to allow testing of alternative technologies for soil moisture reduction and possibly contaminant source term reduction. Previous tests performed by other organizations at the Hanford Site have demonstrated that: vadose zone desiccation using large diameter (greater than 4 inch) boreholes is feasible; under certain circumstances, mobile contaminants may be removed in addition to water vapor; and small diameter (approximately 2 inch) boreholes (such as those placed by the direct push hydraulic hammer) can be used to perform vapor extractions. Evaluation of the previous work combined with laboratory test results have led to the design of a field proof-of-principle test to remove water and possibly mobile contaminants at greater depths, using small boreholes placed with the direct push unit.

Eberlein, Susan J.; Sydnor, Harold A.; Parker, Danny L.; Glaser, Danney R.

2013-01-10T23:59:59.000Z

109

Occupational Exposure Evaluation of Complex Vapor Mixtures at the Hanford Nuclear Waste Site, Washington Work-site Vapor Characterization  

SciTech Connect

Extensive sampling and analysis has been done over the years to characterize the radioactive and chemical properties of hazardous waste stored in 177 underground tanks at the Hanford site in eastern Washington State. The purpose of these analyses was to evaluate safety and environmental concerns related to tank stability. More recently, characterization studies have broadened to evaluate potential health hazards of chemical vapors at the ground surface, where workers perform maintenance and waste transfer activities. Chemical vapor emissions from underground hazardous waste storage tanks on the Hanford site are a potential concern because workers enter the tank farms on a regular basis for waste retrievals, equipment maintenance, and surveillance. The extensive sampling done during this campaign evaluated vapor concentrations of more than 100 different chemical at 70 sites in and around one section of the tank farms. Sampling identified only four vapors (ammonia, nitrous oxide, nitrosodimethylamine, and nitrosomethylethylamine) that were present above occupational exposure limits. These elevated concentrations were detected only at exhaust stacks and passive breather filter outlets. Beyond five feet from the sources, vapors disperse rapidly. No vapors were measured above 10% of their OELs more than five feet from the source. This suggests that vapor controls can be focused on limited hazard zones around sources. (authors)

Anderson, T. J. [CH2M HILL Hanford Group, Inc. / Environmental Health, P.O. Box 1000, S7-70, Richland, WA 99352 (United States)

2006-07-01T23:59:59.000Z

110

The Validation of AIRS Retrievals of Integrated Precipitable Water Vapor Using Measurements from a Network of Ground-Based GPS Receivers over the Contiguous United States  

Science Conference Proceedings (OSTI)

A robust and easily implemented verification procedure based on the column-integrated precipitable water (IPW) vapor estimates derived from a network of ground-based global positioning system (GPS) receivers has been used to assess the quality of ...

M. K. Rama Varma Raja; Seth I. Gutman; James G. Yoe; Larry M. McMillin; Jiang Zhao

2008-03-01T23:59:59.000Z

111

Hanford double shell tank corrosion monitoring instrument tree prototype  

Science Conference Proceedings (OSTI)

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks (DSTs and SSTs). The installation of a prototype corrosion monitoring instrument tree into DST 241-A-101 was completed in December 1995. The instrument tree has the ability to detect and discriminate between uniform corrosion, pitting, and stress corrosion cracking (SCC) through the use of electrochemical noise measurements and a unique stressed element, three-electrode probe. The tree itself is constructed of AISI 304L stainless steel (UNS S30403), with probes in the vapor space, vapor/liquid interface and liquid. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other US Department of Energy (DOE) sites. Keywords: Hanford, radioactive waste, high-level waste tanks, electrochemical noise, probes, double-shell tanks, single-shell tanks, corrosion.

Nelson, J.L.; Edgemon, G.L.; Ohl, P.C.

1995-11-01T23:59:59.000Z

112

Type I Tanks  

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

I Tanks I Tanks * 12 Type I tanks were built between 1951-53 * 750,000 gallon capacity; 75 feet in diameter by 24 ½ feet high * Partial secondary containment with leak detection * Contain approximately 10 percent of the waste volume * 7 Type I tanks have leaked waste into the tank annulus; the amount of waste stored in these tanks is kept below the known leak sites that have appeared over the decades of

113

AX Tank Farm tank removal study  

Science Conference Proceedings (OSTI)

This report examines the feasibility of remediating ancillary equipment associated with the 241-AX Tank Farm at the Hanford Site. Ancillary equipment includes surface structures and equipment, process waste piping, ventilation components, wells, and pits, boxes, sumps, and tanks used to make waste transfers to/from the AX tanks and adjoining tank farms. Two remedial alternatives are considered: (1) excavation and removal of all ancillary equipment items, and (2) in-situ stabilization by grout filling, the 241-AX Tank Farm is being employed as a strawman in engineering studies evaluating clean and landfill closure options for Hanford single-shell tanks. This is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

SKELLY, W.A.

1999-02-24T23:59:59.000Z

114

AX Tank Farm tank removal study  

SciTech Connect

This report considers the feasibility of exposing, demolishing, and removing underground storage tanks from the 241-AX Tank Farm at the Hanford Site. For the study, it was assumed that the tanks would each contain 360 ft{sup 3} of residual waste (corresponding to the one percent residual Inventory target cited in the Tri-Party Agreement) at the time of demolition. The 241-AX Tank Farm is being employed as a ''strawman'' in engineering studies evaluating clean and landfill closure options for Hanford single-shell tank farms. The report is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

SKELLY, W.A.

1998-10-14T23:59:59.000Z

115

HANFORD TANK CLEANUP UPDATE  

SciTech Connect

Access to Hanford's single-shell radioactive waste storage tank C-107 was significantly improved when workers completed the cut of a 55-inch diameter hole in the top of the tank. The core and its associated cutting equipment were removed from the tank and encased in a plastic sleeve to prevent any potential spread of contamination. The larger tank opening allows use of a new more efficient robotic arm to complete tank retrieval.

BERRIOCHOA MV

2011-04-07T23:59:59.000Z

116

Tank 241-AW-101 tank characterization plan  

DOE Green Energy (OSTI)

The first section gives a summary of the available information for Tank AW-101. Included in the discussion are the process history and recent sampling events for the tank, as well as general information about the tank such as its age and the risers to be used for sampling. Tank 241-AW-101 is one of the 25 tanks on the Flammable Gas Watch List. To resolve the Flammable Gas safety issue, characterization of the tanks, including intrusive tank sampling, must be performed. Prior to sampling, however, the potential for the following scenarios must be evaluated: the potential for ignition of flammable gases such as hydrogen-air and/or hydrogen-nitrous oxide; and the potential for secondary ignition of organic-nitrate/nitrate mixtures in crust layer initiated by the burning of flammable gases or by a mechanical in-tank energy source. The characterization effort applicable to this Tank Characterization Plan is focused on the resolution of the crust burn flammable gas safety issue of Tank AW-101. To evaluate the potential for a crust burn of the waste material, calorimetry tests will be performed on the waste. Differential Scanning Calorimetry (DSC) will be used to determine whether an exothermic reaction exists.

Sathyanarayana, P.

1994-11-22T23:59:59.000Z

117

Investigation of low-cost LNG vehicle fuel tank concepts. Final report  

DOE Green Energy (OSTI)

The objective of this study was to investigate development of a low-cost liquid natural gas (LNG) vehicle fuel storage tank with low fuel boil-off, low tank pressure, and high safety margin. One of the largest contributors to the cost of converting a vehicle to LNG is the cost of the LNG fuel tank. To minimize heat leak from the surroundings into the low-temperature fuel, these tanks are designed as cryogenic dewars with double walls separated by an evacuated insulation space containing multi-layer insulation. The cost of these fuel tanks is driven by this double-walled construction, both in terms of materials and labor. The primary focus of the analysis was to try to devise a fuel tank concept that would allow for the elimination of the double-wall requirement. Results of this study have validated the benefit of vacuum/MLI insulation for LNG fuel tanks and the difficulty in identifying viable alternatives. The thickness of a non-vacuum insulation layer would have to be unreasonably large to achieve an acceptable non-venting hold time. Reasonable hold times could be achieved by using an auxiliary tank to accept boil-off vapor from a non-vacuum insulated primary tank, if the vapor in the auxiliary tank can be stored at high pressure. The primary focus of the analysis was to try to devise a fuel tank concept that allowed for the elimination of the double-wall requirement. Thermodynamic relations were developed for analyzing the fuel tank transient response to heat transfer, venting of vapor, and out-flow of either vapor or liquid. One of the major costs associated with conversion of a vehicle to LNG fuel is the cost of the LNG fuel tank. The cost of these tanks is driven by the cryogenic nature of the fuel and by the fundamental design requirements of long non-venting hold times and low storage pressure.

O`Brien, J.E.; Siahpush, A. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1998-02-01T23:59:59.000Z

118

Vapor phase heat transport systems  

DOE Green Energy (OSTI)

Vapor phase heat-transport systems are being tested in two of the passive test cells at Los Alamos. The systems consist of an active fin-and-tube solar collector and a condenser inside a water storage tank. The refrigerant, R-11, can be returned to the collector by a pump or by a self-pumping scheme. In one of the test cells the liquid was self-pumped to the roof-mounted collector 17 ft above the condenser. A mechanical valve was designed and tested that showed that the system could operate in a completely passive mode. Performance comparisons have been made with a passive water wall test cell.

Hedstrom, J.C.

1984-01-01T23:59:59.000Z

119

DuPont Chemical Vapor Technical Report  

Science Conference Proceedings (OSTI)

DuPont Safety Resources was tasked with reviewing the current chemical vapor control practices and providing preventive recommendations on best commercial techniques to control worker exposures. The increased focus of the tank closure project to meet the 2024 Tri-Party Agreement (TPA) milestones has surfaced concerns among some CH2MHill employees and other interested parties. CH2MHill is committed to providing a safe working environment for employees and desires to safely manage the tank farm operations using appropriate control measures. To address worker concerns, CH2MHill has chartered a ''Chemical Vapors Project'' to integrate the activities of multiple CH2MHill project teams, and solicit the expertise of external resources, including an independent Industrial Hygiene expert panel, a communications consultant, and DuPont Safety Resources. Over a three-month time period, DuPont worked with CH2MHill ESH&Q, Industrial Hygiene, Engineering, and the independent expert panel to perform the assessment. The process included overview presentations, formal interviews, informal discussions, documentation review, and literature review. DuPont Safety Resources concluded that it is highly unlikely that workers in the tank farms are exposed to chemicals above established standards. Additionally, the conventional and radiological chemistry is understood, the inherent chemical hazards are known, and the risk associated with chemical vapor exposure is properly managed. The assessment highlighted management's commitment to addressing chemical vapor hazards and controlling the associated risks. Additionally, we found the Industrial Hygiene staff to be technically competent and well motivated. The tank characterization data resides in a comprehensive database containing the tank chemical compositions and relevant airborne concentrations.

MOORE, T.L.

2003-10-03T23:59:59.000Z

120

A summary description of the flammable gas tank safety program  

DOE Green Energy (OSTI)

Radioactive liquid waste may produce hydrogen as result of the interaction of gamma radiation and water. If the waste contains organic chelating agents, additional hydrogen as well as nitrous oxide and ammonia may be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site in Washington State, are on a Flammable Gas Watch List. Some contain waste that produces and retains gases until large quantities of gas are released rapidly to the tank vapor space. Tanks nearly-filled to capacity have relatively little vapor space; therefore if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture could result. The most notable example of a Hanford waste tank with a flammable gas problem is tank 241-SY-101. Upon occasion waste stored in this tank has released enough flammable gas to burn if an ignition source had been present inside of the tank. Several, other Hanford waste tanks exhibit similar behavior although to a lesser magnitude. Because this behavior was hot adequately-addressed in safety analysis reports for the Hanford Tank Farms, an unreviewed safety question was declared, and in 1990 the Flammable Gas Tank Safety Program was established to address this problem. The purposes of the program are a follows: (1) Provide safety documents to fill gaps in the safety analysis reports, and (2) Resolve the safety issue by acquiring knowledge about gas retention and release from radioactive liquid waste and developing mitigation technology. This document provides the general logic and work activities required to resolve the unreviewed safety question and the safety issue of flammable gas mixtures in radioactive liquid waste storage tanks.

Johnson, G.D.; Sherwood, D.J.

1994-10-01T23:59:59.000Z

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


121

Tank 241-S-107 tank characterization plan  

Science Conference Proceedings (OSTI)

The Defense Nuclear Facilities Safety Board (DNFSB) has advised the Department of Energy (DOE) to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues (Conway 1993). The data quality objective (DQO) process was chosen as a tool to be used to identify the sampling and analytical needs for the resolution of safety issues. As a result, a revision in the Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestone M-44 has been made, which states that ``A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process``. This document satisfies that requirement for tank 241-S-107 (S-107) sampling activities. The report gives a summary of descriptive information available on Tank S-107. Included are the present status and physical description of the tank, its age, process history, and expected tank contents from previous sampling and analytical data. The different types of waste, by layer, for Tank S-107 will also be discussed. As of December 1994, Tank S-107 has been categorized as sound and was partially isolated in December 1982. It is a low-heat load tank and is awaiting stabilization. Tank S-107 is expected to contain two primary layers of waste. The bottom layer should contain a mixture of REDOX waste and REDOX cladding waste. The second layer contains S1 saltcake (waste generated from the 242-S evaporator/crystallizer from 1973 until 1976), and S2 salt slurry (waste generated from the 242-S evaporator-crystallizer from 1977 until 1980).

Jo, J.

1995-04-06T23:59:59.000Z

122

Septic Tanks (Oklahoma)  

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

A license from the Department of Environmental Quality is required for cleaning or pumping of septic tanks or holding tanks and disposing of sewage or septage. The rules for the license are...

123

Tank 241-B-112 tank characterization plan  

Science Conference Proceedings (OSTI)

The Defense Nuclear Facilities Safety Board (DNFSB) has advised the US Department of Energy (DOE) to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The data quality objective (DQO) process was chosen as a tool to be used to identify sampling and analytical needs for the resolution of safety issues. As a result, a revision in the Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) milestone M-44-00 has been made, which states that ``A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process... Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.`` This document satisfies that requirement for tank 241-B-112 (B-112). Tank B-112 is currently a non-Watch List tank; therefore, the only applicable DQO as of January 1995 is the Tank Safety Screening Data Quality Objective, which is described below. Tank B-112 is expected to have three primary layers. A bottom layer of sludge consisting of second-cycle waste, followed by a layer of BY saltcake and a top layer of supernate.

Schreiber, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

1995-02-06T23:59:59.000Z

124

DIESEL FUEL TANK FOUNDATIONS  

DOE Green Energy (OSTI)

The purpose of this analysis is to design structural foundations for the Diesel Fuel Tank and Fuel Pumps.

M. Gomez

1995-01-18T23:59:59.000Z

125

Tank 241-AZ-102 tank characterization plan  

Science Conference Proceedings (OSTI)

The Defense Nuclear Facilities Safety Board has advised the DOE to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The Data Quality Objective (DQO) process was chosen as a tool to be used in the resolution of safety issues. As a result, a revision in the Federal Facilities Agreement and Consent Order (Tri-Party Agreement) milestone M-44 has been made, which states that ``A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process ... Development of TCPs by the DQO process is intended to allow users to ensure their needs will be met and that resources are devoted to gaining only necessary information``. This document satisfies that requirement for tank 241-AZ-102 (AZ-102) sampling activities. Tank AZ-102 is currently a non-Watch List tank, so the only DQOs applicable to this tank are the safety screening DQO and the compatibility DQO, as described below. The current contents of Tank AZ-102, as of October 31, 1994, consisted of 3,600 kL (950 kgal) of dilute non-complexed waste and aging waste from PUREX (NCAW, neutralized current acid waste). Tank AZ-102 is expected to have two primary layers. The bottom layer is composed of 360 kL of sludge, and the top layer is composed of 3,240 kL of supernatant, with a total tank waste depth of approximately 8.9 meters.

Schreiber, R.D.

1995-02-06T23:59:59.000Z

126

Tank 241-AZ-101 tank characterization plan  

Science Conference Proceedings (OSTI)

The Defense Nuclear Facilities Safety Board has advised the DOE to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The Data Quality Objective (DQO) process was chosen as a tool to be used in the resolution of safety issues. As a result, A revision in the Federal Facilities Agreement and Consent Order (Tri-Party Agreement) milestone M-44 has been made, which states that ``A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process. Development of TCPs by the DQO process is intended to allow users to ensure their needs will be met and that resources are devoted to gaining only necessary information``. This document satisfies that requirement for Tank 241-AZ-101 (AZ-101) sampling activities. Tank AZ-101 is currently a non-Watch List tank, so the only DQOs applicable to this tank are the safety screening DQO and the compatibility DQO, as described below. The contents of Tank AZ-101, as of October 31, 1994, consisted of 3,630 kL (960 kgal) of dilute non-complexed waste and aging waste from PUREX (NCAW, neutralized current acid waste). Tank AZ-101 is expected to have two primary layers. The bottom layer is composed of 132 kL of sludge, and the top layer is composed of 3,500 kL of supernatant, with a total tank waste depth of approximately 8.87 meters.

Schreiber, R.D.

1995-02-06T23:59:59.000Z

127

Summary - Tank 48 at the Savannah River Site  

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

Tank 48 Tank 48 ETR Report Date: August 2006 ETR-2 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Tank 48 at the Savannah River Site (SRS) Why DOE-EM Did This Review Tank 48 is a 1.3 million gallon tank with full secondary containment, located and interconnected within the SRS tank system that will play a very important role in removal and processing of high-level waste (HLW) in the years ahead. However, the tank is currently isolated from the system and unavailable for use, because its contents. It contains approximately 250,000 gallons of salt solution containing Cesium-137 and other radioisotopes which are contaminated with significant quantities of tetraphenylborate (TPB), a material which

128

Approach for tank safety characterization of Hanford site waste  

Science Conference Proceedings (OSTI)

The overall approach and associated technical basis for characterizing Hanford Site waste to help identify and resolve Waste Tank Safety Program safety issues has been summarized. The safety issues include flammable gas, noxious vapors, organic solvents, condensed-phase exothermic reactions (ferrocyanide and organic complexants), criticality, high heat, and safety screening. For the safety issues involving chemical reactions (i.e., flammable gas, organic solvents, ferrocyanide, and organic complexants), the approach to safety characterization is based on the fact that rapid exothermic reactions cannot occur if either fuel, oxidizer, or temperature (initiators) is not sufficient or controlled. The approach to characterization has been influenced by the progress made since mid-1993: (1) completion of safety analyses on ferrocyanide, criticality, organic solvent in tank 241-C-103, and sludge dryout. (2) successful mitigation of tank 241-SY-101; (3) demonstration of waste aging in laboratory experiments and from waste sampling, and (4) increased understanding of the information that can be obtained from headspace sampling. Headspace vapor sampling is being used to confirm that flammable gas does not accumulate in the single-shell tanks, and to determine whether organic solvents are present. The headspaces of tanks that may contain significant quantities of flammable gas will be monitored continuously using standard hydrogen monitors. For the noxious vapors safety issue, characterization will consist of headspace vapor sampling of most of the Hanford Site waste tanks. Sampling specifically for criticality is not required to confirm interim safe storage; however, analyses for fissile material will be conducted as waste samples are obtained for other reasons. High-heat tanks will be identified through temperature monitoring coupled with thermal analyses.

Meacham, J.E.; Babad, H.; Cash, R.J.; Dukelow, G.T.; Eberlein, S.J.; Hamilton, D.W.; Johnson, G.D.; Osborne, J.W.; Payne, M.A.; Sherwood, D.J. [and others

1995-03-01T23:59:59.000Z

129

Predicting flammable gas mixtures in Hanford double-contained receiver tanks  

DOE Green Energy (OSTI)

This study presents a methodology to estimate the maximum concentrations of flammable gases (ammonia, hydrogen, and methane) which could exist in the vapor space of a double-contained receiver tank (DCRT). DCRTs are temporary storage tanks which receive highly radioactive liquid wastes from salt well pumping of Hanford single-shell tanks (SST). The methodology of this study could be used in other applications involving the storage and transfer of radioactive liquid wastes which generate or contain various dissolved flammable gases.

Hedengren, D.C.

1998-05-13T23:59:59.000Z

130

Comprehensive monitoring report for underground storage tanks 1219-U, 1222-U, 2082-U, and 2068-U at the Rust Garage Facility, Buildings 9720-15 and 9754-1  

SciTech Connect

The purpose of this document is to provide hydrogeologic, geochemical, and vapor monitoring data required for comprehensive monitoring of underground storage tanks at the Rust Garage Facility.

Not Available

1994-06-01T23:59:59.000Z

131

Stennis Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Stennis Tow Tank Stennis Tow Tank Jump to: navigation, search Basic Specifications Facility Name Stennis Tow Tank Overseeing Organization United States Geological Survey, HIF Hydrodynamic Testing Facility Type Tow Tank Length(m) 137.2 Beam(m) 3.7 Depth(m) 3.7 Cost(per day) $1200(+ setup charges) Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 4.6 Length of Effective Tow(m) 114.3 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Description Fully automated data collection/carriage control computer system for mechanical current meters only. Number of channels 4 Cameras None Available Sensors Acceleration, Velocity Data Generation Capability

132

Penn Reverberant Tank | Open Energy Information  

Open Energy Info (EERE)

Penn Reverberant Tank Penn Reverberant Tank Jump to: navigation, search Basic Specifications Facility Name Penn Reverberant Tank Overseeing Organization Pennsylvania State University Hydrodynamics Hydrodynamic Testing Facility Type Reverberant Tank Length(m) 7.9 Beam(m) 5.3 Depth(m) 5.5 Water Type Freshwater Cost(per day) Contact POC Special Physical Features Structurally isolated hydrodynamic acoustics testing. Lined with an absorber on four sides and bottom with three 0.5x0.5 meter underwater viewing ports. Mechanical oscillation of a small-scale test unit-simulation of oscillating flow for wave or tidal excitation. Towing Capabilities Towing Capabilities None Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities

133

Vapor Pressures and Heats of Vaporization of Primary Coal Tars  

Office of Scientific and Technical Information (OSTI)

/ PC92544-18 / PC92544-18 VAPOR PRESSURES AND HEATS OF VAPORIZATION OF PRIMARY COAL TARS FINAL REPORT Grant Dates: August, 1992 - November, 1996 Principal Authors: Eric M. Suuberg (PI) and Vahur Oja Report Submitted: April, 1997 Revised: July, 1997 Grant Number: DE-FG22-92PC92544 Report Submitted by: ERIC M. SUUBERG DIVISION OF ENGINEERING BROWN UNIVERSITY PROVIDENCE, RI 02912 TEL. (401) 863-1420 Prepared For: U. S. DEPT. OF ENERGY FEDERAL ENERGY TECHNOLOGY CENTER P.O. BOX 10940 PITTSBURGH, PA 15236 DR. KAMALENDU DAS, FETC, MORGANTOWN , WV TECHNICAL PROJECT OFFICER "US/DOE Patent Clearance is not required prior to the publication of this document" ii United States Government Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any

134

Engineering task plan for Tanks 241-AN-103, 104, 105 color video camera systems  

DOE Green Energy (OSTI)

This Engineering Task Plan (ETP) describes the design, fabrication, assembly, and installation of the video camera systems into the vapor space within tanks 241-AN-103, 104, and 105. The one camera remotely operated color video systems will be used to observe and record the activities within the vapor space. Activities may include but are not limited to core sampling, auger activities, crust layer examination, monitoring of equipment installation/removal, and any other activities. The objective of this task is to provide a single camera system in each of the tanks for the Flammable Gas Tank Safety Program.

Kohlman, E.H.

1994-11-17T23:59:59.000Z

135

Tank 48 Treatment Process  

-Reduce elutriation of particulates containing coal System planning: Sludge batch planning/DWPF WAC-Evaluate Tank Farm and DWPF coal capability

136

Review of High Level Waste Tanks Ultrasonic Inspection Data  

SciTech Connect

A review of the data collected during ultrasonic inspection of the Type I high level waste tanks has been completed. The data was analyzed for relevance to the possibility of vapor space corrosion and liquid/air interface corrosion. The review of the Type I tank UT inspection data has confirmed that the vapor space general corrosion is not an unusually aggressive phenomena and correlates well with predicted corrosion rates for steel exposed to bulk solution. The corrosion rates are seen to decrease with time as expected. The review of the temperature data did not reveal any obvious correlations between high temperatures and the occurrences of leaks. The complex nature of temperature-humidity interaction, particularly with respect to vapor corrosion requires further understanding to infer any correlation. The review of the waste level data also did not reveal any obvious correlations.

Wiersma, B

2006-03-09T23:59:59.000Z

137

Tank Stabilization September 30, 1999 Summary  

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

United States Court Easter District of Washington United States Court Easter District of Washington Consent Decree (as amended on September 19, 2000.) State Washington Agreement Type Consent Decree Legal Driver(s) RCRA Scope Summary Renegotiate a schedule to pump liquid radioactive hazardous waste from single-shell tanks to double-shell tanks Parties DOE; State of Washington, Department of Ecology Date 09/30/1999; Amended 09/19/2000 SCOPE * Address DOE's obligations to the State of Washington, Department of Ecology concerning missed and remaining milestones under the Hanford Federal Facility Agreement (HFFACO) and Consent Order of May 15, 1989. * Establish a judicially enforceable schedule for pumping radioactive hazardous waste from single-shell to double-shell tanks. ESTABLISHING MILESTONES

138

Calibrated vapor generator source  

DOE Patents (OSTI)

A portable vapor generator is disclosed that can provide a controlled source of chemical vapors, such as, narcotic or explosive vapors. This source can be used to test and calibrate various types of vapor detection systems by providing a known amount of vapors to the system. The vapor generator is calibrated using a reference ion mobility spectrometer. A method of providing this vapor is described, as follows: explosive or narcotic is deposited on quartz wool, placed in a chamber that can be heated or cooled (depending on the vapor pressure of the material) to control the concentration of vapors in the reservoir. A controlled flow of air is pulsed over the quartz wool releasing a preset quantity of vapors at the outlet.

Davies, John P. (Idaho Falls, ID); Larson, Ronald A. (Idaho Falls, ID); Goodrich, Lorenzo D. (Shelley, ID); Hall, Harold J. (Idaho Falls, ID); Stoddard, Billy D. (Idaho Falls, ID); Davis, Sean G. (Idaho Falls, ID); Kaser, Timothy G. (Idaho Falls, ID); Conrad, Frank J. (Albuquerque, NM)

1995-01-01T23:59:59.000Z

139

Calibrated vapor generator source  

DOE Patents (OSTI)

A portable vapor generator is disclosed that can provide a controlled source of chemical vapors, such as, narcotic or explosive vapors. This source can be used to test and calibrate various types of vapor detection systems by providing a known amount of vapors to the system. The vapor generator is calibrated using a reference ion mobility spectrometer. A method of providing this vapor is described, as follows: explosive or narcotic is deposited on quartz wool, placed in a chamber that can be heated or cooled (depending on the vapor pressure of the material) to control the concentration of vapors in the reservoir. A controlled flow of air is pulsed over the quartz wool releasing a preset quantity of vapors at the outlet. 10 figs.

Davies, J.P.; Larson, R.A.; Goodrich, L.D.; Hall, H.J.; Stoddard, B.D.; Davis, S.G.; Kaser, T.G.; Conrad, F.J.

1995-09-26T23:59:59.000Z

140

Oak Ridge National Laboratory TRU Waste Processing Center Tank Waste Processing Supernate Processing System  

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

TRU Waste Processing Center TRU Waste Processing Center ORNL TRU Waste Processing Center Tank Waste Processing Supernate (SN) Processing System Presented by Don F. Gagel Vice President and Chief Technology Officer EnergX LLC ORNL TRU Waste Processing Center 1/21/09 2 SRS Technology Transfer, ORNL SN Process Overview SN Process Facility ORNL TRU Waste Processing Center 3 Waste Concentration Using Evaporator Evaporator Concentrates Waste Vapor stream superheated and HEPA-filtered Vapor stream exhausted to main ventilation system Supernate Pump and Evaporator Discharge Pump circulate waste between selected tank and evaporator during concentration. Evaporator Discharge Pump Supernate Pump Supernate Tank Evaporator Exhaust Blower ORNL TRU Waste Processing Center 4 Tank Sampling/ Transfer To Dryer Tank

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


141

" Million Housing Units, Final...  

U.S. Energy Information Administration (EIA) Indexed Site

that do not contain a storage tank. The water is only heated as it passes through the heat exchanger. 3Use of a water heater for another housing unit also includes the use of...

142

" Million Housing Units, Final...  

U.S. Energy Information Administration (EIA) Indexed Site

that do not contain a storage tank. The water is only heated as it passes through the heat exchanger. 4Use of a water heater for another housing unit also includes the use of...

143

Safety evaluation for packaging (onsite) nitrogen trailers propane tanks  

SciTech Connect

The purpose of the Safety Evaluation for Packaging (SEP) is the evaluation and authorization of the onsite transport of propane tanks that are mounted on the Lockheed Martin Hanford Corporation Characterization Project`s nitrogen trailers. This SEP authorizes onsite transport of the nitrogen trailers, including the propane tanks, until May 31, 1998. The three nitrogen trailers (HO-64-4966, HO-64-4968, and HO-64-5170) are rated for 1,361 kg (30,000 lb) and are equipped with tandem axles and pintel hitches. Permanently mounted on each trailer is a 5,678 L (1,500 gal) cryogenic dewar that is filled with nitrogen, and a propane fired water bath vaporizer system, and a 454 L (1 20 gal) propane tank. The nitrogen trailer system is operated only when it is disconnected from the tow vehicle and is leveled and stabilized. When the trailers are transported, the propane tanks are isolated via closed supply valves.

Ferrell, P.C.

1998-01-28T23:59:59.000Z

144

Radiological Source Terms for Tank Farms Safety Analysis  

Science Conference Proceedings (OSTI)

This document provides Unit Liter Dose factors, atmospheric dispersion coefficients, breathing rates and instructions for using and customizing these factors for use in calculating radiological doses for accident analyses in the Hanford Tank Farms.

COWLEY, W.L.

2000-06-27T23:59:59.000Z

145

Hanford Tank Waste Residuals  

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

Hanford Hanford Tank Waste Residuals DOE HLW Corporate Board November 6, 2008 Chris Kemp, DOE ORP Bill Hewitt, YAHSGS LLC Hanford Tanks & Tank Waste * Single-Shell Tanks (SSTs) - ~27 million gallons of waste* - 149 SSTs located in 12 SST Farms - Grouped into 7 Waste Management Areas (WMAs) for RCRA closure purposes: 200 West Area S/SX T TX/TY U 200 East Area A/AX B/BX/BY C * Double-Shell Tanks (DSTs) - ~26 million gallons of waste* - 28 DSTs located in 6 DST Farms (1 West/5 East) * 17 Misc Underground Storage Tanks (MUST) * 43 Inactive MUST (IMUST) 200 East Area A/AX B/BX/BY C * Volumes fluctuate as SST retrievals and 242-A Evaporator runs occur. Major Regulatory Drivers * Radioactive Tank Waste Materials - Atomic Energy Act - DOE M 435.1-1, Ch II, HLW - Other DOE Orders * Hazardous/Dangerous Tank Wastes - Hanford Federal Facility Agreement and Consent Order (TPA) - Retrieval/Closure under State's implementation

146

Near Tank Treatment System  

Hanford High Level Waste: S/SX Tanks TEM Images of Actual Waste Boehmite 7 (a) 0.2 m (b) 0.2 m (c) 0.5 m (d) 0.2 m U and Mn particles . Near Tank Treatment System

147

SRS Tank Closure Regulatory Developments  

Order 435.1 and State-required documents are prepared and in review Tank-specific documents for Tanks 18, 19, 5 and ... Solids Volume (gal) Solids ...

148

Tank characterization reference guide  

Science Conference Proceedings (OSTI)

Characterization of the Hanford Site high-level waste storage tanks supports safety issue resolution; operations and maintenance requirements; and retrieval, pretreatment, vitrification, and disposal technology development. Technical, historical, and programmatic information about the waste tanks is often scattered among many sources, if it is documented at all. This Tank Characterization Reference Guide, therefore, serves as a common location for much of the generic tank information that is otherwise contained in many documents. The report is intended to be an introduction to the issues and history surrounding the generation, storage, and management of the liquid process wastes, and a presentation of the sampling, analysis, and modeling activities that support the current waste characterization. This report should provide a basis upon which those unfamiliar with the Hanford Site tank farms can start their research.

De Lorenzo, D.S.; DiCenso, A.T.; Hiller, D.B.; Johnson, K.W.; Rutherford, J.H.; Smith, D.J. [Los Alamos Technical Associates, Kennewick, WA (United States); Simpson, B.C. [Westinghouse Hanford Co., Richland, WA (United States)

1994-09-01T23:59:59.000Z

149

Gregory H. Friedman: Before the United States Senate Committee on Energy  

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

United States Senate Committee on United States Senate Committee on Energy and Natural Resources Gregory H. Friedman: Before the United States Senate Committee on Energy and Natural Resources June 17, 2004 Before the United States Senate Committee on Energy and Natural Resources Statement of Gregory H. Friedman, Inspector General U.S. Department of Energy Request to testify regarding recent allegations associated with occupational medical services and tank farm vapor exposures at the Hanford Site. During the Cold War, the United States' nuclear weapons complex generated large amounts of hazardous and radioactive waste. The Department of Energy is responsible for the cleanup of numerous contaminated sites and facilities that supported nuclear weapons production activities. Associated with this is the need to protect the safety and health of the

150

Tank 241-U-202 tank characterization plan  

Science Conference Proceedings (OSTI)

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-202.

Schreiber, R.D.

1995-02-21T23:59:59.000Z

151

Tank 241-BY-106 tank characterization plan  

Science Conference Proceedings (OSTI)

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, PNL 325 Analytical Chemistry Laboratory, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-106.

Schreiber, R.D.

1995-01-24T23:59:59.000Z

152

Tank 241-C-102 tank characterization plan  

SciTech Connect

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from tank 241-C-102.

Schreiber, R.D.

1995-01-01T23:59:59.000Z

153

Pressurizer tank upper support  

DOE Patents (OSTI)

A pressurizer tank in a pressurized water nuclear reactor is mounted between structural walls of the reactor on a substructure of the reactor, the tank extending upwardly from the substructure. For bearing lateral loads such as seismic shocks, a girder substantially encircles the pressurizer tank at a space above the substructure and is coupled to the structural walls via opposed sway struts. Each sway strut is attached at one end to the girder and at an opposite end to one of the structural walls, and the sway struts are oriented substantially horizontally in pairs aligned substantially along tangents to the wall of the circular tank. Preferably, eight sway struts attach to the girder at 90[degree] intervals. A compartment encloses the pressurizer tank and forms the structural wall. The sway struts attach to corners of the compartment for maximum stiffness and load bearing capacity. A valve support frame carrying the relief/discharge piping and valves of an automatic depressurization arrangement is fixed to the girder, whereby lateral loads on the relief/discharge piping are coupled directly to the compartment rather than through any portion of the pressurizer tank. Thermal insulation for the valve support frame prevents thermal loading of the piping and valves. The girder is shimmed to define a gap for reducing thermal transfer, and the girder is free to move vertically relative to the compartment walls, for accommodating dimensional variation of the pressurizer tank with changes in temperature and pressure. 10 figures.

Baker, T.H.; Ott, H.L.

1994-01-11T23:59:59.000Z

154

Pressurizer tank upper support  

DOE Patents (OSTI)

A pressurizer tank in a pressurized water nuclear reactor is mounted between structural walls of the reactor on a substructure of the reactor, the tank extending upwardly from the substructure. For bearing lateral loads such as seismic shocks, a girder substantially encircles the pressurizer tank at a space above the substructure and is coupled to the structural walls via opposed sway struts. Each sway strut is attached at one end to the girder and at an opposite end to one of the structural walls, and the sway struts are oriented substantially horizontally in pairs aligned substantially along tangents to the wall of the circular tank. Preferably, eight sway struts attach to the girder at 90.degree. intervals. A compartment encloses the pressurizer tank and forms the structural wall. The sway struts attach to corners of the compartment for maximum stiffness and load bearing capacity. A valve support frame carrying the relief/discharge piping and valves of an automatic depressurization arrangement is fixed to the girder, whereby lateral loads on the relief/discharge piping are coupled directly to the compartment rather than through any portion of the pressurizer tank. Thermal insulation for the valve support frame prevents thermal loading of the piping and valves. The girder is shimmed to define a gap for reducing thermal transfer, and the girder is free to move vertically relative to the compartment walls, for accommodating dimensional variation of the pressurizer tank with changes in temperature and pressure.

Baker, Tod H. (O' Hara Township, Allegheny County, PA); Ott, Howard L. (Kiski Township, Armstrong County, PA)

1994-01-01T23:59:59.000Z

155

Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank  

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

- Tank Waste Treatment and Immobilization Plant - - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report This is a comprehensive review ofthe Hanford WTP estimate at completion - assessing the project scope, contract requirements, management execution plant, schedule, cost estimates, and risks. Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report More Documents & Publications TBH-0042 - In the Matter of Curtis Hall

156

Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank  

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

ETR Tank Waste Treatment and Immobilization Plant - Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Full Document and Summary Versions are available for download Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Summary - Flowsheet for the Hanford Waste Treatment Plant More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

157

Mercury Vapor Pressure Correlation  

Science Conference Proceedings (OSTI)

An apparent difference between the historical mercury vapor concentration equations used by the mercury atmospheric measurement community ...

2012-10-09T23:59:59.000Z

158

UNIT OPERATION Separator, 3 phase separator, tank.  

E-Print Network (OSTI)

gas volume . . valve, control system . column, reactor . 2. ROATING EQUIPMENT. . Centrifugal compressor, expander, reciprocating compressor centrifugal pump . -Centrifugal compressor expander Inlet output connection , power source volume head . motor

Hong, Deog Ki

159

Tank 48 - Chemical Destruction  

SciTech Connect

Small tank copper-catalyzed peroxide oxidation (CCPO) is a potentially viable technology to facilitate the destruction of tetraphenylborate (TPB) organic solids contained within the Tank 48H waste at the Savannah River Site (SRS). A maturation strategy was created that identified a number of near-term development activities required to determine the viability of the CCPO process, and subsequent disposition of the CCPO effluent. Critical activities included laboratory-scale validation of the process and identification of forward transfer paths for the CCPO effluent. The technical documentation and the successful application of the CCPO process on simulated Tank 48 waste confirm that the CCPO process is a viable process for the disposition of the Tank 48 contents.

Simner, Steven P.; Aponte, Celia I.; Brass, Earl A.

2013-01-09T23:59:59.000Z

160

Cryogenic Fuel Tank Draining  

E-Print Network (OSTI)

One of the technological challenges in designing advanced hypersonic aircraft and the next generation of spacecraft is developing reusable flight-weight cryogenic fuel tanks. As an aid in the design and analysis of these cryogenic tanks, a computational fluid dynamics (CFD) model has been developed specifically for the analysis of flow in a cryogenic fuel tank. This model employs the full set of Navier-Stokes equations, except that viscous dissipation is neglected in the energy equation. An explicit finite difference technique in two-dimensional generalized coordinates, approximated to second-order accuracy in both space and time is used. The stiffness resulting from the low Mach number is resolved by using artificial compressibility. The model simulates the transient, two-dimensional draining of a fuel tank cross section. To calculate the slosh wave dynamics the interface between the ullage gas and liquid fuel is modeled as a free surface. Then, experimental data for free convection inside a horizontal cylinder are compared with model results. Finally, cryogenic tank draining calculations are performed with three different wall heat fluxes to demonstrate the effect of wall heat flux on the internal tank flow field.

Analysis Model Donald; Donald Greer

1999-01-01T23:59:59.000Z

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


161

Tank characterization report for Single-Shell Tank 241-BX-107  

SciTech Connect

This study examined and assessed the status, safety issues, composition, and distribution of the wastes contained in the tank 241-BX-107. Historical and most recent information, ranging from engineering structural assessment experiments, process history, monitoring and remediation activities, to analytical core sample data, were compiled and interpreted in an effort to develop a realistic, contemporary profile for the tank BX-107 contents. The results of this is study revealed that tank BX-107, a 2,006,050 L (530,000 gal) cylindrical single-shell, dished-bottom carbon-steel tank in the 200 East Area of the Hanford Site, was classified as sound. It has been interim stabilized and thus contains less than 189,250 L (50,000 gal) of interstitial liquid, and less than 18,925 L (5,000 gal) of supernatant. It has also been partially interim isolated, whereby all inlets to the tank are sealed to prevent inadvertent addition of liquid. At a residual waste level of {approximately}3.07 m (120.7 {+-} 2 in. from sidewall bottom or {approximately}132.9 in. from center bottom), it is estimated that the tank BX-107 contents are equivalent to 1,305,825 L (345,000 gal). The vapor space pressure is at atmospheric. The latest temperature readings, which were taken in July 1994, show a moderate temperature value of 19{degrees}C (66{degrees}F). Two supernatant samples were collected in 1974 and 1990, prior to interim stabilization. Sludge core samples were obtained in 1979 and 1992.

Raphael, G.F.

1994-09-01T23:59:59.000Z

162

The Hanford site tank waste remediation system technical strategy  

SciTech Connect

The US Department of Energy`s Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of radioactive tank the United States. High-level radioactive waste has been stored in large underground tanks since 1944. Approximately 230,000 m{sup 3} (61 Mgal) of caustic liquids, slurries, saltcakes, and sludges have accumulated in 177 tanks. In addition, significant amounts of {sup 90}S and {sup 137}Cs were removed from the tank waste, converted to salts, doubly encapsulated in metal containers, and stored in water basins. A Tank Waste Remediation System Program was established by the US DOE Energy in 1991 to safely manage and immobilize these wastes for permanent disposal of the high-level waste fraction in a geologic repository. The technical strategy to manage and dispose of these wastes has been revised and successfully negotiated with the regulatory agencies.

Wodrich, D.D.

1994-04-01T23:59:59.000Z

163

Alabama Underground Storage Tank And Wellhead Protection Act (Alabama) |  

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

Alabama Underground Storage Tank And Wellhead Protection Act Alabama Underground Storage Tank And Wellhead Protection Act (Alabama) Alabama Underground Storage Tank And Wellhead Protection Act (Alabama) < Back Eligibility Commercial Construction Industrial Municipal/Public Utility Savings Category Buying & Making Electricity Water Home Weatherization Program Info State Alabama Program Type Environmental Regulations The department, acting through the commission, is authorized to promulgate rules and regulations governing underground storage tanks and is authorized to seek the approval of the United States Environmental Protection Agency to operate the state underground storage tank program in lieu of the federal program. In addition to specific authorities provided by this chapter, the department is authorized, acting through the commission, to

164

Status report for inactive miscellaneous underground storage tanks at Hanford Site 200 Areas  

DOE Green Energy (OSTI)

The purpose of this status report is to summarize updated data and information from the FY 1994 strategy plan that is associated with inactive miscellaneous underground storage tanks (IMUSTs). Assumptions and processes to assess potential risks and operational concerns are documented in this report. Safety issue priorities are ranked based on a number of considerations. Sixty-three IMUSTs have been Identified and placed on the official IMUST list. All the tanks are associated with past Hanford Site operations. Of the 63 tanks., 19 are catch tanks, 20 are vault tanks, 3 are neutralization tanks, 8 are settling tanks, 2 are solvent makeup tanks used to store hexone, 2 are flush tanks, 3 are decontamination tanks, 1 is a diverter station, 1 is a receiver tank, 1 is an experimental tank, and 3 are waste handling tanks. It is important to proactively deal with the risks Imposed by these 63 tanks, and at the same time not jeopardize the existing commitments and schedules for mitigating and resolving identified safety issues related to the 177 SSTs and DSTS. Access controls and signs have been placed on all but the three official IMUSTs added most recently. An accelerated effort to identify authorization documents and perform unreviewed safety question (USQ) screening has been completed. According to a set of criteria consistent with the safety screening data quality objective (DQO) process, 6 IMUSTs are ranked high related to the hydrogen generation potential safety Issue, 1 is ranked high related to the ferrocyanide potential safety issue, 6 are ranked high related to the flammability potential safety issue, and 25 are ranked high related to the vapor emissions potential safety issue.

Powers, T.B.

1995-10-01T23:59:59.000Z

165

AN ASSESSMENT OF THE SERVICE HISTORY AND CORROSION SUSCEPTIBILITY OF TYPE IV WASTE TANKS  

SciTech Connect

Type IV waste tanks were designed and built to store waste that does not require auxiliary cooling. Each Type IV tank is a single-shell tank constructed of a steel-lined pre-stressed concrete tank in the form of a vertical cylinder with a concrete domed roof. There are four such tanks in F-area, Tanks 17-20F, and four in H-Area, Tanks 21-24H. Leak sites were discovered in the liners for Tanks 19 and 20F in the 1980's. Although these leaks were visually observed, the investigation to determine the mechanism by which the leaks had occurred was not completed at that time. Therefore, a concern was raised that the same mechanism which caused the leak sites in the Tanks in F-area may also be operable in the H-Area tanks. Data from the construction of the tanks (i.e., certified mill test reports for the steel, no stress-relief), the service history (i.e., waste sample data, temperature data), laboratory tests on actual wastes and simulants (i.e., electrochemical testing), and the results of the visual inspections were reviewed. The following observations and conclusions were made: (1) Comparison of the compositional and microstructural features indicate that the A212 material utilized for construction of the H-Area tanks are far more resistant to SCC than the A285 materials used for construction of the F-Area tanks. (2) A review of the materials of construction, temperature history, service histories concluded that F-Area tanks likely failed by caustic stress corrosion cracking. (3) The environment in the F-Area tanks was more aggressive than that experienced by the H-Area tanks. (4) Based on a review of the service history, the H-Area tanks have not been exposed to an environment that would render the tanks susceptible to either nitrate stress corrosion cracking (i.e., the cause of failures in the Type I and II tanks) or caustic stress corrosion cracking. (5) Due to the very dilute and uninhibited solutions that have been stored in Tank 23H, vapor space corrosion has occurred on some of areas of the liner. The mild pitting that was observed is broad and shallow and has no structural impact. Further significant pit growth has not been observed since the 1980's.

Wiersma, B

2008-09-18T23:59:59.000Z

166

Tank waste remediation system fiscal year 1998 multi-year work plan WBS 1.1  

Science Conference Proceedings (OSTI)

The TWRS Project Mission is to manage and immobilize for disposal the Hanford Site radioactive tank waste and cesium (Cs)/strontium (Sr) capsules in a safe, environmentally sound, and cost-effective manner. The scope includes all activities needed to (1) resolve safety issues; (2) operate, maintain, and upgrade the tank farms and supporting infrastructure; (3) characterize, retrieve, pretreat, and immobilize the waste for disposal and tank farm closure; and (4) use waste minimization and evaporation to manage tank waste volumes to ensure that the tank capacities of existing DSTs are not exceeded. The TWRS Project is responsible for closure of assigned operable units and D&D of TWRS facilities.

Lenseigne, D.L., Westinghouse Hanford, Richland, WA

1997-09-15T23:59:59.000Z

167

Deflagration studies on waste Tank 101-SY: Test plan  

DOE Green Energy (OSTI)

Waste slurries produced during the recovery of plutonium and uranium from irradiated fuel are stored in underground storage tanks. While a variety of waste types have been generated, of particular concern are the wastes stored in Tank 101-SY. A slurry growth-gas evolution cycle has been observed since 1981. The waste consists of a thick slurry, consisting of a solution high in NaOH, NaNO{sub 3}, NaAlO{sub 2}, dissolved organic complexants (EDTA, HEDTA, NTA, and degradation products), other salts (sulfates and phosphates), and radionuclides (primarily cesium and strontium). During a gas release the major gaseous species identified include: hydrogen and nitrous oxide (N{sub 2}O). Significant amounts of nitrogen may also be present. Traces of ammonia, carbon oxides, and other nitrogen oxides are also detected. Air and water vapor are also present in the tank vapor space. The purpose of the deflagration study is to determine risks of the hydrogen, nitrous oxide, nitrogen, and oxygen system. To be determined are pressure and temperature as a function of composition of reacting gases and the concentration of gases before and after the combustion event. Analyses of gases after the combustion event will be restricted to those tests that had an initial concentration of {le}8% hydrogen. This information will be used to evaluate safety issues related to periodic slurry growth and flammable gas releases from Tank 101-SY. the conditions to be evaluated will simulate gases in the vapor space above the salt cake as well as gases that potentially are trapped in pockets within/under the waste. The deflagration study will relate experimental laboratory results to conditions in the existing tanks.

Cashdollar, K.L.; Zlochower, I.A.; Hertzberg, M.

1991-07-01T23:59:59.000Z

168

Action plan for response to abnormal conditions in Hanford high level radioactive liquid waste storage tanks containing flammable gases. Revision 1  

DOE Green Energy (OSTI)

Radioactive liquid waste tends to produce hydrogen as a result of the interaction of gamma radiation and water. In tanks containing organic chelating agents, additional hydrogen gas as well as nitrous oxide and ammonia can be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site, contain waste that retains the gases produced in them until large quantities are released rapidly to the tank vapor space. Tanks filled to near capacity have relatively little vapor space; therefore, if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture may result. The most notable waste tank with a flammable gas problem is tank 241-SY-101. Waste in this tank has occasionally released enough flammable gas to burn if an ignition source had been present inside of the tank. Several other waste tanks exhibit similar behavior to a lesser magnitude. Administrative controls have been developed to assure that these Flammable Gas Watch List tanks are safely maintained. Responses have also been developed for off-normal conditions which might develop in these tanks. In addition, scientific and engineering studies are underway to further understand and mitigate the behavior of the Flammable Gas Watch List tanks.

Sherwood, D.J.

1994-03-01T23:59:59.000Z

169

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

DOE Green Energy (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 5 is the annual update of the methodology and calculations of the flammable gas Waste Groups for DSTs and SSTs.

BARKER, S.A.

2006-07-27T23:59:59.000Z

170

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

DOE Green Energy (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771, Flammable Gas Safety Isme Resolution. Appendices A through I provide supporting information. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste and characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 6 is the annual update of the flammable gas Waste Groups for DSTs and SSTs.

TU, T.A.

2007-01-04T23:59:59.000Z

171

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT HANFORD SITE [SEC 1 & 2  

DOE Green Energy (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generate ammonia. Nonflammable gases, which act as diluents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semivolatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in tank headspace as described in RPP-7771, Flammable Gas Safety Issue Resolution. Appendices A through L provide supporting information. This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste and characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event.

BARKER, S.A.; HEDENGREN, D.C.

2003-08-28T23:59:59.000Z

172

Implementation plan for Title 40 Code of Federal Regulations Parts 280 and 281; Final rules for underground storage tanks  

Science Conference Proceedings (OSTI)

This report presents the schedules and methods required to comply with the newly promulgated Underground Storage Tank (UST) Regulations Title 40 Code of Federal Regulations (CFR) 280 and 281. These rules were promulgated by the US Environmental Protection Agency (EPA) on September 23, 1988, and became effective December 22, 1988. These regulations are required by Subtitle I of the Resource Conservation and Recovery Act of 1976. Their purpose is to protect the groundwater supplies of the United States in the following ways: Closing old tanks; detecting and remediating tank leaks and spills; establishing stringent standards for new tanks; and upgrade of existing tanks to new-tank standards. 3 refs., 5 tabs.

Stupka, R.C.

1989-04-01T23:59:59.000Z

173

Tank Waste Strategy Update  

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

Tank Waste Subcommittee www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 Tank Waste Subcommittee Ken Picha Office of Environmental Management December 5, 2011 Background Tank Waste Subcommittee (TWS)originally chartered, in response to Secretary's request to perform a technical review of Waste Treatment and Immobilization Plant (WTP) in May 2010. Three tasks: o Verification of closure of WTP External Flowsheet Review Team (EFRT) issues. o WTP Technical Design Review o WTP potential improvements Report completed and briefed to DOE in September 2010 www.em.doe.gov safety performance cleanup closure E M Environmental Management 2 Report completed and briefed to DOE in September 2010 Follow-on scope for TWS identified immediately after briefing to DOE and

174

Tank characterization for Double-Shell Tank 241-AP-102  

SciTech Connect

This document provides the characterization information and interprets the data for Double-Shell Tank AP-102.

DeLorenzo, D.S.; DiCenso, A.T.; Amato, L.C.; Weyns-Rollosson, M.I.; Smith, D.J. [Los Alamos Technical Associates, Inc., Kennewick, WA (United States); Simpson, B.C.; Welsh, T.L. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

175

Vapor spill monitoring method  

DOE Patents (OSTI)

Method for continuous sampling of liquified natural gas effluent from a spill pipe, vaporizing the cold liquified natural gas, and feeding the vaporized gas into an infrared detector to measure the gas composition. The apparatus utilizes a probe having an inner channel for receiving samples of liquified natural gas and a surrounding water jacket through which warm water is flowed to flash vaporize the liquified natural gas.

Bianchini, Gregory M. (Livermore, CA); McRae, Thomas G. (Livermore, CA)

1985-01-01T23:59:59.000Z

176

CEMENTITIOUS GROUT FOR CLOSING SRS HIGH LEVEL WASTE TANKS - #12315  

SciTech Connect

In 1997, the first two United States Department of Energy (US DOE) high level waste tanks (Tanks 17-F and 20-F: Type IV, single shell tanks) were taken out of service (permanently closed) at the Savannah River Site (SRS). In 2012, the DOE plans to remove from service two additional Savannah River Site (SRS) Type IV high-level waste tanks, Tanks 18-F and 19-F. These tanks were constructed in the late 1950's and received low-heat waste and do not contain cooling coils. Operational closure of Tanks 18-F and 19-F is intended to be consistent with the applicable requirements of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and will be performed in accordance with South Carolina Department of Health and Environmental Control (SCDHEC). The closure will physically stabilize two 4.92E+04 cubic meter (1.3 E+06 gallon) carbon steel tanks and isolate and stabilize any residual contaminants left in the tanks. The closure will also fill, physically stabilize and isolate ancillary equipment abandoned in the tanks. A Performance Assessment (PA) has been developed to assess the long-term fate and transport of residual contamination in the environment resulting from the operational closure of the F-Area Tank Farm (FTF) waste tanks. Next generation flowable, zero-bleed cementitious grouts were designed, tested, and specified for closing Tanks 18-F and 19-F and for filling the abandoned equipment. Fill requirements were developed for both the tank and equipment grouts. All grout formulations were required to be alkaline with a pH of 12.4 and chemically reduction potential (Eh) of -200 to -400 to stabilize selected potential contaminants of concern. This was achieved by including Portland cement and Grade 100 slag in the mixes, respectively. Ingredients and proportions of cementitious reagents were selected and adjusted, respectively, to support the mass placement strategy developed by closure operations. Subsequent down selection was based on compressive strength and saturated hydraulic conductivity results. Fresh slurry property results were used as the first level of screening. A high range water reducing admixture and a viscosity modifying admixture were used to adjust slurry properties to achieve flowable grouts. Adiabatic calorimeter results were used as the second level screening. The third level of screening was used to design mixes that were consistent with the fill material parameters used in the F-Tank Farm Performance Assessment which was developed to assess the long-term fate and transport of residual contamination in the environment resulting from the operational closures.

Langton, C.; Burns, H.; Stefanko, D.

2012-01-10T23:59:59.000Z

177

Tank Farm Operations Surveillance Automation Analysis  

Science Conference Proceedings (OSTI)

The Nuclear Operations Project Services identified the need to improve manual tank farm surveillance data collection, review, distribution and storage practices often referred to as Operator Rounds. This document provides the analysis in terms of feasibility to improve the manual data collection methods by using handheld computer units, barcode technology, a database for storage and acquisitions, associated software, and operational procedures to increase the efficiency of Operator Rounds associated with surveillance activities.

MARQUEZ, D.L.

2000-12-21T23:59:59.000Z

178

Tanks focus area. Annual report  

SciTech Connect

The U.S. Department of Energy Office of Environmental Management is tasked with a major remediation project to treat and dispose of radioactive waste in hundreds of underground storage tanks. These tanks contain about 90,000,000 gallons of high-level and transuranic wastes. We have 68 known or assumed leaking tanks, that have allowed waste to migrate into the soil surrounding the tank. In some cases, the tank contents have reacted to form flammable gases, introducing additional safety risks. These tanks must be maintained in the safest possible condition until their eventual remediation to reduce the risk of waste migration and exposure to workers, the public, and the environment. Science and technology development for safer, more efficient, and cost-effective waste treatment methods will speed up progress toward the final remediation of these tanks. The DOE Office of Environmental Management established the Tanks Focus Area to serve as the DOE-EM`s technology development program for radioactive waste tank remediation in partnership with the Offices of Waste Management and Environmental Restoration. The Tanks Focus Area is responsible for leading, coordinating, and facilitating science and technology development to support remediation at DOE`s four major tank sites: the Hanford Site in Washington State, Idaho National Engineering and Environmental Laboratory in Idaho, Oak Ridge Reservation in Tennessee, and the Savannah River Site in South Carolina. The technical scope covers the major functions that comprise a complete tank remediation system: waste retrieval, waste pretreatment, waste immobilization, tank closure, and characterization of both the waste and tank. Safety is integrated across all the functions and is a key component of the Tanks Focus Area program.

Frey, J.

1997-12-31T23:59:59.000Z

179

Release of LNG vapor from large-volume, low-pressure LNG storage. Letter report, September 30, 1981-September 30, 1982  

Science Conference Proceedings (OSTI)

This project involves development of practical release prevention measures by developing design and operating procedures beyond current practice. The objective of the program is to obtain the quantitative field data necessary to model the physics of the tank vapor space pressure response to boil-off compressor operation and atmospheric pressure changes. This work will lead to the development of guides to LNG storage tank operation and equipment specification that will limit the possibility of vapor venting or rollover of the stored LNG.

Not Available

1982-01-01T23:59:59.000Z

180

Tank characterization data report: Tank 241-C-112  

Science Conference Proceedings (OSTI)

Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. It is probable that tank 241-C-112 exceeds the 1,000 g-mol inventory criteria established for the Ferrocyanide USQ; however, extensive energetic analysis of the waste has determined a maximum exothermic value of -9 cal/g dry waste. This value is substantially below any levels of concern (-75 cal/g). In addition, an investigation of potential mechanisms to generate concentration levels of radionuclides high enough to be of concern was performed. No credible mechanism was postulated that could initiate the formation of such concentration levels in the tank. Tank 241-C-112 waste is a complex material made up primarily of water and inert salts. The insoluble solids are a mixture of phosphates, sulfates, and hydroxides in combination with aluminum, calcium, iron, nickel, and uranium. Disodium nickel ferrocyanide and sodium cesium nickel ferrocyanide probably exist in the tank; however, there appears to have been significant degradation of this material since the waste was initially settled in the tank.

Simpson, B.C.; Borsheim, G.L.; Jensen, L.

1993-04-01T23:59:59.000Z

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


181

Partial Acceptance for Beneficial Use (ABU) for the Type 4 In Situ Vapor Sampler (ISVS) Carts  

Science Conference Proceedings (OSTI)

This document provides the Acceptance for Beneficial Use (ABU) for the Type 4 in-situ vapor sampler (ISVS) system. This document is generated to support the completion of equipment modifications and engineering documentation for the ISVS system that is used for sampling gaseous vapors in the Hanford single shell radioactive waste storage tanks. This ABU documents items for transferring the ISVS system to operations for field use. This document is generated following Characterization Engineering Desk Instruction DI-CE-004-001.

BOGER, R.M.

2000-05-19T23:59:59.000Z

182

Carderock Rotating Arm Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Rotating Arm Tow Tank Rotating Arm Tow Tank Jump to: navigation, search Basic Specifications Facility Name Carderock Rotating Arm Tow Tank Overseeing Organization United States Naval Surface Warfare Center Hydrodynamic Testing Facility Type Tow Tank Beam(m) 79.2 Depth(m) 6.1 Water Type Freshwater Cost(per day) Contact POC Special Physical Features Rotating Arm facility is a circular indoor basin 79.2m in diameter. The arm is a bridge-like structure with a span of 39.3m and pivots on a pedestal in the center of the basin. Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 25.8 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Cameras None

183

Correlation models for waste tank sludges and slurries  

SciTech Connect

This report presents the results of work conducted to support the TEMPEST computer modeling under the Flammable Gas Program (FGP) and to further the comprehension of the physical processes occurring in the Hanford waste tanks. The end products of this task are correlation models (sets of algorithms) that can be added to the TEMPEST computer code to improve the reliability of its simulation of the physical processes that occur in Hanford tanks. The correlation models can be used to augment, not only the TEMPEST code, but other computer codes that can simulate sludge motion and flammable gas retention. This report presents the correlation models, also termed submodels, that have been developed to date. The submodel-development process is an ongoing effort designed to increase our understanding of sludge behavior and improve our ability to realistically simulate the sludge fluid characteristics that have an impact on safety analysis. The effort has employed both literature searches and data correlation to provide an encyclopedia of tank waste properties in forms that are relatively easy to use in modeling waste behavior. These properties submodels will be used in other tasks to simulate waste behavior in the tanks. Density, viscosity, yield strength, surface tension, heat capacity, thermal conductivity, salt solubility, and ammonia and water vapor pressures were compiled for solutions and suspensions of sodium nitrate and other salts (where data were available), and the data were correlated by linear regression. In addition, data for simulated Hanford waste tank supernatant were correlated to provide density, solubility, surface tension, and vapor pressure submodels for multi-component solutions containing sodium hydroxide, sodium nitrate, sodium nitrite, and sodium aluminate.

Mahoney, L.A.; Trent, D.S.

1995-07-01T23:59:59.000Z

184

Carderock Tow Tank 1 | Open Energy Information  

Open Energy Info (EERE)

1 1 Overseeing Organization United States Naval Surface Warfare Center Hydrodynamic Testing Facility Type Tow Tank Length(m) 271.0 Beam(m) 15.5 Depth(m) 6.7 Water Type Freshwater Cost(per day) Contact POC Special Physical Features Carriage 1 is located on this basin Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 9.3 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Cameras None Data Generation Capability Real-Time No Test Services Test Services None Special Characteristics Special Characteristics None Hydro | Hydrodynamic Testing Facilities Retrieved from "http://en.openei.org/w/index.php?title=Carderock_Tow_Tank_1&oldid=602146

185

Think Tank: Delaware Department of Natural Resources  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Spring 2009 Number 58 Spring 2009 Number 58 UST Regulations Revision Update Jill Hall The Tank Management Branch (TMB) conducted 3 public workshops in October 2008 to roll out changes to the Delaware Regulations Governing Underground Storage Tanks (UST Regulations). The UST Regulations were completely re- vamped last year and became effective January 11, 2008. Changes were made last year for 2 reasons: (1) the UST Reg- ulations were woefully out of date with regards to technological changes, and (2) the Federal Energy Policy Act (EPACT) dictated that states make several chang- es to their UST programs. The changes required by EPACT have deadlines rang- ing from 2008 to August 2009. Delaware could not make all the required changes by January 11, 2008 because the United States Environmental Protection Agency

186

Steady State Flammable Gas Release Rate Calculation and Lower Flammability Level Evaluation for Hanford Tank Waste  

DOE Green Energy (OSTI)

Assess the steady-state flammability level at normal and off-normal ventilation conditions. Hydrogen generation rate was calculated for 177 tanks using rate equation model. Ammonia liquid/vapor equilibrium model is incorporated into the methodology for ammonia analysis.

HU, T.A.

2001-02-23T23:59:59.000Z

187

NOTICE OF AVAILABILITY - INTERIM RECORD OF DECISION FOR THE F-AREA TANK FARM, WASTE TANKS 17 AND 20  

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

5 5 April 30, 2013 NOTICE OF AVAILABILITY - INTERIM RECORD OF DECISION FOR THE F-AREA TANK FARM, WASTE TANKS 17 AND 20 The Interim Record of Decision (IROD) Remedial Alternative Selection for the F-Area Tank Farm (FTF), Waste Tanks 17 and 20, is being issued by the U.S. Department of Energy (DOE), the lead agency for the Savannah River Site (SRS), with concur- rence by the U.S. Environmental Protection Agency - Region 4 (EPA), and South Carolina Department of Health and Environ- mental Control (SCDHEC). The IROD was completed to facilitate the terms of the Federal Facility Agreement (FFA) for SRS governing the investigation and cleanup of waste units. The FFA integrates the requirements of Resource Conservation and Re- covery Act and the Comprehensive Environmental Response, Compensation, and Liability Act.

188

Savannah River Site Contractor Achieves Tank Waste Milestone | Department  

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

Contractor Achieves Tank Waste Milestone Contractor Achieves Tank Waste Milestone Savannah River Site Contractor Achieves Tank Waste Milestone February 2, 2012 - 12:00pm Addthis Pictured here is a component of the Interim Salt Disposition Process — known as Modular Caustic Side Solvent Extraction Unit (MCU) — that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. Pictured here is a component of the Interim Salt Disposition Process - known as Modular Caustic Side Solvent Extraction Unit (MCU) - that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. AIKEN, S.C. - The Savannah River Site's liquid waste contractor recently achieved a contract milestone by processing 500,000 gallons of

189

Engineering Task Plan for Preparing the Type 4 In Situ Vapor Samplers (ISVS) for Use  

SciTech Connect

The DOE has identified a need to sample vapor space and exhaust ducts of several waste tanks The In-Situ Vapor Sampling (ISVS) Type IV vapor sampling cart has been identified as the appropriate monitoring tool. The ISVS carts have been out of service for a number of years. This ETP outlines the work to be performed to ready the type IV gas sampler for operation Characterization Engineering will evaluate the Type IV gas sampler carts to determine their state of readiness and will proceed to update procedures and equipment documentation to make the sampler operationally acceptable.

BOGER, R.M.

2000-01-06T23:59:59.000Z

190

Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Appendix A  

Science Conference Proceedings (OSTI)

This document is a compilation of data relating to the Tank Waste Remediation System Multi-Year Program. Topics discussed include: management systems; waste volume, transfer and evaporation management; transition of 200 East and West areas; ferricyanide, volatile organic vapor, and flammable gas management; waste characterization; retrieval from SSTs and DSTs; heat management; interim storage; low-level and high-level radioactive waste management; and tank farm closure.

NONE

1995-09-01T23:59:59.000Z

191

A STRUCTURAL IMPACT ASSESSMENT OF FLAWS DETECTED DURING ULTRASONIC EXAMINATION OF TANK 15  

SciTech Connect

Ultrasonic (UT) inspection of Tank 15 was conducted between April and July 2007 in accordance with the Tank 15 UT inspection plan. This was a planned re-inspection of this tank, the previous one was performed in 2002. Ten cracks were characterized in the previous examination. The re-inspection was performed to verify the present models and understanding for stress corrosion cracking. During this re-examination, one indication that was initially reported as a 'possible perpendicular crack <25% through wall' in 2002, was clearly shown not to be a crack. Additionally, examination of a new area immediately adjacent to other cracks along a vertical weld revealed three new cracks. It is not known when these new cracks formed as they could very well have been present in 2002 as well. Therefore, a total of twelve cracks were evaluated during the re-examination. A critical review of the information describing stress corrosion crack behavior for the SRS waste tanks, as well as a summary review of the service history of Tank 15, was performed. Each crack was then evaluated for service exposure history, consistency of the crack behavior with the current understanding of stress corrosion cracking, and present and future impact to the structural integrity of the tank. Crack instability calculations were performed on each crack for a bounding waste removal loading condition in Tank 15. In all cases, the crack behavior was determined to be consistent with the previous understanding of stress corrosion cracking in the SRS waste tank environment. The length of the cracks was limited due to the short-range nature of the residual stresses near seam, repair and attachment welds. Of the twelve cracks, nine were located in the vapor space above the sludge layer, including the three new cracks. Comparison of the crack lengths measured in 2002 and 2007 revealed that crack growth had occurred in four of the six previously measured vapor space cracks. However, the growth remained within the residual stress zone. None of the three cracks beneath the sludge showed evidence of growth. The impact of the cracks that grew on the future service of Tank 15 was also assessed. Tank 15 is expected to undergo closure activities including sludge waste removal. A bounding loading condition for waste removal of the sludge at the bottom of Tank 15 was considered for this analysis. The analysis showed that the combination of hydrostatic, seismic, pump and weld residual stresses are not expected to drive any of the cracks identified during the Tank 15 UT inspection to instability. Wall thickness mapping for general thinning and pitting was also performed. No significant wall thinning was observed. The average wall thickness values were well above nominal. Two isolated pit-like indications were observed. Both were approximately 30 mils deep. However, the remaining wall thickness was still greater than nominal specified for the original construction plate material. It was recommended that a third examination of selected cracks in Tank 15 be performed in 2014. This examination would provide information to determine whether any additional detectable degradation is occurring in Tank 15 and to supplement the basis for characterization of conditions that are non-aggressive to tank corrosion damage. The in-service inspection program is re-evaluated on a three year periodicity. The Type I and II tanks are not active receipt tanks at present, and are therefore not a part of the In-Service Inspection Program for the Type III Tanks [1]. Changes to the mission for Tank 15 and other Type I and II tanks may be considered by the In-Service Inspection Review Committee (ISIRC) and the program adjusted accordingly.

Wiersma, B; James Elder, J

2008-08-21T23:59:59.000Z

192

Estimating Waste Inventory and Waste Tank Characterization |...  

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

Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue...

193

Revitalized Board Lays Out New Path amid EM's Recent Underground Tank  

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

Revitalized Board Lays Out New Path amid EM's Recent Underground Revitalized Board Lays Out New Path amid EM's Recent Underground Tank Waste Successes Revitalized Board Lays Out New Path amid EM's Recent Underground Tank Waste Successes August 20, 2012 - 12:00pm Addthis Cement trucks transport a specially formulated grout that is pumped into two underground waste tanks at the Savannah River Site as part of work to close the massive structures. Cement trucks transport a specially formulated grout that is pumped into two underground waste tanks at the Savannah River Site as part of work to close the massive structures. A view of the interior of the Integrated Waste Treatment Unit at the Idaho site. A view of the interior of the Integrated Waste Treatment Unit at the Idaho site. Cement trucks transport a specially formulated grout that is pumped into two underground waste tanks at the Savannah River Site as part of work to close the massive structures.

194

Electrolyte vapor condenser  

DOE Patents (OSTI)

A system is disclosed for removing electrolyte from a fuel cell gas stream. The gas stream containing electrolyte vapor is supercooled utilizing conventional heat exchangers and the thus supercooled gas stream is passed over high surface area passive condensers. The condensed electrolyte is then drained from the condenser and the remainder of the gas stream passed on. The system is particularly useful for electrolytes such as phosphoric acid and molten carbonate, but can be used for other electrolyte cells and simple vapor separation as well. 3 figs.

Sederquist, R.A.; Szydlowski, D.F.; Sawyer, R.D.

1983-02-08T23:59:59.000Z

195

Electrolyte vapor condenser  

DOE Patents (OSTI)

A system is disclosed for removing electrolyte from a fuel cell gas stream. The gas stream containing electrolyte vapor is supercooled utilizing conventional heat exchangers and the thus supercooled gas stream is passed over high surface area passive condensers. The condensed electrolyte is then drained from the condenser and the remainder of the gas stream passed on. The system is particularly useful for electrolytes such as phosphoric acid and molten carbonate, but can be used for other electrolyte cells and simple vapor separation as well.

Sederquist, Richard A. (Newington, CT); Szydlowski, Donald F. (East Hartford, CT); Sawyer, Richard D. (Canton, CT)

1983-01-01T23:59:59.000Z

196

Vapor concentration monitor  

DOE Patents (OSTI)

An apparatus for monitoring the concentration of a vapor, such as heavy water, having at least one narrow bandwidth in its absorption spectrum, in a sample gas such as air. The air is drawn into a chamber in which the vapor content is measured by means of its radiation absorption spectrum. High sensitivity is obtained by modulating the wavelength at a relatively high frequency without changing its optical path, while high stability against zero drift is obtained by the low frequency interchange of the sample gas to be monitored and of a reference sample. The variable HDO background due to natural humidity is automatically corrected.

Bayly, John G. (Deep River, CA); Booth, Ronald J. (Deep River, CA)

1977-01-01T23:59:59.000Z

197

Definition: Mercury Vapor | Open Energy Information  

Open Energy Info (EERE)

Mercury Vapor Jump to: navigation, search Dictionary.png Mercury Vapor Mercury is discharged as a highly volatile vapor during hydrothermal activity and high concentrations in...

198

Tank Waste Corporate Board | Department of Energy  

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

Tank Waste Corporate Board Tank Waste Corporate Board Tank Waste Corporate Board The Tank Waste Corporate Board is a chartered group of senior DOE, contractor, and laboratory managers and staff that meets approximately semi-annually to formulate and coordinate implementation of an effective and efficient national Tank Waste program. August 1, 2012 Tank Waste Corporate Board Meeting 08/01/12 The following documents are associated with the Tank Waste Corporate Board Meeting held on August 1st, 2012. November 18, 2010 Tank Waste Corporate Board Meeting 11/18/10 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010. July 29, 2009 Tank Waste Corporate Board Meeting 07/29/09 The following documents are associated with the Tank Waste Corporate Board

199

FEMA Think Tank Call Meeting  

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

FEMA Think Tank Call Meeting FEMA Think Tank Call Meeting Minimize Date: Wednesday, September 25, 2013 Time: 1:00 - 2:30 p.m. (Eastern Time) Location: Y-12 New Hope Center, 602 Scarboro Rd, Oak Ridge, TN 37830 Overview Description: The FEMA Think Tank is a mechanism to formally collect, discuss, evaluate, and develop innovative ideas in the emergency management community - state, local, and tribal governments, as well as members of the public, including the private sector, the disability community, and volunteer groups. It ensures whole community partners and federal employees are motivated and encouraged to innovate, actively solicit and discuss ideas, and oversee the implementation of promising ideas. The FEMA Think Tank is designed to act as a forum where good ideas are shared, discussed, and become innovative solutions. There are currently two components to the think tank. The first, an online component, can be accessed at any time at, http://fema.ideascale.com. The second component is a conference call that includes both a nationwide telephone audience and an audience at the FEMA Think Tank Call site. This second component is described in more detail at the following website: http://www.fema.gov/fema-think-tank.

200

Organic vapor jet printing system  

DOE Patents (OSTI)

An organic vapor jet printing system includes a pump for increasing the pressure of an organic flux.

Forrest, Stephen R

2012-10-23T23:59:59.000Z

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


201

Tank 241-C-103 tank characterization plan. Revision 2  

Science Conference Proceedings (OSTI)

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-C-103.

Homi, C.S.

1995-10-04T23:59:59.000Z

202

Tank 241-AN-102 tank characterization plan. Revision 1  

Science Conference Proceedings (OSTI)

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-AN-102

Homi, C.S.

1995-10-04T23:59:59.000Z

203

Tank characterization report for single-shell Tank B-201  

Science Conference Proceedings (OSTI)

The purpose of this report is to characterize the waste in single shell Tank B-201. Characterization includes the determination of the physical, chemical (e.g., concentrations of elements and organic species), and radiological properties of the waste. These determinations are made using analytical results from B-201 core samples as well as historical information about the tank. The main objective is to determine average waste properties: but in some cases, concentrations of analytes as a function of depth were also determined. This report also consolidates the available historical information regarding Tank B-201, arranges the analytical information from the recent core sampling in a useful format, and provides an interpretation of the data within the context of what is known about the tank.

Heasler, P.G.; Remund, K.M.; Tingey, J.M.; Baird, D.B.; Ryan, F.M.

1994-09-01T23:59:59.000Z

204

United States Government Departmen  

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

7/05 TUE 07:58 FAX 423 241 3897 OIG -** HQ @]002 7/05 TUE 07:58 FAX 423 241 3897 OIG -** HQ @]002 DOE F 1325.8 (08-93) United States Government Departmen of Energy memorandum DATE: December 20, 2005 Audit Report Number: OAS-L-06-03 REPLY TO A1TN OF; IG-36 (A05SR025) SUBJECT: Audit of "Defense Waste Processing Facility Operations at the Savannah River Site" TO: Jeffrey M. Allison, Manager, Savannah River Operations Office INTRODUCTION AND OBJECTIVE The Department of Energy's (Department) Savannah River Site stores approximately 36 million gallons of liquid, high-level radioactive waste in 49 underground waste storage tanks. The contents of the waste tanks are broadly characterized as either "sludge waste" or "salt waste". Sludge waste is insoluble and settles to the bottom of a waste tank, beneath a layer of liquid supernate. Salt

205

Hanford Determines Double-Shell Tank Leaked Waste From Inner Tank |  

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

Determines Double-Shell Tank Leaked Waste From Inner Tank Determines Double-Shell Tank Leaked Waste From Inner Tank Hanford Determines Double-Shell Tank Leaked Waste From Inner Tank October 22, 2012 - 12:00pm Addthis Media Contacts Lori Gamache, ORP 509-372-9130 John Britton, WRPS 509-376-5561 RICHLAND - The Department of Energy's Office of River Protection (ORP), working with its Hanford tank operations contractor Washington River Protection Solutions, has determined that there is a slow leak of chemical and radioactive waste into the annulus space in Tank AY-102, the approximately 30-inch area between the inner primary tank and the outer tank that serves as the secondary containment for these types of tanks. This is the first time a double-shell tank (DST) leak from the primary tank into the annulus has been identified. There is no indication of waste in

206

Scholars from northeast Brazil, Costa Rica, southeast Mexico, Nicaragua, Italy, and the United States gathered for a think-tank international week April 18-22, 2011 to examine Latin America's equity-gap challenges using a community engagement  

E-Print Network (OSTI)

Scholars from northeast Brazil, Costa Rica, southeast Mexico, Nicaragua, Italy, and the United. The keynote address--Brazil's Unified Health System May Promote Social Inequality: Paradox or dialectic/northeastern Brazil constitute nadirs of economic and health inequality. The stunting rates among children

Liu, Taosheng

207

High-Pressure Hydrogen Tanks  

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

February 8 February 8 th , 2005 Mark J. Warner, P.E. Principal Engineer Quantum Technologies, Inc. Irvine, CA Low Cost, High Efficiency, Low Cost, High Efficiency, High Pressure Hydrogen Storage High Pressure Hydrogen Storage This presentation does not contain any proprietary or confidential information. 70 MPa Composite Tanks Vent Line Ports Defueling Port (optional) Fill Port Filter Check Valve Vehicle Interface Bracket with Stone Shield In Tank Regulator with Solenoid Lock-off Pressure Relief Device Manual Valve Compressed Hydrogen Storage System In-Tank Regulator Pressure Sensor (not visible here) Pressure Relief Device (thermal) In Tank Gas Temperature Sensor Carbon Composite Shell (structural) Impact Resistant Outer Shell (damage resistant) Gas Outlet Solenoid Foam Dome (impact protection)

208

Improvement in LNG storage tanks  

SciTech Connect

To develop and produce natural gas fuel tanks for medium duty truck and transit bus end-use to overcome the weight and range problems inherent in current fuel systems.

NONE

1999-11-20T23:59:59.000Z

209

Hydrogen Storage "Think Tank" Report  

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

brainstorming on this critical issue. This "Think Tank" meeting was held in Washington, D.C. on March 14, 2003 and was organized and sponsored by the U.S. Department of...

210

Mercury Vapor | Open Energy Information  

Open Energy Info (EERE)

Mercury Vapor Mercury Vapor Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Mercury Vapor Details Activities (23) Areas (23) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Fluid Lab Analysis Parent Exploration Technique: Fluid Lab Analysis Information Provided by Technique Lithology: Stratigraphic/Structural: Anomalously high concentrations can indicate high permeability or conduit for fluid flow Hydrological: Field wide soil sampling can generate a geometrical approximation of fluid circulation Thermal: High concentration in soils can be indicative of active hydrothermal activity Dictionary.png Mercury Vapor: Mercury is discharged as a highly volatile vapor during hydrothermal

211

Fuel vapor canister  

SciTech Connect

This paper discusses an improved fuel vapor storage canister for use in a vehicle emission system of the type utilizing an enclosure with an interior communicated with a source of fuel vapor. The improved canister comprises: the enclosure having a mixture including particles of activated charcoal and many pieces of foam rubber, the pieces of foam rubber in the mixture being randomly and substantially evenly dispersed whereby substantially all the charcoal particles are spaced relatively closely to at least one foam rubber piece; the mixture being packed into the enclosure under pressure so that the pieces of foam rubber are compressed enough to tightly secure the charcoal particles one against another to prevent a griding action therebetween.

Moskaitis, R.J.; Ciuffetelli, L.A.

1991-03-26T23:59:59.000Z

212

Stratified vapor generator  

DOE Patents (OSTI)

A stratified vapor generator (110) comprises a first heating section (H.sub.1) and a second heating section (H.sub.2). The first and second heating sections (H.sub.1, H.sub.2) are arranged so that the inlet of the second heating section (H.sub.2) is operatively associated with the outlet of the first heating section (H.sub.1). A moisture separator (126) having a vapor outlet (164) and a liquid outlet (144) is operatively associated with the outlet (124) of the second heating section (H.sub.2). A cooling section (C.sub.1) is operatively associated with the liquid outlet (144) of the moisture separator (126) and includes an outlet that is operatively associated with the inlet of the second heating section (H.sub.2).

Bharathan, Desikan (Lakewood, CO); Hassani, Vahab (Golden, CO)

2008-05-20T23:59:59.000Z

213

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 1 [of 2  

SciTech Connect

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. A phased and integrated approach to waste retrieval operations was used for the GAAT Remediation Project. The project promoted safety by obtaining experience from low-risk operations in the North Tank Farm before moving to higher-risk operations in the South Tank Farm. This approach allowed project personnel to become familiar with the tanks and waste, as well as the equipment, processes, procedures, and operations required to perform successful waste retrieval. By using an integrated approach to tank waste retrieval and tank waste management, the project was completed years ahead of the original baseline schedule, which resulted in avoiding millions of dollars in associated costs. This report is organized in two volumes. Volume 1 provides information on the various phases of the GAAT Remediation Project. It also describes the different types of equipment and how they were used. The emphasis of Volume 1 is on the description of the tank waste retrieval performance and the lessons learned during the GAAT Remediation Project. Volume 2 provides the appendixes for the report, which include the following information: (A) Background Information for the Gunite and Associated Tanks Operable Unit; (B) Annotated Bibliography; (C) Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; (D) GAAT Equipment Matrix; and (E) Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435,000 below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

Lewis, BE

2003-10-07T23:59:59.000Z

214

VAPOR PRESSURES AND HEATS OF VAPORIZATION OF PRIMARY COAL TARS  

DOE Green Energy (OSTI)

This project had as its main focus the determination of vapor pressures of coal pyrolysis tars. It involved performing measurements of these vapor pressures and from them, developing vapor pressure correlations suitable for use in advanced pyrolysis models (those models which explicitly account for mass transport limitations). This report is divided into five main chapters. Each chapter is a relatively stand-alone section. Chapter A reviews the general nature of coal tars and gives a summary of existing vapor pressure correlations for coal tars and model compounds. Chapter B summarizes the main experimental approaches for coal tar preparation and characterization which have been used throughout the project. Chapter C is concerned with the selection of the model compounds for coal pyrolysis tars and reviews the data available to us on the vapor pressures of high boiling point aromatic compounds. This chapter also deals with the question of identifying factors that govern the vapor pressures of coal tar model materials and their mixtures. Chapter D covers the vapor pressures and heats of vaporization of primary cellulose tars. Chapter E discusses the results of the main focus of this study. In summary, this work provides improved understanding of the volatility of coal and cellulose pyrolysis tars. It has resulted in new experimentally verified vapor pressure correlations for use in pyrolysis models. Further research on this topic should aim at developing general vapor pressure correlations for all coal tars, based on their molecular weight together with certain specific chemical characteristics i.e. hydroxyl group content.

Eric M. Suuberg; Vahur Oja

1997-07-01T23:59:59.000Z

215

Ethanol production by vapor compression distillation  

DOE Green Energy (OSTI)

The goal of this project is to develop and demonstrate a one gallon per hour vapor compression distillation unit for fuel ethanol production that can be profitably manufactured and economically operated by individual family units. Vapor compression distillation is already an industrially accepted process and this project's goal is to demonstrate that it can be done economically on a small scale. Theoretically, the process is independent of absolute pressure. It is only necessary that the condenser be at higher pressure than the evaporator. By reducing the entire process to a pressure of approximately 0.1 atmosphere, the evaporation and condensation can occur at near ambient temperature. Even though this approach requires a vacuum pump, and thus will not represent the final cost effective design, it does not require preheaters, high temperature materials, or as much insulation as if it were to operate a near ambient pressure. Therefore, the operation of the ambient temperature unit constitutes the first phase of this project. Presently, the ambient temperature unit is fully assembled and has begun testing. So far it has successfully separated ethanol from a nine to one diluted input solution. However the production rate has been very low.

Ellis, G.S.

1981-01-01T23:59:59.000Z

216

Progress in resolving Hanford Site high-level waste tank safety issues  

DOE Green Energy (OSTI)

Interim storage of alkaline, high-level radioactive waste, from two generations of spent fuel reprocessing and waste management activities, has resulted in the accumulation of 238 million liters of waste in Hanford Site single and double-shell tanks. Before the 1990`s, the stored waste was believed to be: (1) chemically unreactive under its existing storage conditions and plausible accident scenarios; and (2) chemically stable. This paradigm was proven incorrect when detailed evaluation of tank contents and behavior revealed a number of safety issues and that the waste was generating flammable and noxious gases. In 1990, the Waste Tank Safety Program was formed to focus on identifying safety issues and resolving the ferrocyanide, flammable gas, organic, high heat, noxious vapor, and criticality issues. The tanks of concern were placed on Watch Lists by safety issue. This paper summarizes recent progress toward resolving Hanford Site high-level radioactive waste tank safety issues, including modeling, and analyses, laboratory experiments, monitoring upgrades, mitigation equipment, and developing a strategy to screen tanks for safety issues.

Babad, H.; Eberlein, S.J.; Johnson, G.D.; Meacham, J.E.; Osborne, J.W.; Payne, M.A.; Turner, D.A.

1995-02-01T23:59:59.000Z

217

Hanford Site C Tank Farm Meeting Summary - May 2011 | Department...  

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

May 2011 Hanford Site C Tank Farm Meeting Summary - May 2011 Hanford Site C Tank Farm Meeting Summary More Documents & Publications Hanford Site C Tank Farm Meeting Summary -...

218

Hanford Site C Tank Farm Meeting Summary - September 2010 | Department...  

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

September 2010 Hanford Site C Tank Farm Meeting Summary - September 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

219

Hanford Site C Tank Farm Meeting Summary - September 2009 | Department...  

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

September 2009 Hanford Site C Tank Farm Meeting Summary - September 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

220

Hanford Site C Tank Farm Meeting Summary - February 2009 | Department...  

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

February 2009 Hanford Site C Tank Farm Meeting Summary - February 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

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


221

Hanford Waste Tank Plant PIA, Richland Operations Office | Department...  

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

Hanford Waste Tank Plant PIA, Richland Operations Office Hanford Waste Tank Plant PIA, Richland Operations Office Hanford Waste Tank Plant PIA, Richland Operations Office Hanford...

222

Auxiliary resonant DC tank converter  

SciTech Connect

An auxiliary resonant dc tank (ARDCT) converter is provided for achieving soft-switching in a power converter. An ARDCT circuit is coupled directly across a dc bus to the inverter to generate a resonant dc bus voltage, including upper and lower resonant capacitors connected in series as a resonant leg, first and second dc tank capacitors connected in series as a tank leg, and an auxiliary resonant circuit comprising a series combination of a resonant inductor and a pair of auxiliary switching devices. The ARDCT circuit further includes first clamping means for holding the resonant dc bus voltage to the dc tank voltage of the tank leg, and second clamping means for clamping the resonant dc bus voltage to zero during a resonant period. The ARDCT circuit resonantly brings the dc bus voltage to zero in order to provide a zero-voltage switching opportunity for the inverter, then quickly rebounds the dc bus voltage back to the dc tank voltage after the inverter changes state. The auxiliary switching devices are turned on and off under zero-current conditions. The ARDCT circuit only absorbs ripples of the inverter dc bus current, thus having less current stress. In addition, since the ARDCT circuit is coupled in parallel with the dc power supply and the inverter for merely assisting soft-switching of the inverter without participating in real dc power transmission and power conversion, malfunction and failure of the tank circuit will not affect the functional operation of the inverter; thus a highly reliable converter system is expected.

Peng, Fang Z. (Knoxville, TN)

2000-01-01T23:59:59.000Z

223

241-AY-101 Tank Construction Extent of Condition Review for Tank Integrity  

Science Conference Proceedings (OSTI)

This report provides the results of an extent of condition construction history review for tank 241-AY-101. The construction history of tank 241-AY-101 has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In tank 241-AY-101, the second double-shell tank constructed, similar issues as those with tank 241-AY-102 construction reoccurred. The overall extent of similary and affect on tank 241-AY-101 integrity is described herein.

Barnes, Travis J.; Gunter, Jason R.

2013-08-26T23:59:59.000Z

224

241-AW Tank Farm Construction Extent of Condition Review for Tank Integrity  

Science Conference Proceedings (OSTI)

This report provides the results of an extent of condition construction history review for the 241-AW tank farm. The construction history of the 241-AW tank farm has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In the 241-AW tank farm, the fourth double-shell tank farm constructed, similar issues as those with tank 241-AY-102 construction occured. The overall extent of similary and affect on 241-AW tank farm integrity is described herein.

Barnes, Travis J.; Gunter, Jason R.; Reeploeg, Gretchen E.

2013-11-19T23:59:59.000Z

225

Life Estimation of High Level Waste Tank Steel for H-Tank Farm ...  

the tanks is not considered in the analysis. Life Estimation of High Level Waste Tank ... conservative scenario in which the concrete vault has completely

226

Methodology for Predicting Flammable Gas Mixtures in Double Contained Receiver Tanks [SEC 1 THRU SEC 3  

DOE Green Energy (OSTI)

This methodology document provides an estimate of the maximum concentrations of flammable gases (ammonia, hydrogen, and methane) which could exist in the vapor space of a double-contained receiver tank (DCRT) from the simultaneous saltwell pumping of one or more single-shell tanks (SSTs). This document expands Calculation Note 118 (Hedengren et a1 1997) and removes some of the conservatism from it, especially in vapor phase ammonia predictions. The methodologies of Calculation Note 118 (Hedengren et a1 1997) are essentially identical for predicting flammable gas mixtures in DCRTs from saltwell pumping for low DCRT ventilation rates, 1e, < 1 cfm. The hydrogen generation model has also been updated in the methodology of this document.

HEDENGREN, D.C.

2000-01-31T23:59:59.000Z

227

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

Science Conference Proceedings (OSTI)

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

NGUYEN, D.M.

2000-02-01T23:59:59.000Z

228

TANK48 CFD MODELING ANALYSIS  

SciTech Connect

The process of recovering the waste in storage tanks at the Savannah River Site (SRS) typically requires mixing the contents of the tank to ensure uniformity of the discharge stream. Mixing is accomplished with one to four dual-nozzle slurry pumps located within the tank liquid. For the work, a Tank 48 simulation model with a maximum of four slurry pumps in operation has been developed to estimate flow patterns for efficient solid mixing. The modeling calculations were performed by using two modeling approaches. One approach is a single-phase Computational Fluid Dynamics (CFD) model to evaluate the flow patterns and qualitative mixing behaviors for a range of different modeling conditions since the model was previously benchmarked against the test results. The other is a two-phase CFD model to estimate solid concentrations in a quantitative way by solving the Eulerian governing equations for the continuous fluid and discrete solid phases over the entire fluid domain of Tank 48. The two-phase results should be considered as the preliminary scoping calculations since the model was not validated against the test results yet. A series of sensitivity calculations for different numbers of pumps and operating conditions has been performed to provide operational guidance for solids suspension and mixing in the tank. In the analysis, the pump was assumed to be stationary. Major solid obstructions including the pump housing, the pump columns, and the 82 inch central support column were included. The steady state and three-dimensional analyses with a two-equation turbulence model were performed with FLUENT{trademark} for the single-phase approach and CFX for the two-phase approach. Recommended operational guidance was developed assuming that local fluid velocity can be used as a measure of sludge suspension and spatial mixing under single-phase tank model. For quantitative analysis, a two-phase fluid-solid model was developed for the same modeling conditions as the single-phase model. The modeling results show that the flow patterns driven by four pump operation satisfy the solid suspension requirement, and the average solid concentration at the plane of the transfer pump inlet is about 12% higher than the tank average concentrations for the 70 inch tank level and about the same as the tank average value for the 29 inch liquid level. When one of the four pumps is not operated, the flow patterns are satisfied with the minimum suspension velocity criterion. However, the solid concentration near the tank bottom is increased by about 30%, although the average solid concentrations near the transfer pump inlet have about the same value as the four-pump baseline results. The flow pattern results show that although the two-pump case satisfies the minimum velocity requirement to suspend the sludge particles, it provides the marginal mixing results for the heavier or larger insoluble materials such as MST and KTPB particles. The results demonstrated that when more than one jet are aiming at the same position of the mixing tank domain, inefficient flow patterns are provided due to the highly localized momentum dissipation, resulting in inactive suspension zone. Thus, after completion of the indexed solids suspension, pump rotations are recommended to avoid producing the nonuniform flow patterns. It is noted that when tank liquid level is reduced from the highest level of 70 inches to the minimum level of 29 inches for a given number of operating pumps, the solid mixing efficiency becomes better since the ratio of the pump power to the mixing volume becomes larger. These results are consistent with the literature results.

Lee, S.

2011-05-17T23:59:59.000Z

229

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

Science Conference Proceedings (OSTI)

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

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

1996-09-01T23:59:59.000Z

230

Tank Waste Disposal Program redefinition  

SciTech Connect

The record of decision (ROD) (DOE 1988) on the Final Environmental Impact Statement, Hanford Defense High-Level, Transuranic and Tank Wastes, Hanford Site, Richland Washington identifies the method for disposal of double-shell tank waste and cesium and strontium capsules at the Hanford Site. The ROD also identifies the need for additional evaluations before a final decision is made on the disposal of single-shell tank waste. This document presents the results of systematic evaluation of the present technical circumstances, alternatives, and regulatory requirements in light of the values of the leaders and constitutents of the program. It recommends a three-phased approach for disposing of tank wastes. This approach allows mature technologies to be applied to the treatment of well-understood waste forms in the near term, while providing time for the development and deployment of successively more advanced pretreatment technologies. The advanced technologies will accelerate disposal by reducing the volume of waste to be vitrified. This document also recommends integration of the double-and single-shell tank waste disposal programs, provides a target schedule for implementation of the selected approach, and describes the essential elements of a program to be baselined in 1992.

Grygiel, M.L.; Augustine, C.A.; Cahill, M.A.; Garfield, J.S.; Johnson, M.E.; Kupfer, M.J.; Meyer, G.A.; Roecker, J.H. [Westinghouse Hanford Co., Richland, WA (United States); Holton, L.K.; Hunter, V.L.; Triplett, M.B. [Pacific Northwest Lab., Richland, WA (United States)

1991-10-01T23:59:59.000Z

231

Insulating LNG (liquified natural gas) storage tank containment dikes with a lightweight polymer concrete  

SciTech Connect

The natural gas industry has always been concerned ith accidental spills of liquified natural gas (LNG) from storage tanks into surrounding containment dikes. The LNG that is leaked to the dike area boils off and the vapors mix with the atmosphere forming a hazardous explsoive mixture within the dike walls. These hazardous mixtures can travel long distances into industrial or residential areas surroungind LNG storage facilities. Studies by the natural gas industry indicate that the hazards associated with accidental spills of LNG from storage tanks can be makedly reduced by insulating the diked areas surrounding these tanks. In this manner, the heat transfer from the dike surface to the LNG is reduced. The insulating composite is used to construct a thermal barrier between the walls and floor of the dike an the spilled LNG. The thermal conductivity, porosity, and compression strength of a concrete, polymer composite insulating material is discussed. 6 refs., 8 figs., 5 tbs.

Fontana, J.J.

1987-08-01T23:59:59.000Z

232

Tank 241-AZ-101 prototype corrosion probe four month status report  

SciTech Connect

High-level nuclear wastes at the Hanford Site are stored underground in carbon steel double-shell and single-shell tanks. The installation of a prototype corrosion monitoring system into double-shell tank 241-AZ-101 was completed in August, 1996. The system monitors fluctuations in corrosion current and potential (electrochemical noise) occurring on three electrode arrays immersed in the waste liquid and in the vapor space above the waste. The system also supports the use of Tafel and linear polarization resistance testing. By monitoring and analyzing the data from these techniques, changes in the corrosive characteristics of the waste have been rapidly detected and correlated with operational changes in the tank.

Edgemon, G.L., Westinghouse Hanford

1996-12-12T23:59:59.000Z

233

Vapor spill pipe monitor  

DOE Patents (OSTI)

The invention is a method and apparatus for continually monitoring the composition of liquefied natural gas flowing from a spill pipe during a spill test by continually removing a sample of the LNG by means of a probe, gasifying the LNG in the probe, and sending the vaporized LNG to a remote ir gas detector for analysis. The probe comprises three spaced concentric tubes surrounded by a water jacket which communicates with a flow channel defined between the inner and middle, and middle and outer tubes. The inner tube is connected to a pump for providing suction, and the probe is positioned in the LNG flow below the spill pipe with the tip oriented partly downward so that LNG is continuously drawn into the inner tube through a small orifice. The probe is made of a high thermal conductivity metal. Hot water is flowed through the water jacket and through the flow channel between the three tubes to provide the necessary heat transfer to flash vaporize the LNG passing through the inner channel of the probe. The gasified LNG is transported through a connected hose or tubing extending from the probe to a remote ir sensor which measures the gas composition.

Bianchini, G.M.; McRae, T.G.

1983-06-23T23:59:59.000Z

234

Carderock Tow Tank 3 | Open Energy Information  

Open Energy Info (EERE)

3 3 Overseeing Organization United States Naval Surface Warfare Center Hydrodynamic Testing Facility Type Tow Tank Length(m) 904.6 Beam(m) 6.4 Depth(m) 4.9 Water Type Freshwater Cost(per day) Contact POC Special Physical Features Two operable carriages on this basin: Carriage 3 (max towing speed of 15.4 m/s); Carriage 5 (max towing speed of 25.8 m/s) Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 25.8 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.6 Maximum Wave Length(m) 12.2 Wave Period Range(s) 0.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Irregular waves with a spectrum resembling typical ocean wave patterns with appropriate scale reductions. Wave Direction Uni-Directional

235

RECOMMENDATIONS FOR SAMPLING OF TANK 19 IN F TANK FARM  

SciTech Connect

Representative sampling is required for characterization of the residual material in Tank 19 prior to operational closure. Tank 19 is a Type IV underground waste storage tank located in the F-Tank Farm. It is a cylindrical-shaped, carbon steel tank with a diameter of 85 feet, a height of 34.25 feet, and a working capacity of 1.3 million gallons. Tank 19 was placed in service in 1961 and initially received a small amount of low heat waste from Tank 17. It then served as an evaporator concentrate (saltcake) receiver from February 1962 to September 1976. Tank 19 also received the spent zeolite ion exchange media from a cesium removal column that once operated in the Northeast riser of the tank to remove cesium from the evaporator overheads. Recent mechanical cleaning of the tank removed all mounds of material. Anticipating a low level of solids in the residual waste, Huff and Thaxton [2009] developed a plan to sample the waste during the final clean-up process while it would still be resident in sufficient quantities to support analytical determinations in four quadrants of the tank. Execution of the plan produced fewer solids than expected to support analytical determinations in all four quadrants. Huff and Thaxton [2009] then restructured the plan to characterize the residual separately in the North and the South regions: two 'hemispheres.' This document provides sampling recommendations to complete the characterization of the residual material on the tank bottom following the guidance in Huff and Thaxton [2009] to split the tank floor into a North and a South hemisphere. The number of samples is determined from a modification of the formula previously published in Edwards [2001] and the sample characterization data for previous sampling of Tank 19 described by Oji [2009]. The uncertainty is quantified by an upper 95% confidence limit (UCL95%) on each analyte's mean concentration in Tank 19. The procedure computes the uncertainty in analyte concentration as a function of the number of samples, and the final number of samples is determined when the reduction in the uncertainty from an additional sample no longer has a practical impact on results. The characterization of the full suite of analytes in the North and South hemispheres is currently supported by a single Mantis rover sample in each hemisphere. A floor scrape sample was obtained from a compact region near the center riser slightly in the South hemisphere and has been analyzed for a shortened list of key analytes. There is not enough additional material from the floor scrape sample material for completing the full suite of constituents. No floor scrape samples have been previously taken from the North hemisphere. The criterion to determine the number of additional samples was based on the practical reduction in the uncertainty when a new sample is added. This was achieved when five additional samples are obtained. In addition, two archived samples will be used if a contingency such as failing to demonstrate the comparability of the Mantis samples to the floor scrape samples occurs. To complete sampling of the Tank 19 residual floor material, four additional samples should be taken from the North hemisphere and four additional samples should be taken from the South hemisphere. One of the samples from each hemisphere will be archived in case of need. Three of the four additional samples from each hemisphere will be analyzed. Once the results are available, differences between the Mantis and three floor scrape sample results will be evaluated. If there are no statistically significant analyte concentration differences between the Mantis and floor scrape samples, those results will be combined and then UCL95%s will be calculated. If the analyte concentration differences between the Mantis and floor scrape samples are statistically significant, the UCL95%s will be calculated without the Mantis sample results. If further reduction in the upper confidence limits is needed and can be achieved by the addition of the archived samples, they will be analyzed and included in t

Harris, S.; Shine, G.

2009-12-14T23:59:59.000Z

236

Military - Tougher tanks | ornl.gov  

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

Military - Tougher tanks Improving welds of heavy and light armored fighting vehicles is the target of a collaboration among Oak Ridge National Laboratory, the U.S. Army Tank...

237

Technical requirements specification for tank waste retrieval  

Science Conference Proceedings (OSTI)

This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

Lamberd, D.L.

1996-09-26T23:59:59.000Z

238

Tanks 18/19: Sample Characterization, Method Development and ...  

Measurement of radioactive constituents in tank. ... SRS Waste Tank . 5 ... Low Level Measurements Ra-226 1*10-4

239

Savannah River Site- Tank 48 Briefing on SRS Tank 48 Independent Technical Review  

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

This presentation outlines the SRS Tank 48 ITR listing observations, conclusions, and TPB processing.

240

Tank 41H bounding uranium enrichment  

Science Conference Proceedings (OSTI)

The intent of this document is to combine data from salt samples and historical process information to bound the uranium (U-235) enrichment which could be expected in the upper portion of the salt in Tank 41H. This bounding enrichment will be used in another document to establish a nuclear safety basis for initial salt removal operations. During the processing period of interest (4/82-4/87), waste was fed to the 2H Evaporator from Tank 43H, and the evaporator bottoms were sent to Tank 41H where the bottoms were allowed to cool (resulting in the formation of salt deposits in the tank). As Tank 41H was filled with concentrate, the supernate left after salt formation was recycled back to Tank 43H and reprocessed through the evaporator along with any additional waste which had been added to Tank 43H. As Tank 41 H filled with salt, this recycle took place with increasing frequency because it took less time to fill the decreased volume with evaporator concentrate. By determining which of the sampled waste tanks were receiving fresh waste from the canyons at the time the tanks were sampled (from published transfer records), it was possible to deduce which samples were likely representative of fresh canyon waste. The processing that was being carried out in the Separation canyons when these tanks were sampled, should be comparable to the processing while Tank 41H was being filled.

Cavin, W.S.

1994-07-12T23:59:59.000Z

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


241

EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review |  

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

Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review Environmental Management Advisory Board EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review Report Number TWS #003 EMAB EM-TWS SRS / Hanford Tank Waste June 23, 2011 This is the second report of the Environmental Management Tank Waste Subcommittee (EMTWS) of the Environmental Management Advisory Board (EMAB). The first report was submitted and accepted by the Assistant Secretary for Environmental Management (EM-1) in September 2010. The EM-TWS responded to three charges from EM-1 regarding the Waste Treatment and Immobilization Plant at Hanford (WTP) under construction in Richland, Washington. EM's responses were timely, and efforts have been

242

Savannah River Site - Tank 48 Briefing on SRS Tank 48 Independent Technical Review  

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

Tank 48 Tank 48 Independent Technical Review August 2006 2 SRS Tank 48 ITR SRS Tank 48 ITR Key ITR Observation Two distinct problems: Removing tetraphenylborate (TPB) waste and then cleaning the tank sufficiently to support return to service Processing contents to eliminate TPB hazard August 2006 3 SRS Tank 48 ITR SRS Tank 48 ITR Overarching ITR Conclusions 1. TPB Processing is on the right track - DOE/WSRC have selected the most promising candidates - Fluidized Bed Steam Reforming (FBSR) is the most technically attractive and mature of the candidate processes August 2006 4 SRS Tank 48 ITR SRS Tank 48 ITR Overarching Conclusions (continued) 2. Heel removal and tank cleanout will be a very challenging task. Compounding issues: - Physical difficulties in cleanout (access, congestion, etc.)

243

Intercalibrating Microwave Satellite Observations for Monitoring Long-Term Variations in Upper- and Midtropospheric Water Vapor  

Science Conference Proceedings (OSTI)

This paper analyzes the growing archive of 183-GHz water vapor absorption band measurements from the Advanced Microwave Sounding Unit B (AMSU-B) and Microwave Humidity Sounder (MHS) on board polar-orbiting satellites and document adjustments ...

Eui-Seok Chung; Brian J. Soden; Viju O. John

2013-10-01T23:59:59.000Z

244

Applicability of AIRS Monthly Mean Atmospheric Water Vapor Profiles over the Tibetan Plateau Region  

Science Conference Proceedings (OSTI)

The research explores the applicability of the gridded (level 3) monthly tropospheric water vapor (version 5) retrievals from the Atmospheric Infrared Sounder (AIRS) instrument and the Advanced Microwave Sounding Unit (AMSU) on board the NASA Aqua ...

Yuwei Zhang; Donghai Wang; Panmao Zhai; Guojun Gu

2012-11-01T23:59:59.000Z

245

TNKVNT: A model of the Tank 48 purge/ventilation exhaust system. Revision 1  

DOE Green Energy (OSTI)

The waste tank purge ventilation system for Tank 48 is designed to prevent dangerous concentrations of hydrogen or benzene from accumulating in the gas space of the tank. Fans pull the gas/water vapor mixture from the tank gas space and pass it sequentially through a demister, a condenser, a reheater, and HEPA filters before discharging to the environment. Proper operation of the HEPA filters requires that the gas mixture passing through them has a low relative humidity. The ventilation system has been modified by increasing the capacity of the fans and changing the condenser from a two-pass heat exchanger to a single-pass heat exchanger. It is important to understand the impact of these modifications on the operation of the system. A hydraulic model of the ventilation exhaust system has been developed. This model predicts the properties of the air throughout the system and the flowrate through the system, as functions of the tank gas space and environmental conditions. This document serves as a Software Design Report, a Software Coding report, and a User`s Manual. All of the information required for understanding and using this code is herein contained: the governing equations are fully developed, the numerical algorithms are described in detail, and an extensively commented code listing is included. This updated version of the code models the entire purge ventilation system, and is therefore more general in its potential applications.

Shadday, M.A. Jr.

1996-04-01T23:59:59.000Z

246

FLAMMABILITY CHARACTERISTICS OF COMBUSTIBLE GASES AND VAPORS  

Office of Scientific and Technical Information (OSTI)

Bulletin 627 Bulletin 627 BUREAU o b MINES FLAMMABILITY CHARACTERISTICS OF COMBUSTIBLE GASES AND VAPORS By Michael G. Zabetakis DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement,

247

ICPP Tank Farm planning through 2012  

SciTech Connect

Historically, liquid high-level waste (HLW) generated at the Idaho Chemical Processing Plant has been stored in the Tank Farm after which it is calcined with the calcine being stored in stainless steel bins. Following the curtailment of spent nuclear fuel reprocessing in 1992, the HLW treatment methods were re-evaluated to establish a path forward for producing a final waste form from the liquid sodium bearing wastes (SBW) and the HLW calcine. Projections for significant improvements in waste generation, waste blending and evaporation, and calcination were incorporated into the Tank Farm modeling. This optimized modeling shows that all of the SBW can be calcined by the end of 2012 as required by the Idaho Settlement Agreement. This Tank Farm plan discusses the use of each of the eleven HLW tanks and shows that two tanks can be emptied, allowing them to be Resource Conservation and Recovery Act closed by 2006. In addition, it describes the construction of each tank and vault, gives the chemical concentrations of the contents of each tank, based on historical input and some sampling, and discusses the regulatory drivers important to Tank Farm operation. It also discusses new waste generation, the computer model used for the Tank Farm planning, the operating schedule for each tank, and the schedule for when each tank will be empty and closed.

Palmer, W.B.; Millet, C.B.; Staiger, M.D.; Ward, F.S.

1998-04-01T23:59:59.000Z

248

VAPOR SHIELD FOR INDUCTION FURNACE  

DOE Patents (OSTI)

This patent relates to a water-cooled vapor shield for an inductlon furnace that will condense metallic vapors arising from the crucible and thus prevent their condensation on or near the induction coils, thereby eliminating possible corrosion or shorting out of the coils. This is accomplished by placing, about the top, of the crucible a disk, apron, and cooling jacket that separates the area of the coils from the interior of the cruclbIe and provides a cooled surface upon whlch the vapors may condense.

Reese, S.L.; Samoriga, S.A.

1958-03-11T23:59:59.000Z

249

Vapor adsorption process  

SciTech Connect

The removal of undesirable acid components from sour natural gas is often accomplished by a vapor adsorption process wherein a bed of solid adsorbent material is contacted with an inlet gas stream so that desired components contained in the gas stream are adsorbed on the bed, then regenerated by contact with a heated regeneration gas stream. Adsorbed components are desorbed from the bed and the bed is cooled preparatory to again being contacted with the inlet gas stream. By this process, the bed is contacted, during the regeneration cycle, with a selected adsorbable material. This material has the property of being displaced from the bed by the desired components and has a heat of desorption equal to or greater than the heat of adsorption of the desired components. When the bed is contacted with the inlet gas stream, the selected adsorbable material is displaced by the desired components resulting in the temperature of the bed remaining relatively constant, thereby allowing the utilization of the maximum bed adsorption capacity. (4 claims)

Snyder, C.F.; Casad, B.M.

1973-04-24T23:59:59.000Z

250

Life Extension of Aging High-Level Waste Tanks  

Science Conference Proceedings (OSTI)

The Double Shell Tanks (DSTs) play a critical role in the Hanford High-Level Waste Treatment Complex, and therefore activities are underway to protect and better understand these tanks. The DST Life Extension Program is focused on both tank life extension and on evaluation of tank integrity. Tank life extension activities focus on understanding tank failure modes and have produced key chemistry and operations controls to minimize tank corrosion and extend useful tank life. Tank integrity program activities have developed and applied key technologies to evaluate the condition of the tank structure and predict useful tank life. Program results to date indicate that DST useful life can be extended well beyond the original design life and allow the existing tanks to fill a critical function within the Hanford High-Level Waste Treatment Complex. In addition the tank life may now be more reliably predicted, facilitating improved planning for the use and possible future replacement of these tanks.

Bryson, D.; Callahan, V.; Ostrom, M.; Bryan, W.; Berman, H.

2002-02-26T23:59:59.000Z

251

Evaluation of 241 AN tank farm flammable gas behavior  

DOE Green Energy (OSTI)

The 241 AN Tank Farm tanks 241-AN-103, -104, and 105 are Flammable Gas Watch List tanks. Characteristics exhibited by these tanks (i.e., surface level drops, pressure increases, and temperature profiles) are similar to those exhibited by tank 241-SY-101, which is also a Watch List tank. Although the characteristics exhibited by tank 241-SY-101 are also present in tanks 241-AN-103, -104, and 105, they are exhibited to a lesser degree in the AN Tank Farm tanks. The 241 AN Tank Farm tanks have only small surface level drops, and the pressure changes that occur are not sufficient to release an amount of gas that would cause the dome space to exceed the lower flammability limit (LFL) for hydrogen. Therefore, additional restrictions are probably unnecessary for working within the 241 AN Tank Farm, either within the dome space of the tanks or in the waste.

Reynolds, D.A.

1994-01-01T23:59:59.000Z

252

TANK 40 FINAL SLUDGE BATCH 8 CHEMICAL CHARACTERIZATION RESULTS  

SciTech Connect

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

Bannochie, C.

2013-09-19T23:59:59.000Z

253

CRITICAL ASSUMPTIONS IN THE F-TANK FARM CLOSURE OPERATIONAL DOCUMENTATION REGARDING WASTE TANK INTERNAL CONFIGURATIONS  

SciTech Connect

The intent of this document is to provide clarification of critical assumptions regarding the internal configurations of liquid waste tanks at operational closure, with respect to F-Tank Farm (FTF) closure documentation. For the purposes of this document, FTF closure documentation includes: (1) Performance Assessment for the F-Tank Farm at the Savannah River Site (hereafter referred to as the FTF PA) (SRS-REG-2007-00002), (2) Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site (DOE/SRS-WD-2012-001), (3) Tier 1 Closure Plan for the F-Area Waste Tank Systems at the Savannah River Site (SRR-CWDA-2010-00147), (4) F-Tank Farm Tanks 18 and 19 DOE Manual 435.1-1 Tier 2 Closure Plan Savannah River Site (SRR-CWDA-2011-00015), (5) Industrial Wastewater Closure Module for the Liquid Waste Tanks 18 and 19 (SRRCWDA-2010-00003), and (6) Tank 18/Tank 19 Special Analysis for the Performance Assessment for the F-Tank Farm at the Savannah River Site (hereafter referred to as the Tank 18/Tank 19 Special Analysis) (SRR-CWDA-2010-00124). Note that the first three FTF closure documents listed apply to the entire FTF, whereas the last three FTF closure documents listed are specific to Tanks 18 and 19. These two waste tanks are expected to be the first two tanks to be grouted and operationally closed under the current suite of FTF closure documents and many of the assumptions and approaches that apply to these two tanks are also applicable to the other FTF waste tanks and operational closure processes.

Hommel, S.; Fountain, D.

2012-03-28T23:59:59.000Z

254

Carderock Tow Tank 2 | Open Energy Information  

Open Energy Info (EERE)

2 2 Overseeing Organization United States Naval Surface Warfare Center Hydrodynamic Testing Facility Type Tow Tank Length(m) 574.9 Beam(m) 15.5 Depth(m) 6.7 Water Type Freshwater Cost(per day) Contact POC Special Physical Features Carriage 2 is located on this basin Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 10.3 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.6 Maximum Wave Length(m) 12.2 Wave Period Range(s) 0.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Irregular waves with a spectrum resembling typical ocean wave patterns with appropriate scale reductions Wave Direction Uni-Directional Simulated Beach Yes Description of Beach The wave absorber spans the full width of the basin at the end opposite the wavemaker dome, the absorbers are a discontinuous 12 degree slope type made up of 12 permeable layers of rectangular precast concrete bar panels resting on an impermeable concrete slab supported by a structural steel framework, the center section of the absorber is of wood construction & can be raised and lowered as a unit to provide model access to and from the fitting-out dry dock located at the end of the basin.

255

Enhanced Tank Waste Strategy Update  

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

Reduce the life-cycle costs and accelerate the cleanup of the Cold War environmental legacy www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 cleanup of the Cold War environmental legacy Shirley J. Olinger Associate Principal Deputy for Corporate Operations EMAB Presentation June 23, 2011 EM Priorities: Activities to maintain a safe, secure, and compliant posture in the EM complex Radioactive tank waste stabilization, treatment, and disposal Spent (used) nuclear fuel storage, receipt, and disposition "To-Go Life-Cycle Costs" ($185B - $218B as of the FY 2012 Request) Programmatic support activities* 10% Radioactive tank waste stabilization, treatment and disposal 38% Excess facilities decontamination and decommissioning

256

High Pressure Hydrogen Tank Manufacturing  

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

Workshop Workshop High Pressure Hydrogen Tank Manufacturing Mark Leavitt Quantum Fuel Systems Technologies Worldwide, Inc. August 11, 2011 This presentation does not contain any proprietary, confidential, or otherwise restricted information History of Innovations... Announced breakthrough in all-composite lightweight, high capacity, low-cost fuel storage technologies. * Developed a series of robust, OEM compatible electronic control products. Developed H 2 storage system for SunLine Tran-sit Hythane® bus. Awarded patent for integrated module including in-tank regulator * Developed high efficiency H 2 fuel storage systems for DOE Future Truck programs Developed H 2 storage and metering system for Toyota's FCEV platform. First to certify 10,000 psi systems in Japan

257

U.S. Department of Energy Onboard Storage Tank Workshop Notes  

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

U.S. Department of Energy U.S. Department of Energy Onboard Storage Tank Workshop Workshop Notes April 29, 2010 Sandia National Laboratories - Livermore, CA 2 Report from the Onboard Storage Tank Workshop Livermore, CA April 29 th , 2010 The Onboard Storage Tank Workshop was held on April 29 th , 2010, at Sandia National Laboratories (SNL) in Livermore, CA. The Workshop was co-hosted by SNL and the United States Department of Energy (DOE). The purpose of the Workshop was to identify key issues including research and development (R&D) needs, regulations, codes and standards (RCS), and a path forward to enable the deployment of hydrogen storage tanks in early market fuel cell applications. Background The objectives of the Workshop were to: * Provide initial follow up to the DOE and Department of Transportation (DOT)

258

Tank Waste Corporate Board Meeting 03/05/09 | Department of Energy  

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

Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 The following documents are associated with the Tank Waste Corporate Board Meeting held on March 5th, 2009. Overview of Integrated Waste Treatment Unit Desired PU Loading During Vitrification HLW System Integrated Project Team Waste Determination and Section 3116 of the 2005 National Defense Authorization Act - HQ Perspective Status of Art & Practice of Performance Assessment within the DOE Complex Experience from the Short Course on Introduction to Nuclear Chemistry and Fuel Cycle Separations and Future Educational Opportunities Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission Performance Assessment Community of Practice Action Item Review and Status

259

RECOMMENDATIONS FOR SAMPLING OF TANK 18 IN F TANK FARM  

SciTech Connect

Representative sampling is required for characterization of the residual floor material in Tank 18 prior to operational closure. Tank 18 is an 85-foot diameter, 34-foot high carbon steel tank with nominal operating volume of 1,300,000 gallons. It is a Type IV tank, and has been in service storing radioactive materials since 1959. Recent mechanical cleaning of the tank removed all mounds of material. Anticipating a low level of solids in the residual material, Huff and Thaxton [2009] developed a plan to sample the material during the final clean-up process while it would still be resident in sufficient quantities to support analytical determinations in four quadrants of the tank. Execution of the plan produced fewer solids than expected to support analytical determinations in all four quadrants. Huff and Thaxton [2009] then restructured the plan to characterize the residual floor material separately in the North and the South regions: two 'hemispheres.' This document provides sampling recommendations to complete the characterization of the residual material on the tank bottom following the guidance in Huff and Thaxton [2009] to split the tank floor into a North and a South hemisphere. The number of samples is determined from a modification of the formula previously published in Edwards [2001] and the sample characterization data for previous sampling of Tank 18 described by Oji [2009]. The uncertainty is quantified by an upper 95% confidence limit (UCL95%) on each analyte's mean concentration in Tank 18. The procedure computes the uncertainty in analyte concentration as a function of the number of samples, and the final number of samples is determined when the reduction in the uncertainty from an additional sample no longer has a practical impact on results. The characterization of the full suite of analytes in the North hemisphere is currently supported by a single Mantis rover sample obtained from a compact region near the center riser. A floor scrape sample was obtained from a compact region near the northeast riser and has been analyzed for a shortened list of key analytes. Since the unused portion of the floor scrape sample material is archived and available in sufficient quantity, additional analyses need to be performed to complete results for the full suite of constituents. The characterization of the full suite of analytes in the South hemisphere is currently supported by a single Mantis rover sample; there have been no floor scrape samples previously taken from the South hemisphere. The criterion to determine the number of additional samples was based on the practical reduction in the uncertainty when a new sample is added. This was achieved when five additional samples are obtained. In addition, two archived samples will be used if a contingency such as failing to demonstrate the comparability of the Mantis samples to the floor scrape samples occurs. To complete sampling of the Tank 18 residual floor material, three additional samples should be taken from the North hemisphere and four additional samples should be taken from the South hemisphere. One of the samples from each hemisphere will be archived in case of need. Two of the three additional samples from the North hemisphere and three of the four additional samples from the South hemisphere will be analyzed. Once the results are available, differences between the Mantis and three floor scrape samples (the sample previously obtained near NE riser plus the two additional samples that will be analyzed) results will be evaluated. If there are no statistically significant analyte concentration differences between the Mantis and floor scrape samples, those results will be combined and then UCL95%s will be calculated. If the analyte concentration differences between the Mantis and floor scrape samples are statistically significant, the UCL95%s will be calculated without the Mantis sample results. If further reduction in the upper confidence limits is needed and can be achieved by the addition of the archived samples, they will be analyzed and included in the stati

Shine, G.

2009-12-14T23:59:59.000Z

260

Atmospheric Water Vapor over China  

Science Conference Proceedings (OSTI)

Chinese radiosonde data from 1970 to 1990 are relatively homogeneous in time and are used to examine the climatology, trends, and variability of Chinas atmospheric water vapor content. The climatological distribution of precipitable water (PW) ...

Panmao Zhai; Robert E. Eskridge

1997-10-01T23:59:59.000Z

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


261

241-AZ Tank Farm Construction Extent of Condition Review for Tank Integrity  

SciTech Connect

This report provides the results of an extent of condition construction history review for tanks 241-AZ-101 and 241-AZ-102. The construction history of the 241-AZ tank farm has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In the 241-AZ tank farm, the second DST farm constructed, both refractory quality and tank and liner fabrication were improved.

Barnes, Travis J.; Boomer, Kayle D.; Gunter, Jason R.; Venetz, Theodore J.

2013-07-30T23:59:59.000Z

262

241-SY Tank Farm Construction Extent of Condition Review for Tank Integrity  

SciTech Connect

This report provides the results of an extent of condition construction history review for tanks 241-SY-101, 241-SY-102, and 241-SY-103. The construction history of the 241-SY tank farm has been reviewed to identify issues similar to those experienced during tank 241-AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank 241-AY-102 as the comparison benchmark. In the 241-SY tank farm, the third DST farm constructed, refractory quality and stress relief were improved, while similar tank and liner fabrication issues remained.

Barnes, Travis J.; Boomer, Kayle D.; Gunter, Jason R.; Venetz, Theodore J.

2013-07-25T23:59:59.000Z

263

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT BUCKLING EVALUATION METHODS & RESULTS FOR THE PRIMARY TANKS  

SciTech Connect

This report documents a detailed buckling evaluation of the primary tanks in the Hanford double shell waste tanks. The analysis is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raise by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review (in April and May 2001) of work being performed on the double-shell tank farms, and the operation of the aging waste facility (AWF) primary tank ventilation system.

MACKEY, T.C.

2006-03-17T23:59:59.000Z

264

Vapor deposition of hardened niobium  

DOE Patents (OSTI)

A method of coating ceramic nuclear fuel particles containing a major amount of an actinide ceramic in which the particles are placed in a fluidized bed maintained at ca. 800.degree. to ca. 900.degree. C., and niobium pentachloride vapor and carbon tetrachloride vapor are led into the bed, whereby niobium metal is deposited on the particles and carbon is deposited interstitially within the niobium. Coating apparatus used in the method is also disclosed.

Blocher, Jr., John M. (Columbus, OH); Veigel, Neil D. (Columbus, OH); Landrigan, Richard B. (Columbus, OH)

1983-04-19T23:59:59.000Z

265

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM - 2011  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2011 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2011 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2011-00026, HLW Tank Farm Inspection Plan for 2011, were completed. Ultrasonic measurements (UT) performed in 2011 met the requirements of C-ESR-G-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 25, 26 and 34 and the findings are documented in SRNL-STI-2011-00495, Tank Inspection NDE Results for Fiscal Year 2011, Waste Tanks 25, 26, 34 and 41. A total of 5813 photographs were made and 835 visual and video inspections were performed during 2011. A potential leaksite was discovered at Tank 4 during routine annual inspections performed in 2011. The new crack, which is above the allowable fill level, resulted in no release to the environment or tank annulus. The location of the crack is documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.6.

West, B.; Waltz, R.

2012-06-21T23:59:59.000Z

266

RETRIEVAL & TREATMENT OF HANFORD TANK WASTE  

SciTech Connect

The Hanford Tank Farms contain 53 million gal of radioactive waste accumulated during over 50 years of operations. The waste is stored in 177 single-shell and double-shell tanks in the Hanford 200 Areas. The single-shell tanks were put into operation from the early 1940s through the 1960s with wastes received from several generations of processing facilities for the recovery of plutonium and uranium, and from laboratories and other ancillary facilities. The overall hanford Tank Farm system represents one of the largest nuclear legacies in the world driving towards completion of retrieval and treatment in 2028 and the associated closure activity completion by 2035. Remote operations, significant radiation/contamination levels, limited access, and old facilities are just some of the challenges faced by retrieval and treatment systems. These systems also need to be able to successfully remove 99% or more of the waste, and support waste treatment, and tank closure. The Tank Farm retrieval program has ramped up dramatically in the past three years with design, fabrication, installation, testing, and operations ongoing on over 20 of the 149 single-shell tanks. A variety of technologies are currently being pursued to retrieve different waste types, applications, and to help establish a baseline for recovery/operational efficiencies. The paper/presentation describes the current status of retrieval system design, fabrication, installation, testing, readiness, and operations, including: (1) Saltcake removal progress in Tanks S-102, S-109, and S-112 using saltcake dissolution, modified sluicing, and high pressure water lancing techniques; (2) Sludge vacuum retrieval experience from Tanks C-201, C-202, C-203, and C-204; (3) Modified sluicing experience in Tank C-103; (4) Progress on design and installation of the mobile retrieval system for sludge in potentially leaking single-shell tanks, particularly Tank C-101; and (5) Ongoing installation of various systems in the next generation of tanks to be retrieved.

EACKER, J.A.; SPEARS, J.A.; STURGES, M.H.; MAUSS, B.M.

2006-01-20T23:59:59.000Z

267

Chemical vapor deposition sciences  

SciTech Connect

Chemical vapor deposition (CVD) is a widely used method for depositing thin films of a variety of materials. Applications of CVD range from the fabrication of microelectronic devices to the deposition of protective coatings. New CVD processes are increasingly complex, with stringent requirements that make it more difficult to commercialize them in a timely fashion. However, a clear understanding of the fundamental science underlying a CVD process, as expressed through computer models, can substantially shorten the time required for reactor and process development. Research scientists at Sandia use a wide range of experimental and theoretical techniques for investigating the science of CVD. Experimental tools include optical probes for gas-phase and surface processes, a range of surface analytic techniques, molecular beam methods for gas/surface kinetics, flow visualization techniques and state-of-the-art crystal growth reactors. The theoretical strategy uses a structured approach to describe the coupled gas-phase and gas-surface chemistry, fluid dynamics, heat and mass transfer of a CVD process. The software used to describe chemical reaction mechanisms is easily adapted to codes that model a variety of reactor geometries. Carefully chosen experiments provide critical information on the chemical species, gas temperatures and flows that are necessary for model development and validation. This brochure provides basic information on Sandia`s capabilities in the physical and chemical sciences of CVD and related materials processing technologies. It contains a brief description of the major scientific and technical capabilities of the CVD staff and facilities, and a brief discussion of the approach that the staff uses to advance the scientific understanding of CVD processes.

1992-12-31T23:59:59.000Z

268

SLUDGE BATCH 6/TANK 40 SIMULANT CHEMICAL PROCESS CELL SIMULATIONS  

SciTech Connect

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

Koopman, David

2010-04-28T23:59:59.000Z

269

Single-shell tank closure work plan. Revision A  

SciTech Connect

In January 1994, the Hanford Federal Facility Agreement and Conset Order (Tri-Party Agreement) was amended to reflect a revised strategy for remediation of radioactive waste in underground storage tanks. These amendments include milestones for closure of the single-shell tank (SST) operable units, to be initiated by March 2012 and completed by September 2024. This SST-CWP has been prepared to address the principal topical areas identified in Tri-Party Agreement Milestone M-45-06 (i.e., regulatory pathway, operable unit characterization, waste retrieval, technology development, and a strategy for achieving closure). Chapter 2.0 of this SST-CWP provides a brief description of the environmental setting, SST System, the origin and characteristics of SST waste, and ancillary equipment that will be remediated as part of SST operable unit closure. Appendix 2A provides a description of the hydrogeology of the Hanford Site, including information on the unsaturated sediments (vadose zone) beneath the 200 Areas Plateau. Chapter 3.0 provides a discussion of the laws and regulations applicable to closure of the SST farm operable units. Chapter 4.0 provides a summary description of the ongoing characterization activities that best align with the proposed regulatory pathway for closure. Chapter 5.0 describes aspects of the SST waste retrieval program, including retrieval strategy, technology, and sequence, potential tank leakage during retrieval, and considerations of deployment of subsurface barriers. Chapter 6.0 outlines a proposed strategy for closure. Chapter 7.0 provides a summary of the programs underway or planned to develop technologies to support closure. Ca. 325 refs.

NONE

1995-06-01T23:59:59.000Z

270

Storage Tanks (Arkansas) | Department of Energy  

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

Storage Tanks (Arkansas) Storage Tanks (Arkansas) Storage Tanks (Arkansas) < Back Eligibility Commercial Construction Fuel Distributor Industrial Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Program Info State Arkansas Program Type Environmental Regulations Siting and Permitting Provider Department of Environmental Quality The Storage Tanks regulations is a set of rules and permit requirements mandated by the Arkansas Pollution and Ecology Commission in order to protect the public health and the lands and the waters of the State of Arkansas. They are promulgated pursuant to Arkansas Code Annotated 8-7-801 and the Petroleum Storage Trust Fund Act 8-7-901. It covers all storage tanks, above (AST) and underground (UST). Most importantly these regulations establish that all owners and operators of storage tanks must

271

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2  

SciTech Connect

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

Lewis, BE

2003-10-07T23:59:59.000Z

272

Tank characterization report for single-shell tank 241-B-201  

SciTech Connect

This tank characterization report for Tank 241-B-201 was initially released as PNL-10100. This document is now being released as WHC-SD- WM-ER-550 in order to accommodate internet publishing.

Conner, J.M.

1996-06-06T23:59:59.000Z

273

ICPP tank farm closure study. Volume 1  

SciTech Connect

The disposition of INEEL radioactive wastes is now under a Settlement Agreement between the DOE and the State of Idaho. The Settlement Agreement requires that existing liquid sodium bearing waste (SBW), and other liquid waste inventories be treated by December 31, 2012. This agreement also requires that all HLW, including calcined waste, be disposed or made road ready to ship from the INEEL by 2035. Sodium bearing waste (SBW) is produced from decontamination operations and HLW from reprocessing of SNF. SBW and HLW are radioactive and hazardous mixed waste; the radioactive constituents are regulated by DOE and the hazardous constituents are regulated by the Resource Conservation and Recovery Act (RCRA). Calcined waste, a dry granular material, is produced in the New Waste Calcining Facility (NWCF). Two primary waste tank storage locations exist at the ICPP: Tank Farm Facility (TFF) and the Calcined Solids Storage Facility (CSSF). The TFF has the following underground storage tanks: four 18,400-gallon tanks (WM 100-102, WL 101); four 30,000-gallon tanks (WM 103-106); and eleven 300,000+ gallon tanks. This includes nine 300,000-gallon tanks (WM 182-190) and two 318,000 gallon tanks (WM 180-181). This study analyzes the closure and subsequent use of the eleven 300,000+ gallon tanks. The 18,400 and 30,000-gallon tanks were not included in the work scope and will be closed as a separate activity. This study was conducted to support the HLW Environmental Impact Statement (EIS) waste separations options and addresses closure of the 300,000-gallon liquid waste storage tanks and subsequent tank void uses. A figure provides a diagram estimating how the TFF could be used as part of the separations options. Other possible TFF uses are also discussed in this study.

Spaulding, B.C.; Gavalya, R.A.; Dahlmeir, M.M. [and others

1998-02-01T23:59:59.000Z

274

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

West, B.; Waltz, R.

2011-06-23T23:59:59.000Z

275

Unit Conversion  

Science Conference Proceedings (OSTI)

Unit Conversion. ... Unit Conversion Example. "If you have an amount of unit of A, how much is that in unit B?"; Dimensional Analysis; ...

2012-12-04T23:59:59.000Z

276

Underground Storage Tank Regulations | Department of Energy  

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

Underground Storage Tank Regulations Underground Storage Tank Regulations Underground Storage Tank Regulations < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Program Info State Mississippi Program Type Environmental Regulations Siting and Permitting Provider Department of Environmental Quality The Underground Storage Tank Regulations is relevant to all energy projects

277

Supporting document for the historical tank content estimate for AN-tank farm  

Science Conference Proceedings (OSTI)

This Supporting Document provides historical in-depth characterization information on AN-Tank Farm, such as historical waste transfer and level data, tank physical information, temperature plots, liquid observation well plots, chemical analyte and radionuclide inventories for the Historical Tank Content Estimate Report for the Southeast Quadrant of the Hanford 200 Areas.

Brevick, C.H.; Stroup, J.L.; Funk, J.W., Fluor Daniel Hanford

1997-03-06T23:59:59.000Z

278

Supporting document for the SW Quadrant Historical Tank Content Estimate for U-Tank Farm  

Science Conference Proceedings (OSTI)

This Supporting Document provides historical characterization information gathered on U-Tank Farm, such as historical waste transfer and level data, tank physical information, temperature data, sampling data, and drywell and liquid observation well data for Historical Tank Content Estimate of the SW Quadrant at the Hanford 200 West Area.

Brevick, C.H.; Gaddis, L.A.; Johnson, E.D.

1994-06-01T23:59:59.000Z

279

Supporting document for the historical tank content estimate for BY Tank Farm  

Science Conference Proceedings (OSTI)

This document provides historical evaluations of the radioactive mixed wastes stored in the Hanford Site 200-East Area underground single-shell tanks (SSTs). A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy (DOE) and Department of Defense (DOD) contractors. The historical data will supplement information gathered from in-tank core sampling activities that are currently underway. A tank history review that is accompanied by current characterization data creates a complete and reliable inventory estimate. Additionally, historical review of the tanks may reveal anomalies or unusual contents that are critical to characterization and post characterization activities. Complete and accurate tank waste characterizations are critical first steps for DOE and Westinghouse Hanford Company safety programs, waste pretreatment, and waste retrieval activities. The scope of this document is limited to the SSTs in the BY Tank Farm of the northeast quadrant of the 200 East Area. Nine appendices contain data on: tank level histories; temperature graphs; surface level graphs; drywell graphs; riser configuration and tank cross section; sampling data; tank photographs; unknown tank transfers; and tank layering comparison. 113 refs.

Brevick, C.H.; Gaddis, L.A.; Walsh, A.C.

1994-06-01T23:59:59.000Z

280

Supporting document for the historical tank content estimate for B Tank Farm  

Science Conference Proceedings (OSTI)

This document provides historical evaluations of the radioactive mixed wastes stored in the Hanford Site 200-East Area underground single-shell tanks (SSTs). A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy (DOE) and Department of Defense (DOD) contractors. The historical data will supplement information gathered from in-tank core sampling activities that are currently underway. A tank history review that is accompanied by current characterization data creates a complete and reliable inventory estimate. Additionally, historical review of the tanks may reveal anomalies or unusual contents that are critical to characterization and post characterization activities. Complete and accurate tank waste characterizations are critical first steps for DOE and Westinghouse Hanford Company safety programs, waste pretreatment, and waste retrieval activities. The scope of this document is limited to the SSTs in the B Tank Farm of the northeast quadrant of the 200 East Area. Nine appendices compile data on: tank level histories; temperature graphs; surface level graphs; drywell graphs; riser configuration and tank cross section; sampling data; tank photographs; unknown tank transfers; and tank layering comparison. 113 refs.

Brevick, C.H.; Gaddis, L.A.; Johnson, E.D.

1994-06-01T23:59:59.000Z

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


281

Supporting document for the historical tank content estimate for S tank farm  

SciTech Connect

This document provides historical evaluations of the radioactive mixed wastes stored in the Hanford Site 200 West Area underground single-shell tanks (SSTs). A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy (DOE) and Department of Defense (DOD) contractors. The historical data will supplement information gathered from in-tank core sampling activities that are currently underway. A tank history review that is accompanied by current characterization data creates a complete and reliable inventory estimate. Additionally, historical review of the tanks may reveal anomalies or unusual contents that are critical to characterization and post characterization activities. Complete and accurate tank waste characterizations are critical first steps for DOE and Westinghouse Hanford Company safety programs, waste pretreatment, and waste retrieval activities. The scope of this document is limited to all the SSTs in the S Tank Farm of the southwest quadrant of the 200 West Area. Nine appendices compile data on: tank level histories; temperature graphs; surface level graphs; drywell graphs; riser configuration and tank cross section; sampling data; tank photographs; unknown tank transfers; and tank layering comparison. 113 refs.

Brevick, C.H.; Gaddis, L.A.; Walsh, A.C.

1994-06-01T23:59:59.000Z

282

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SUMMARY OF COMBINED THERMAL AND OPERATING LOADS WITH SEISMIC ANALYSIS  

SciTech Connect

This report summarizes the results of the Double-Shell Tank Thermal and Operating Loads Analysis (TaLA) combined with the Seismic Analysis. This combined analysis provides a thorough, defensible, and documented analysis that will become a part of the overall analysis of record for the Hanford double-shell tanks (DSTs). The bases of the analytical work presented herein are two ANSYS{reg_sign} finite element models that were developed to represent a bounding-case tank. The TaLA model includes the effects of temperature on material properties, creep, concrete cracking, and various waste and annulus pressure-loading conditions. The seismic model considers the interaction of the tanks with the surrounding soil including a range of soil properties, and the effects of the waste contents during a seismic event. The structural evaluations completed with the representative tank models do not reveal any structural deficiencies with the integrity of the DSTs. The analyses represent 60 years of use, which extends well beyond the current date. In addition, the temperature loads imposed on the model are significantly more severe than any service to date or proposed for the future. Bounding material properties were also selected to provide the most severe combinations. While the focus of the analyses was a bounding-case tank, it was necessary during various evaluations to conduct tank-specific analyses. The primary tank buckling evaluation was carried out on a tank-specific basis because of the sensitivity to waste height, specific gravity, tank wall thickness, and primary tank vapor space vacuum limit. For this analysis, the occurrence of maximum tank vacuum was classified as a service level C, emergency load condition. The only area of potential concern in the analysis was with the buckling evaluation of the AP tank, which showed the current limit on demand of l2-inch water gauge vacuum to exceed the allowable of 10.4 inches. This determination was based on analysis at the design waste temperature of 350 F and the full 60-year corrosion allowance on the tank wall of 0.060 inch. However, analysis at a more realistic temperature of 250 F or corrosion allowance of 0.025 inch results in an acceptable demand/capacity ratio according to the ASME code criteria. Thus, buckling of the primary tank is judged to be unlikely for the current lack of corrosion in the tanks, and the expectation that the maximum waste temperature will not exceed 210 F. The reinforced concrete structure was evaluated as specified by the American Concrete Institute (ACI) code requirements for nuclear safety-related structures (ACI-349). The demand was demonstrated to be lower than the capacity at all locations. Revision 1 is being issued to document changes to the anchor bolt evaluation. RPP-RPT-32237 Rev. 1, Hanford Double-Shell Tank Thermal and Seismic Project-Increased Liquid Level Analysis for 241AP Tank Farms, described changes to the anchor bolt modeling and evaluation which were implemented in response to the independent reviewer's comments. Similar changes have been made in the bounding tank analysis and are documented in RPP-RPT-28968 Rev. 1. The conclusions of the previous releases of this report remain unchanged.

MACKEY TC; DEIBLER JE; RINKER MW; JOHNSON KI; ABATT FG; KARRI NK; PILLI SP; STOOPS KL

2009-01-15T23:59:59.000Z

283

Tank farms essential drawing plan  

SciTech Connect

The purpose of this document is to define criteria for selecting Essential Drawings, Support Drawings, and Controlled Print File (CPF) drawings and documents for facilities that are part of East and West Tank Farms. Also, the drawings and documents that meet the criteria are compiled separate listings. The Essential Drawing list and the Support Drawing list establish a priority for updating technical baseline drawings. The CPF drawings, denoted by an asterisk (*), defined the drawings and documents that Operations is required to maintain per the TWRS Administration Manual. The Routing Boards in Buildings 272-WA and 272-AW are not part of the CPF.

Domnoske-Rauch, L.A.

1998-08-04T23:59:59.000Z

284

united stadium. united station.  

E-Print Network (OSTI)

??DC United is one of Major League Soccers most decorated franchises, yet it still plays its home games within the crumbling confines of RFK Stadium. (more)

Groff, David R.

2011-01-01T23:59:59.000Z

285

Hanford Site C Tank Farm Meeting Summary - May 2010 | Department...  

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

0 Hanford Site C Tank Farm Meeting Summary - May 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

286

Hanford Site C Tank Farm Meeting Summary - July 2010 | Department...  

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

July 2010 Hanford Site C Tank Farm Meeting Summary - July 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm...

287

Hanford Site C Tank Farm Meeting Summary - May 2009 | Department...  

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

09 Hanford Site C Tank Farm Meeting Summary - May 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

288

Hanford Site C Tank Farm Meeting Summary - January 2010 | Department...  

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

0 Hanford Site C Tank Farm Meeting Summary - January 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

289

Hanford Site C Tank Farm Meeting Summary - January 2011 | Department...  

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

1 Hanford Site C Tank Farm Meeting Summary - January 2011 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

290

Hanford Site C Tank Farm Meeting Summary - October 2009 | Department...  

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

October 2009 Hanford Site C Tank Farm Meeting Summary - October 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm...

291

Hanford Site C Tank Farm Meeting Summary - September 2009 | Department...  

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

Hanford Site C Tank Farm Meeting Summary - September 2009 Hanford Site C Tank Farm Meeting Summary - September 2009 Meeting Summary for Development of the Hanford Site C Tank Farm...

292

Gas transport model for chemical vapor infiltration  

Science Conference Proceedings (OSTI)

A node-bond percolation model is presented for the gas permeability and pore surface area of the coarse porosity in woven fiber structures during densification by chemical vapor infiltration (CVI). Model parameters include the number of nodes per unit volume and their spatial distribution, and the node and bond radii and their variability. These parameters relate directly to structural features of the weave. Some uncertainty exists in the proper partition of the porosity between ``node`` and ``bond`` and between intra-tow and inter-tow, although the total is constrained by the known fiber loading in the structure. Applied to cloth layup preforms the model gives good agreement with the limited number of available measurements.

Starr, T.L. [School of Materials Science and Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332-0245 (United States)

1995-09-01T23:59:59.000Z

293

Report on the EH special review of occupational safety and health programs for the Hanford high-level waste tanks  

DOE Green Energy (OSTI)

This report documents a review of the occupational safety and health programs currently in effect at the tank farms located at the Hanford Reservation in Washington State. The review was undertaken by the Office of Environment, Safety and Health (EH) at the request of the Office of Environmental Restoration and Waste Management (EM) to determine whether issues important to worker safety and health have been properly identified, prioritized, and resolved. To carry out this task, four categories of safety and health activities were reviewed. The first category involved examination of management issues associated with the toxicity, flammability, and explosivity of gases and vapors generated by wastes. The second focused on waste tank characterization and technology programs that have been initiated at Hanford to identify, characterize and mitigate hazards associated with tanks generating hydrogen or containing ferrocyanides or organic compounds. The third evaluated worker safety and health programs necessary to support hazardous waste site operations it the tank farms. The fourth dealt with interim corrective actions currently in place, pending full implementation of site-specific safety and health programs to address waste vapor toxicity, flammability, and explosivity hazards.

Not Available

1992-11-01T23:59:59.000Z

294

Tank 40 Final SB7b Chemical Characterization Results  

SciTech Connect

A sample of Sludge Batch 7b (SB7b) was taken from Tank 40 in order to obtain radionuclide inventory analyses necessary for compliance with the Waste Acceptance Product Specifications (WAPS). The SB7b WAPS sample was also analyzed for chemical composition including noble metals and fissile constituents. At the Savannah River National Laboratory (SRNL) the 3-L Tank 40 SB7b sample was transferred from the shipping container into a 4-L high density polyethylene bottle and solids were allowed to settle over the weekend. Supernate was then siphoned off and circulated through the shipping container to complete the transfer of the sample. Following thorough mixing of the 3-L sample, a 558 g sub-sample was removed. This sub-sample was then utilized for all subsequent analytical samples. Eight separate aliquots of the slurry were digested, four with HNO{sub 3}/HCl (aqua regia) in sealed Teflon? vessels and four with NaOH/Na{sub 2}O{sub 2} (alkali or peroxide fusion) using Zr crucibles. Two Analytical Reference Glass ? 1 (ARG-1) standards were digested along with a blank for each preparation. Each aqua regia digestion and blank was diluted to 1:100 mL with deionized water and submitted to Analytical Development (AD) for inductively coupled plasma ? atomic emission spectroscopy (ICP-AES) analysis, inductively coupled plasma ? mass spectrometry (ICP-MS) analysis, atomic absorption spectroscopy (AA) for As and Se, and cold vapor atomic absorption spectroscopy (CV-AA) for Hg. Equivalent dilutions of the alkali fusion digestions and blank were submitted to AD for ICP-AES analysis. Tank 40 SB7b supernate was collected from a mixed slurry sample in the SRNL Shielded Cells and submitted to AD for ICP-AES, ion chromatography (IC), total base/free OH{sup -}/other base, total inorganic carbon/total organic carbon (TIC/TOC) analyses, and Cs-137 gamma scan. Weighted dilutions of slurry were submitted for IC, TIC/TOC, and total base/free OH-/other base analyses. Activities for U-233, U-235, and Pu-239 were determined from the ICP-MS data for the aqua regia digestions of the Tank 40 WAPS slurry using the specific activity of each isotope. The Pu-241 value was determined from a Pu-238/-241 method.

Bannochie, C. J.

2012-11-06T23:59:59.000Z

295

Use belowground storage tanks to manage stormwater  

Science Conference Proceedings (OSTI)

To meet performance and operating requirements under Resource Conservation and Recovery Act (RCRA), BP Oil`s Toledo Refinery installed two 10-million-gallon (MMgal) concrete belowground storage tanks to replace the existing impoundment ponds. Environmental, safety and operating criteria influenced how this older refinery could cost-effectively replace impoundment ponds without interrupting the production schedule. The north stormwater impoundment pond at BP Oil`s Toledo Refinery had received primary sludge, a RCRA-listed hazardous waste and material exceeding the toxic characteristic limit for benzene (0.5 ppm). Because the pond could not be adapted to meet RCRA standards, it had to be replaced by a system that met these standards and New Source Performance Standards (NSPS). Under normal operating conditions, stormwater was commingled with process wastewater and processed at the wastewater treatment unit (WWTU) before final disposal. However, when flow in the sewer system exceeded the capacity of the WWTU, excess flow was stored in an impoundment system. The case history shows how BP Oil`s project engineers, working with a consulting engineering group and a general contractor (GC), cost-effectively replaced the impoundment pond to handle stormwater runoff for the refinery.

Nedrow, J. [BP Oil Co., Toledo, OH (United States)

1996-01-01T23:59:59.000Z

296

Image Storage in Hot Vapors  

E-Print Network (OSTI)

We theoretically investigate image propagation and storage in hot atomic vapor. A $4f$ system is adopted for imaging and an atomic vapor cell is placed over the transform plane. The Fraunhofer diffraction pattern of an object in the object plane can thus be transformed into atomic Raman coherence according to the idea of ``light storage''. We investigate how the stored diffraction pattern evolves under diffusion. Our result indicates, under appropriate conditions, that an image can be reconstructed with high fidelity. The main reason for this procedure to work is the fact that diffusion of opposite-phase components of the diffraction pattern interfere destructively.

Zhao, L; Xiao, Y; Yelin, S F

2007-01-01T23:59:59.000Z

297

Image Storage in Hot Vapors  

E-Print Network (OSTI)

We theoretically investigate image propagation and storage in hot atomic vapor. A $4f$ system is adopted for imaging and an atomic vapor cell is placed over the transform plane. The Fraunhofer diffraction pattern of an object in the object plane can thus be transformed into atomic Raman coherence according to the idea of ``light storage''. We investigate how the stored diffraction pattern evolves under diffusion. Our result indicates, under appropriate conditions, that an image can be reconstructed with high fidelity. The main reason for this procedure to work is the fact that diffusion of opposite-phase components of the diffraction pattern interfere destructively.

L. Zhao; T. Wang; Y. Xiao; S. F. Yelin

2007-10-22T23:59:59.000Z

298

Double-Shell Tank Visual Inspection Changes REsulting from the Tank 241-AY-102 Primary Tank Leak - 14193  

SciTech Connect

As part of the Double-Shell Tank (DST) Integrity Program, remote visual inspections are utilized to perform qualitative in-service inspections of the DSTs in order to provide a general overview of the condition of the tanks. During routine visual inspections of tank 241-AY -1 02 (A Y -1 02) in August 2012, anomalies were identified on the annulus floor which resulted in further evaluations. In October 2012, Washington River Protection Solutions, LLC determined that the primary tank of AY -102 was leaking. Following identification of the tank AY-102 probable leak cause, evaluations considered the adequacy of the existing annulus inspection frequency with respect to the circumstances of the tank AY-1021eak and the advancing age of the DST structures. The evaluations concluded that the interval between annulus inspections should be shortened for all DSTs, and each annulus inspection should cover > 95 percent of annulus floor area, and the portion of the primary tank (i.e., dome, sidewall, lower knuckle, and insulating refractory) that is visible from the annulus inspection risers. In March 2013, enhanced visual inspections were performed for the six oldest tanks: 241-AY-101, 241-AZ-101,241-AZ-102, 241-SY-101, 241-SY-102, and 241-SY-103, and no evidence of leakage from the primary tank were observed. Prior to October 2012, the approach for conducting visual examinations of DSTs was to perform a video examination of each tank's interior and annulus regions approximately every five years (not to exceed seven years between inspections). Also, the annulus inspection only covered about 42 percent of the annulus floor.

Girardot, Crystal L.; Washenfelder, Dennis J.; Johnson, Jeremy M.; Engeman, Jason K.

2013-11-14T23:59:59.000Z

299

Structural analysis and evaluation of a mixer pump in a double-shell tank at the Hanford Site  

DOE Green Energy (OSTI)

The double-shell waste tank 241-SY-101 is a 1,000,000 gallon tank used to store radioactive waste at the Hanford Site near Richland, Washington. With time the waste has formed two layers of sludge, a convective and a nonconvective layer. In addition, a crest has formed over the surface of the waste, isolating the convective layer from the vapor space. Ongoing reactions in the waste cause a buildup of hydrogen molecules that become trapped within the nonconvective layer and under the crust. Over time, this hydrogen buildup increases pressure on the crest from beneath. Every 100 to 140 days, the pressure is released when the crust lifts upward in what is called a waste rollover. To prevent the release of a large volume of hydrogen to the vapor space, a mixer pump has been designed to be installed in the tank to circulate the waste and reduce or prevent the hydrogen buildup. The structural analysis and evaluation designed as part of the hydrogen mitigation test process and presented herein addresses the response of the mixer pump and the tank dome resulting from expected operational and design loads. The loads include deadweight, waste rollover, asymmetric thrust, and pump vibration, as well as seismic loads. The seismically induced loads take into consideration both the convective and the impulsive effects of the waste-filled tank. The structural evaluations were performed in accordance with applicable national codes and standards. The qualification of the mixer pump required the design of a unique mounting assembly to transfer the loads from the pump to the surrounding soil without overstressing the structural components such as the dome penetration riser. Also, special consideration was given to minimize the additional stresses in the already stressed concrete tank dome.

Rezvani, M.A.; Strehlow, J.P. [Westinghouse Hanford Co., Richland, WA (United States); Baliga, R. [ADVENT Engineering Services, Inc., San Ramon, CA (United States)

1993-08-01T23:59:59.000Z

300

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total of 5945 photographs were made and 1221 visual and video inspections were performed during 2007. Additionally, ultrasonic testing was performed on four Waste Tanks (15, 36, 37 and 38) in accordance with approved inspection plans that met the requirements of WSRC-TR-2002- 00061, Revision 2 'In-Service Inspection Program for High Level Waste Tanks'. The Ultrasonic Testing (UT) In-Service Inspections (ISI) are documented in a separate report that is prepared by the ISI programmatic Level III UT Analyst. Tanks 15, 36, 37 and 38 are documented in 'Tank Inspection NDE Results for Fiscal Year 2007'; WSRC-TR-2007-00064.

West, B; Ruel Waltz, R

2008-06-05T23:59:59.000Z

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


301

Tanks Focus Area annual report FY2000  

SciTech Connect

The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation effort with tanks containing hazardous and radioactive waste resulting from the production of nuclear materials. With some 90 million gallons of waste in the form of solid, sludge, liquid, and gas stored in 287 tanks across the DOE complex, containing approximately 650 million curies, radioactive waste storage tank remediation is the nation's highest cleanup priority. Differing waste types and unique technical issues require specialized science and technology to achieve tank cleanup in an environmentally acceptable manner. Some of the waste has been stored for over 50 years in tanks that have exceeded their design lives. The challenge is to characterize and maintain these contents in a safe condition and continue to remediate and close each tank to minimize the risks of waste migration and exposure to workers, the public, and the environment. In 1994, the DOE's Office of Environmental Management (EM) created a group of integrated, multiorganizational teams focusing on specific areas of the EM cleanup mission. These teams have evolved into five focus areas managed within EM's Office of Science and Technology (OST): Tanks Focus Area (TFA); Deactivation and Decommissioning Focus Area; Nuclear Materials Focus Area; Subsurface Contaminants Focus Area; and Transuranic and Mixed Waste Focus Area.

None

2000-12-01T23:59:59.000Z

302

Improved method for determining tank heel volumes  

SciTech Connect

As part of the tank calibration process, the instrument heel is that part of the tank that cannot be measured by the liquid level instrumentation. if the tank being calibrated is not a bottom drain tank, some volume of fluid will be present in the bottom of the tank after draining as much as possible. The amount of fluid remaining in the tank at the start of each run can be estimated by measuring a concentration change of an added spiking material. With the great improvement of liquid level measuring instruments, the total error associated with the instrument heel determination can be greatly affected by the laboratory method used to measure the concentration difference. At the Savannah River Site, the laboratory method used has historically been Direct Current Plasma Emission Spectroscopy, which yielded very marginal results at best. In the most recent tank calibrations, the laboratory method was changed to Absorption Spectrophotometry, which reduces the total error on the instrument heel measurement by a factor of 2.5 times. This paper describes the method used to determine tank instrument heels and the improvements made to this process.

Holt, S.H.; Livingston, R.R.; Nave, S.E.

1994-07-01T23:59:59.000Z

303

HANFORD WASTE TANK BUMP ACCIDENT & CONSEQUENCE ANALYSIS  

DOE Green Energy (OSTI)

Postulated physical scenarios leading to tank bumps were examined. A combination of a substantial supernatant layer depth, supernatant temperatures close to saturation, and high sludge temperatures are required for a tank bump to occur. Scenarios postulated at various times for sludge layers lacking substantial supernatant, such as superheat within the layer and fumarole formation leading to a bump were ruled out.

MEACHAM, J.E.

2005-02-22T23:59:59.000Z

304

Cellular glass insulation keeps liquefied gas from vaporizing  

SciTech Connect

The North West Shelf Project, located on the Burrup Peninsula in Western Australia, supplies much of that vast state with natural gas for domestic and industrial applications. Some of the gas is also exported to Japan as liquefied natural gas (LNG). While awaiting shipment to Japan, the LNG is stored at {minus}322 F in four storage tanks, each with a capacity of 2.5 million ft{sup 3}. When Woodside Offshore Petroleum Pty Ltd., operator of the LNG facility, selected insulation material for the storage tanks, it went in search of a material with more than just insulating value. Since the insulation is installed inside the tanks, it must be able to resist wicking or absorbing the LNG. Also, it had to have sufficient strength to withstand the weight of the 2.5 million ft{sup 3} of LNG without being crushed or losing its insulting properties. And, as a safety precaution, the selected materials should neither burn nor support combustion. Ultimately, Woodside selected a cellular glass insulation called Foamglas, from Pittsburgh Corning Corp., that met all the performance criteria and was cost competitive with the lesser-performing alternatives. Foamglas is produced from strong, inert borosilicate glass. Its insulating capability is provided by the tiny, closed cells of air encapsulated within the foam-like structure of the glass. Since the cells are closed,neither liquid nor vapor can enter the structure of the insulation. The inert glass itself will not absorb or react with LNG, nor will it burn or support a fire. The cellular structure provides effective insulation in both not and cold applications, and offers a fire barrier.

NONE

1995-11-01T23:59:59.000Z

305

Fuel Cell Technologies Office: Onboard Storage Tank Workshop  

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

Onboard Storage Tank Onboard Storage Tank Workshop to someone by E-mail Share Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Facebook Tweet about Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Twitter Bookmark Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Google Bookmark Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Delicious Rank Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Digg Find More places to share Fuel Cell Technologies Office: Onboard Storage Tank Workshop on AddThis.com... Publications Program Publications Technical Publications Educational Publications Newsletter Program Presentations Multimedia Conferences & Meetings Annual Merit Review Proceedings Workshop & Meeting Proceedings

306

DOE Selects Washington River Protection Solutions, LLC for Tank...  

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

Washington River Protection Solutions, LLC for Tank Operations Contract at Hanford Site DOE Selects Washington River Protection Solutions, LLC for Tank Operations Contract at...

307

Independent Oversight Review of Hanford Tank Farms Safety Basis...  

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

to create tank vacuum exceeding their analyzed capabilities, which could result in structural failures. The vacuum relief valves and other tank vacuum 3 protection devices are...

308

Independent Oversight Review of Hanford Tank Farms Safety Basis...  

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

Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades November 2011 Office of Safety and Emergency Management Evaluations Office of...

309

Hanford Site C Tank Farm Meeting Summary - March 2010 | Department...  

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

March 2010 Hanford Site C Tank Farm Meeting Summary - March 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Meeting Summary for...

310

Hanford Tank Waste Treatment and Immobilization Plan Project...  

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

Hanford Tank Waste Treatment and Immobilization Plan Project PIA, Richland Operations Office Hanford Tank Waste Treatment and Immobilization Plan Project PIA, Richland Operations...

311

What's going on Inside Today's Fuel Storage Tank?  

Science Conference Proceedings (OSTI)

... 14 Page 15. E85 tanks ? Minnesota has a high percentage of underground tanks at gas stations storing 85% ethanol ? Last ...

2013-08-28T23:59:59.000Z

312

Refrigeration system with a compressor-pump unit and a liquid ...  

The refrigeration system includes a compressor-pump unit and/or a liquid-injection assembly. The refrigeration system is a vapor-compression refrigera ...

313

Hydrogen Tank Testing R&D  

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

04.29.2010 | Presented by Joe Wong, P.Eng. 04.29.2010 | Presented by Joe Wong, P.Eng. DOE Tank Safety Workshop Hydrogen Tank Safety Testing 1 POWERTECH - Hydrogen & CNG Services  Certification testing of individual high pressure components  Design Verification, Performance, End-of-Life testing of complete fuel systems  Design, construction, and operation of Hydrogen Fill Stations  Safety Studies  Standards Development 2 PRESENTATION  Discuss CNG Field Performance Data  Discuss Safety Testing of Type 4 Tanks  Current work to support Codes & Standards Development 3 Storage Tank Technologies 4 basic types of tank designs  Type 1 - all metal  Type 2 - metal liner with hoop wrapped composite  Type 3 - metal liner with fully wrapped composite  Type 4 - Plastic liner with

314

Haynes Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Haynes Tow Tank Haynes Tow Tank Jump to: navigation, search Basic Specifications Facility Name Haynes Tow Tank Overseeing Organization Texas A&M (Haynes) Hydrodynamic Testing Facility Type Tow Tank Length(m) 45.7 Beam(m) 3.7 Depth(m) 3.0 Water Type Freshwater Cost(per day) $150/hour (excluding labor) Special Physical Features The tank includes a 7.6m by 3.7m by 1.5m deep sediment pit. Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 1.8 Length of Effective Tow(m) 24.4 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Description National Instruments LabView Number of channels 40 Cameras Yes Number of Color Cameras 6 Description of Camera Types 3 video; 3 digital

315

Tank characterization report for single-shell tank 241-BY-104  

SciTech Connect

This characterization report summarizes the available information on the historical uses, current status, and the sampling and analysis results of waste contained in underground storage tank 241-BY-104. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09. Tank 241-BY-104 is one of 12 single-shell tanks located in the BY-Tank Farm in the 200 East Area of the Hanford Site. Tank 241-BY-104 entered service in the first quarter of 1950 with a transfer of metal waste from an unknown source. Through cascading, the tank was full of metal waste by the second quarter of 1951. The waste was sluiced in the second quarter of 1954. Uranium recovery (tributyl phosphate) waste was sent from tank 241-BY-107 during the second quarter of 1955 and from tank 241-BY-110 during the third quarter of 1955. Most of this waste was sent to a crib during the fourth quarter of 1955. During the third and fourth quarters of 1956 and the second and third quarters of 1957, the tank received waste from the in-plant ferrocyanide scavenging process (PFeCN2) from tanks 241-BY-106, -107, -108, and -110. This waste type is predicted to compose the bottom layer of waste currently in the tank. The tank received PUREX cladding waste (CWP) periodically from 1961 to 1968. Ion-exchange waste from cesium recovery operations was received from tank 241-BX-104 during the second and third quarters of 1968. Tank 241-BY-104 received evaporator bottoms waste from the in-tank solidification process that was conducted in the BY-Tank Farm 0247from tanks 241 -BY- 109 and 241 -BY- 1 12 from 1970 to 1974. The upper portion of tank waste is predicted to be composed of BY saltcake. Tank 241-BY-104 was declared inactive in 1977. Waste was saltwell pumped from the tank during the third quarter of 1982 and the fourth quarter of 1985. Table ES-1 and Figure ES-1 describe tank 241-BY-104 and its status. The tank has an operating capacity of 2,869 kL and presently contains an estimated 1,234 kL of noncomplexed waste. Of this total volume, 568 kL are estimated to be sludge and 666 kL are estimated to be saltcake. The Hanlon values are not used because they are inconsistent with waste surface level measurements, and they will not be updated until the tank level stabilizes and the new surface photos are taken. This report summarizes the collection and analysis of two rotary-mode core samples obtained in October and November 1995 and reported in the Final Report for Tank 241-BY-104, Rotary Mode Cores 116 and 117. Cores 116 and 117 were obtained from risers 5 and IIA, respectively. The sampling event was performed to satisfy the requirements listed in the following documents: Tank Safety Screening Data Quality Objective , Data Requirements for the Ferrocyanide Safety Issue Developed through the Data Quality Objective Process, Data Quality Objective to Support Resolution of the Organic Fuel Rich Tank Safety Issue, Test Plan for Samples from Hanford Waste Tanks 241-BY-103, BY-104, BY-105, BY-106, BY-108, BY-110, YY-103, U-105, U-107, U-108, and U-109.

Benar, C.J.

1996-09-26T23:59:59.000Z

316

Definitions common to all certification and test procedures are in: D-200 Definitions for Certification Procedures and Test Procedures for Vapor Recovery Systems  

E-Print Network (OSTI)

For the purpose of this procedure, the term "ARB " refers to the State of California Air Resources Board, and the term "ARB Executive Officer " refers to the Executive Officer of the ARB or his or her authorized representative or designate. 1.1 General Applicability This procedure applies to the determination of the one minute static pressure performance of a vapor recovery system of a cargo tank by fluid mechanical principles. This procedure applies to any vapor emissions associated with the dispensing of any fluid, although it is written to reflect application to the hydrocarbon vapors associated with the dispensing of gasoline. 1.2 Determinations of Compliance and Violation Determinations of certain modes of compliance with and violation of certification specifications is outlined in 9. 1.3 Modifications Modification of this procedure may be necessary for vapors and fluids other than the hydrocarbon vapors associated with the dispensing of gasoline. Any modification of this method shall be subject to approval by the ARB Executive Officer. 2 PRINCIPLE AND SUMMARY OF TEST PROCEDURE Upon completion of loading operations at the bulk gasoline distribution facility, the gasoline cargo tank is pressurized, with nitrogen, to 18 inches water column. By using the total cargo California Air Resources Board March 17, 1999 TP-204.2, Page 1tank shell capacity, post-loading headspace volume, and the Ideal Gas Law, a one-minute maximum allowable pressure decay is calculated. The pressure decay is monitored for one minute and compliance is determined by comparison with the maximum allowable calculated value. The leak rate through the cargo tank internal vapor vent valve is similarly obtained. 3

unknown authors

1996-01-01T23:59:59.000Z

317

Atomic vapor laser isotope separation process  

DOE Patents (OSTI)

A laser spectroscopy system is utilized in an atomic vapor laser isotope separation process. The system determines spectral components of an atomic vapor utilizing a laser heterodyne technique. 23 figs.

Wyeth, R.W.; Paisner, J.A.; Story, T.

1990-08-21T23:59:59.000Z

318

Vapor Pressure Measurement of Supercooled Water  

Science Conference Proceedings (OSTI)

A new dewpoint hygrometer was developed for subfreezing temperature application. Vapor pressure of supercooled water was determined by measuring temperatures at the dew-forming surface and the vapor source ice under the flux density balance, and ...

N. Fukuta; C. M. Gramada

2003-08-01T23:59:59.000Z

319

Distribution of Tropical Tropospheric Water Vapor  

Science Conference Proceedings (OSTI)

Utilizing a conceptual model for tropical convection and observational data for water vapor, the maintenance of the vertical distribution of the tropical tropospheric water vapor is discussed. While deep convection induces large-scale subsidence ...

De-Zheng Sun; Richard S. Lindzen

1993-06-01T23:59:59.000Z

320

Atmospheric Water Vapor Characteristics at 70N  

Science Conference Proceedings (OSTI)

Using an extensive rawinsonde archive, characteristics of Arctic water vapor and its transports at 70N are examined for the period 19741991. Monthly-mean profiles and vertically integrated values of specific humidity and meridional vapor fluxes ...

Mark C. Serreze; Roger G. Barry; John E. Walsh

1995-04-01T23:59:59.000Z

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


321

Intercalibrating microwave satellite observations for monitoring long-term variations in upper and mid-tropospheric water vapor  

Science Conference Proceedings (OSTI)

We analyze the growing archive of 183 GHz water vapor absorption band measurements from Advanced Microwave Sounding Unit-B (AMSU-B) and Microwave Humidity Sounder (MHS) onboard polar orbiting satellites and document adjustments necessary to use ...

Eui-Seok Chung; Brian J. Soden; Viju O. John

322

Combustion modeling in waste tanks  

DOE Green Energy (OSTI)

This paper has two objectives. The first one is to repeat previous simulations of release and combustion of flammable gases in tank SY-101 at the Hanford reservation with the recently developed code GASFLOW-II. The GASFLOW-II results are compared with the results obtained with the HMS/TRAC code and show good agreement, especially for non-combustion cases. For combustion GASFLOW-II predicts a steeper pressure rise than HMS/TRAC. The second objective is to describe a so-called induction parameter model which was developed and implemented into GASFLOW-II and reassess previous calculations of Bureau of Mines experiments for hydrogen-air combustion. The pressure time history improves compared with the one-step model, and the time rate of pressure change is much closer to the experimental data.

Mueller, C.; Unal, C. [Los Alamos National Lab., NM (United States); Travis, J.R. [Los Alamos National Lab., NM (United States)]|[Forschungszentrum Karlsruhe (Germany). Inst. fuer Reaktorsicherheit

1997-08-01T23:59:59.000Z

323

Savannah River Tank Waste Residuals  

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

Savannah Savannah River Savannah River Tank Waste Residuals HLW Corporate Board November 6, 2008 1 November 6, 2008 Presentation By Sherri R. Ross Department of Energy Savannah River Operations Office The Issue * How clean is clean? * Ultimate Challenge - Justify highly radioactive radionuclides have been removed to the maximum extent practical? 2 removed to the maximum extent practical? - Building compelling regulatory documentation that will withstand intense scrutiny §3116 Requirements 1. Does not require disposal in deep geological repository 2. Highly radioactive radionuclides removed to the maximum extent practical 3. Meet the performance objectives in 10 CFR Part 3 3. Meet the performance objectives in 10 CFR Part 61, Subpart C 4. Waste disposed pursuant to a State-approved closure plan or permit Note: If it is anticipated that Class C disposal limits will be exceeded, additional

324

Vapor phase modifiers for oxidative coupling  

DOE Patents (OSTI)

Volatilized metal compounds retard vapor phase alkane conversion reactions in oxidative coupling processes that convert lower alkanes to higher hydrocarbons.

Warren, Barbara K. (Charleston, WV)

1991-01-01T23:59:59.000Z

325

LOW PRESSURE CHEMICAL VAPOR DEPOSITION OF POLYSILICON  

E-Print Network (OSTI)

THEORY The mass transport processes in low pressure chemical vapor deposition (LPCVD) are similar to those occuring in catalytic reactors

Gieske, R.J.

2011-01-01T23:59:59.000Z

326

Tank characterization report for Single-Shell Tank 241-T-107  

Science Conference Proceedings (OSTI)

Single shell tank 241-T-107 is a Hanford Site Ferrocyanide Watch List tank most recently sampled in March 1993. Analyses of materials obtained from tank T-107 were conducted to support the Ferrocyanide Unreviewed Safety Question (USQ) and the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-06 as well as Milestones M-44-05 and M-44-07. Characterization of the tank waste T-107 will support the ferrocyanide safety issue in order to classify the tank as safe, conditionally safe, or unsafe. This tank characterization report expands on the data found in Ferrocyanide Safety Program: Data Interpretation Report for Tank 241-T-107 Core Samples. Analysis of core samples obtained from tank T-107 strongly indicate the cyanide and oxidizer (nitrate/nitrite) concentrations in the tank waste are not significant enough to support a self-sustaining exothermic reaction. Therefore, the contents of tank T-107 present no imminent threat to the workers at the Hanford Site, the public, or the environment. Because the possibility of an exothermic reaction is remote, the consequences of an accident scenario, as proposed by the General Accounting Office, are not applicable.

Valenzuela, B.D.; Jensen, L.

1994-09-01T23:59:59.000Z

327

Vadose zone characterization project at the Hanford Tank Farms: U Tank Farm Report  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy Grand Junction Office (DOE-GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the gamma-ray-emitting radionuclides that are distributed in the vadose zone sediments beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources when possible, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information regarding vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. This information is presently limited to detection of gamma-emitting radionuclides from both natural and man-made sources. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank in a tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the U Tank Farm. Logging operations used high-purity germanium detection systems to acquire laboratory-quality assays of the gamma-emitting radionuclides in the sediments around and below the tanks. These assays were acquired in 59 boreholes that surround the U Tank Farm tanks. Logging of all boreholes was completed in December 1995, and the last Tank Summary Data Report for the U Tank Farm was issued in September 1996.

NONE

1997-05-01T23:59:59.000Z

328

TANK 4 CHARACTERIZATION, SETTLING, AND WASHING STUDIES  

SciTech Connect

A sample of PUREX sludge from Tank 4 was characterized, and subsequently combined with a Tank 51 sample (Tank 51-E1) received following Al dissolution, but prior to a supernate decant by the Tank Farm, to perform a settling and washing study to support Sludge Batch 6 preparation. The sludge source for the majority of the Tank 51-E1 sample is Tank 12 HM sludge. The Tank 51-E1 sample was decanted by SRNL prior to use in the settling and washing study. The Tank 4 sample was analyzed for chemical composition including noble metals. The characterization of the Tank 51-E1 sample, used here in combination with the Tank 4 sample, was reported previously. SRNL analyses on Tank 4 were requested by Liquid Waste Engineering (LWE) via Technical Task Request (TTR) HLE-TTR-2009-103. The sample preparation work is governed by Task Technical and Quality Assurance Plan (TTQAP), and analyses were controlled by an Analytical Study Plan and modifications received via customer communications. Additional scope included a request for a settling study of decanted Tank 51-E1 and a blend of decanted Tank 51-E1 and Tank 4, as well as a washing study to look into the fate of undissolved sulfur observed during the Tank 4 characterization. The chemistry of the Tank 4 sample was modeled with OLI Systems, Inc. StreamAnalyzer to determine the likelihood that sulfate could exist in this sample as insoluble Burkeite (2Na{sub 2}SO{sub 4} {center_dot} Na{sub 2}CO{sub 3}). The OLI model was also used to predict the composition of the blended tank materials for the washing study. The following conclusions were drawn from the Tank 4 analytical results reported here: (1) Any projected blend of Tank 4 and the current Tank 51 contents will produce a SB6 composition that is lower in Ca and U than the current SB5 composition being processed by DWPF. (2) Unwashed Tank 4 has a relatively large initial S concentration of 3.68 wt% on a total solids basis, and approximately 10% of the total S is present as an insoluble or undissolved form. (3) There is 19% more S than can be accounted for by IC sulfate measurement. This additional soluble S is detected by ICP-AES analysis of the supernate. (4) Total supernate and slurry sulfur by ICP-AES should be monitored during washing in addition to supernate sulfate in order to avoid under estimating the amount of sulfur species removed or remaining in the supernate. (5) OLI simulation calculations show that the presence of undissolved Burkeite in the Tank 4 sample is reasonable, assuming a small difference in the Na concentration that is well within the analytical uncertainties of the reported value. The following conclusions were drawn from the blend studies of Tank 4 and decanted Tank 51-E1: (1) The addition of Tank 4 slurry to a decanted Tank 51-E1 sample significantly improved the degree and time for settling. (2) The addition of Tank 4 slurry to a decanted Tank 51-E1 sample significantly improved the plastic viscosity and yield stress. (3) The SRNL washing test, where nearly all of the wash solution was decanted from the solids, indicates that approximately 96% or more of the total S was removed from the blend in these tests, and the removal of the sulfur tracks closely with that of Na. Insoluble (undissolved) S remaining in the washed sludge was calculated from an estimate of the final slurry liquid fraction, the S result in the slurry digestion, and the S in the final decant (which was very close to the method detection limit). Based on this calculated result, about 4% of the initial total S remained after these washes; this amount is equivalent to about 18% of the initially undissolved S.

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

2009-09-29T23:59:59.000Z

329

Hazard Analysis for In Tank Spray Leaks  

SciTech Connect

The River Protection Project (RPP) Authorization Basis (AB) contains controls that address spray leaks in tanks. However, there are no hazardous conditions in the Hazards Database that specifically identify in-tank spray leak scenarios. The purpose of this Hazards Evaluation is to develop hazardous conditions related to in-tank spray leaks for the Hazards Database and to provide more complete coverage of Tank Farm facilities. Currently, the in-tank spray leak is part of the ''Spray Leak in Structures or From Waste Transfer Lines'' accidents in Section 3.4.2.9 of the Final Safety Analysis Report (FSAR) (CHG, 2000a). The accident analysis for the ''Spray Leak in Structure or From Waste Transfer Lines'' states the following regarding the location of a possible spray leak: Inside ventilated waste storage tanks (DSTs, DCRTs, and some SSTs). Aerosols could be generated inside a storage tank during a transfer because of a leak from the portion of the transfer pipe inside the tank. The tank ventilation system could help disperse the aerosols to the atmosphere should the vent system HEPA filters fail. This Hazards Evaluation also evaluates the controls currently assigned to the spray leak in structure accident and determines the applicability of the controls to the new hazardous conditions. This comparison reviews both the analysis in the FSAR and the controls found in the Technical Safety Requirements (TSRs) (CHG, 2000h). If the new hazardous conditions do not match the analyzed accident conditions and controls, then additional analysis may be required. This document is not intended to authorize the activity or determine the adequacy of controls; it is only intended to provide information about the hazardous conditions associated with this activity. The Control decision process as defined in the AB will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis.

GRAMS, W.H.

2000-06-13T23:59:59.000Z

330

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

Science Conference Proceedings (OSTI)

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

Hay, M; Daniel McCabe, D

2008-05-16T23:59:59.000Z

331

Vehicle Tank & Loading Rack Meters - 2013-04-22  

Science Conference Proceedings (OSTI)

Vehicle Tank & Loading Rack Meters. Purpose: ... Participants should bring a calculator to the training. Materials & Supplies: ...

2013-06-03T23:59:59.000Z

332

Enclosure 1 Additional Information on Hanford Tank Wastes  

E-Print Network (OSTI)

Enclosure 1 Additional Information on Hanford Tank Wastes Introduction The U. S. Nuclear Regulatory of Energy to the U. S. Environmental Protection Agency addressing the Hanford Tank and K Basin Wastes (CBFO stored in two tanks (designated as tanks 241-AW-103 and 241-AW-105) at the Hanford Site are not high

333

Tank characterization report for single-shell tank 241-C-109  

SciTech Connect

This document provides the characterization information and interprets the data for Single-Shell Tank 241-C-109. Single-Shell Tank 241-C-109 is an underground storage tank containing high-level radioactive waste. It is located in the C Tank Farm in the Hanford Site`s 200 East Area. The tank was sampled in September of 1992 to address the Ferrocyanide Unreviewed Safety Question. Analyses of tank waste were also performed to support Hanford Federal Facility Agreement and Consent Order Milestone M-44-08. Tank 241-C-109 went into service in 1946 and received first-cycle decontamination waste from bismuth phosphate process operations at B Plant in 1948. Other waste types added that are expected to contribute to the current contents include ferrocyanide scavenging waste and Strontium Semiworks waste. It is the last tank in a cascade with Tanks 241-C-107 and 241-C-108. The tank has a capacity of 2,010 kL (530 kgal) and currently contains 250 kL (66 kgal) of waste, existing primarily of sludge. Approximately 9.15 kL (4 kgal) of supernate remain. The sludge is heterogeneous, with significantly different chemical compositions depending on waste depth. The major waste constituents include aluminum, calcium, iron, nickel, nitrate, nitrite, phosphate, sodium, sulfate and uranium. The major radionuclides present are Cesium 137 and Strontium 90. The results of this characterization indicate that the waste in this tank is adequately described in the Dangerous Waste Permit Application of the Single-Shell Tank System.

DiCenso, A.T.; Amato, L.C.; Lambie, R.W.; Franklin, J.D.; Seymour, B.J.; Johnson, K.W.; Stevens, R.H. [Los Alamos Technical Associates, Inc., Kennewick, WA (United States); Remund, K.M. [Pacific Northwest Lab., Richland, WA (United States); Sasaki, L.M.; Simpson, B.C. [Westinghouse Hanford Co., Richland, WA (United States)

1995-02-01T23:59:59.000Z

334

TANK 21 AND TANK 24 BLEND AND FEED STUDY: BLENDING TIMES, SETTLING TIMES, AND TRANSFERS  

Science Conference Proceedings (OSTI)

The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where salt solutions of up to 1.2 million gallons will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. In particular, Tanks 21 and 24 are planned to be used for blending and transferring to the SDI feed tank. These tanks were evaluated here to determine blending times, to determine a range of settling times for disturbed sludge, and to determine that the SWPF Waste Acceptance Criteria that less than 1200 mg/liter of solids will be entrained in salt solutions during transfers from the Tank 21 and Tank 24 will be met. Overall conclusions for Tank 21 and Tank 24 operations include: (1) Experimental correction factors were applied to CFD (computational fluid dynamics) models to establish blending times between approximately two and five hours. As shown in Phase 2 research, blending times may be as much as ten times greater, or more, if lighter fluids are added to heavier fluids (i.e., water added to salt solution). As the densities of two salt solutions converge this effect may be minimized, but additional confirmatory research was not performed. (2) At the current sludge levels and the presently planned operating heights of the transfer pumps, solids entrainment will be less than 1200 mg/liter, assuming a conservative, slow settling sludge simulant. (3) Based on theoretical calculations, particles in the density range of 2.5 to 5.0 g/mL must be greater than 2-4 {micro}m in diameter to ensure they settle adequately in 30-60 days to meet the SWPF feed criterion ( 60 days) settling times in Tank 21.

Lee, S.; Leishear, R.; Poirier, M.

2012-05-31T23:59:59.000Z

335

Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Promulgation of Promulgation of Renewable Fuel Storage Tank Regulations to someone by E-mail Share Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Facebook Tweet about Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Twitter Bookmark Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Google Bookmark Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Delicious Rank Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Digg Find More places to share Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on AddThis.com... More in this section... Federal

336

Means and method for vapor generation  

DOE Patents (OSTI)

A liquid, in heat transfer contact with a surface heated to a temperature well above the vaporization temperature of the liquid, will undergo a multiphase (liquid-vapor) transformation from 0% vapor to 100% vapor. During this transition, the temperature driving force or heat flux and the coefficients of heat transfer across the fluid-solid interface, and the vapor percentage influence the type of heating of the fluid--starting as "feedwater" heating where no vapors are present, progressing to "nucleate" heating where vaporization begins and some vapors are present, and concluding with "film" heating where only vapors are present. Unstable heating between nucleate and film heating can occur, accompanied by possibly large and rapid temperature shifts in the structures. This invention provides for injecting into the region of potential unstable heating and proximate the heated surface superheated vapors in sufficient quantities operable to rapidly increase the vapor percentage of the multiphase mixture by perhaps 10-30% and thereby effectively shift the multiphase mixture beyond the unstable heating region and up to the stable film heating region.

Carlson, Larry W. (Oswego, IL)

1984-01-01T23:59:59.000Z

337

Alternative Fuels Data Center: Filling CNG Fuel Tanks  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Filling CNG Fuel Tanks Filling CNG Fuel Tanks to someone by E-mail Share Alternative Fuels Data Center: Filling CNG Fuel Tanks on Facebook Tweet about Alternative Fuels Data Center: Filling CNG Fuel Tanks on Twitter Bookmark Alternative Fuels Data Center: Filling CNG Fuel Tanks on Google Bookmark Alternative Fuels Data Center: Filling CNG Fuel Tanks on Delicious Rank Alternative Fuels Data Center: Filling CNG Fuel Tanks on Digg Find More places to share Alternative Fuels Data Center: Filling CNG Fuel Tanks on AddThis.com... More in this section... Natural Gas Basics Benefits & Considerations Stations Vehicles Availability Conversions Emissions Maintenance & Safety Fuel System & Cylinders Fuel Safety Traffic Accident Filling CNG Tanks Laws & Incentives Filling CNG Fuel Tanks Unlike liquid fuel, which consistently holds about the same volume of fuel

338

Tank characterization report for single-shell tank 241-BY-110  

Science Conference Proceedings (OSTI)

This characterization report summarizes information on the historical uses, current status, and sampling and analysis results of waste stored in tank 241-BY-110.

Schreiber, R.D.

1996-09-16T23:59:59.000Z

339

EM Tank Waste Subcommittee Report for SRS and Hanford Tank Waste...  

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

incorporating chemistry. Such tools would allow the facile evaluation of the impacts of treatment and waste form alternatives on the overall disposition path for Hanford tank...

340

TANKS 18 AND 19-F EQUIPMENT GROUT FILL MATERIAL EVALUATION AND RECOMMENDATIONS  

SciTech Connect

The United States Department of Energy (US DOE) intends to remove Tanks 18-F and 19-F at the Savannah River Site (SRS) from service. The high-level waste (HLW) tanks have been isolated from the F-area Tank Farm (FTF) facilities and will be filled with cementitious grout for the purpose of: (1) physically stabilizing the empty volumes in the tanks, (2) limiting/eliminating vertical pathways from the surface to residual waste on the bottom of the tanks, (3) providing an intruder barrier, and (4) providing an alkaline, chemical reducing environment within the closure boundary to limit solubility of residual radionuclides. Bulk waste and heel waste removal equipment will remain in Tanks 18-F and 19-F when the tanks are closed. This equipment includes: mixer pumps, transfer pumps, transfer jets, equipment support masts, sampling masts and dip tube assemblies. The current Tank 18-F and 19-F closure strategy is to grout the internal void spaces in this equipment to eliminate fast vertical pathways and slow water infiltration to the residual material on the tank floor. This report documents the results of laboratory testing performed to identify a grout formulation for filling the abandoned equipment in Tanks 18-F and 19-F. The objective of this work was to formulate a flowable grout for filling internal voids of equipment that will remain in Tanks 18-F and 19-F during the final closures. This work was requested by V. A. Chander, Tank Farm Closure Engineering, in HLW-TTR-2011-008. The scope for this task is provided in the Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2011-00587. The specific objectives of this task were to: (1) Prepare and evaluate the SRR cooling coil grout identified in WSRC-STI-2008-00298 per the TTR for this work. The cooling coil grout is a mixture of BASF MasterFlow{reg_sign} 816 cable grout (67.67 wt. %), Grade 100 ground granulated blast furnace slag (7.52 wt. %) and water (24.81 wt. %); (2) Identify equipment grout placement and performance properties; (3) Design up to 2 additional grout systems for filling the Tank 18-F and Tank 19-F equipment; (4) Prepare samples of candidate grouts and measure fresh properties, thermal properties and cured properties; (5) Recommend a grout for the Tier 1A equipment fill mock up - ADMP 4 foot high mock up, 1 inch and 2 inch pipes; (6) Support procurement of materials for the Tier 1A equipment fill mock up test; (7) Prepare samples of the recommended grout for hydraulic property measurements which can be used for comparison to values used in the F- Tank Farm Performance Assessment (PA); and (8) Document equipment fill grout data and recommendations in a report.

Stefanko, D.; Langton, C.

2011-12-15T23:59:59.000Z

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


341

Ship Towing Tank | Open Energy Information  

Open Energy Info (EERE)

Towing Tank Towing Tank Jump to: navigation, search Basic Specifications Facility Name Ship Towing Tank Overseeing Organization University of Iowa Hydrodynamic Testing Facility Type Tow Tank Length(m) 100.0 Beam(m) 3.0 Depth(m) 3.0 Cost(per day) Contact POC Special Physical Features Towed 3DPIV; contactless motion tracking; free surface measurement mapping Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 3 Length of Effective Tow(m) 75.0 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.2 Maximum Wave Height(m) at Wave Period(s) 2.0 Maximum Wave Length(m) 6 Wave Period Range(s) 0.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Fully programmable using LabView for regular or irregular waves

342

Ohmsett Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Ohmsett Tow Tank Ohmsett Tow Tank Jump to: navigation, search Basic Specifications Facility Name Ohmsett Tow Tank Overseeing Organization Ohmsett Hydrodynamic Testing Facility Type Tow Tank Length(m) 203.0 Beam(m) 19.8 Depth(m) 2.4 Water Type Freshwater Cost(per day) Contact POC Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 3.4 Length of Effective Tow(m) 155.0 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.9 Maximum Wave Height(m) at Wave Period(s) 4.1 Maximum Wave Length(m) 18 Wave Period Range(s) 4.1 Current Velocity Range(m/s) 3.4 Programmable Wavemaking Yes Wavemaking Description Programmable frequency Wave Direction Uni-Directional Simulated Beach Yes Description of Beach Wave dampening at downstream end Channel/Tunnel/Flume

343

MHL Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Tow Tank Tow Tank Jump to: navigation, search Basic Specifications Facility Name MHL Tow Tank Overseeing Organization University of Michigan Hydrodynamics Hydrodynamic Testing Facility Type Tow Tank Length(m) 109.7 Beam(m) 6.7 Depth(m) 3.7 Cost(per day) $2000 (+ Labor/Materials) Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 6.7 Length of Effective Tow(m) 103.6 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.5 Wave Period Range(s) 0.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Regular and irregular wave spectrum Wave Direction Uni-Directional Simulated Beach Yes Description of Beach Concrete beach Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None

344

Small Towing Tank | Open Energy Information  

Open Energy Info (EERE)

Towing Tank Towing Tank Jump to: navigation, search Basic Specifications Facility Name Small Towing Tank Overseeing Organization University of Iowa Hydrodynamic Testing Facility Type Tow Tank Length(m) 3.7 Beam(m) 0.6 Depth(m) 0.8 Cost(per day) Contact POC Special Physical Features Flows up to 5 gallons per minute Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 0.03 Length of Effective Tow(m) 3.0 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Cameras None Available Sensors Acoustics, Thermal, Turbulence, Velocity Data Generation Capability Real-Time Yes Test Services Test Services Yes On-Site fabrication capability/equipment Machine shop, carpenter shop, welding shop, instrumentation and electronics shop

345

Maine Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Tow Tank Tow Tank Jump to: navigation, search Basic Specifications Facility Name Maine Tow Tank Overseeing Organization University of Maine Hydrodynamics Hydrodynamic Testing Facility Type Tow Tank Length(m) 30.5 Beam(m) 2.4 Depth(m) 1.2 Cost(per day) Contact POC Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 3 Length of Effective Tow(m) 27.4 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.0 Wave Period Range(s) 0.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wave Direction Uni-Directional Simulated Beach Yes Description of Beach Simulated beach is framed with PVC/mesh. Has a 4:9 slope. Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition

346

Lakefront Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Lakefront Tow Tank Lakefront Tow Tank Jump to: navigation, search Basic Specifications Facility Name Lakefront Tow Tank Overseeing Organization University of New Orleans Hydrodynamic Testing Facility Type Tow Tank Length(m) 36.6 Beam(m) 4.9 Depth(m) 1.8 Cost(per day) $1200 Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 2.7 Length of Effective Tow(m) 25.9 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.5 Maximum Wave Length(m) 22 Wave Period Range(s) 0.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Regular random and transient waves Spectra include ISSC, JONSWAP, Bretschneider, Pierson-Moskowitz and custom user-defined. Wave Direction Uni-Directional Simulated Beach Yes Description of Beach Aluminum segmented arch

347

Davidson Laboratory Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Laboratory Tow Tank Laboratory Tow Tank Jump to: navigation, search Basic Specifications Facility Name Davidson Laboratory Tow Tank Overseeing Organization Stevens Institute of Technology Hydrodynamic Testing Facility Type Tow Tank Length(m) 97.5 Beam(m) 4.9 Depth(m) 2.0 Water Type Freshwater Cost(per day) Contact POC Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 18.3 Length of Effective Tow(m) 30.5 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.5 Maximum Wave Height(m) at Wave Period(s) 4.0 Maximum Wave Length(m) 15.2 Wave Period Range(s) 4.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Menu driven selection of standard spectra or user specified Wave Direction Uni-Directional Simulated Beach Yes

348

Ice Towing Tank | Open Energy Information  

Open Energy Info (EERE)

Ice Towing Tank Ice Towing Tank Jump to: navigation, search Basic Specifications Facility Name Ice Towing Tank Overseeing Organization University of Iowa Hydrodynamic Testing Facility Type Tow Tank Length(m) 21.2 Beam(m) 5.0 Depth(m) 1.3 Cost(per day) Contact POC Special Physical Features Specialized for cold regions research, room temperature can be decreased to -10°F Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 0.5 Length of Effective Tow(m) 15.0 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Cameras Yes Description of Camera Types Underwater Available Sensors Acoustics, Thermal, Turbulence, Velocity Data Generation Capability

349

Underground Storage Tank Management (District of Columbia)  

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

The installation, upgrade and operation of any petroleum UST (>110 gallons) or hazardous substance UST System, including heating oil tanks over 1,100 gallons capacity in the District requires a...

350

Analyses and characterization of double shell tank  

Science Conference Proceedings (OSTI)

Evaporator candidate feed from tank 241-AP-108 (108-AP) was sampled under prescribed protocol. Physical, inorganic, and radiochemical analyses were performed on tank 108-AP. Characterization of evaporator feed tank waste is needed primarily for an evaluation of its suitability to be safely processed through the evaporator. Such analyses should provide sufficient information regarding the waste composition to confidently determine whether constituent concentrations are within not only safe operating limits, but should also be relevant to functional limits for operation of the evaporator. Characterization of tank constituent concentrations should provide data which enable a prediction of where the types and amounts of environmentally hazardous waste are likely to occur in the evaporator product streams.

Not Available

1994-10-04T23:59:59.000Z

351

Cryogenic Fuel Tank Draining Analysis Model  

E-Print Network (OSTI)

One of the technological challenges in designing advanced hypersonic aircraft and the next generation of spacecraft is developing reusable flight-weight cryogenic fuel tanks. As an aid in the design and analysis of these cryogenic tanks, a computational fluid dynamics (CFD) model has been developed specifically for the analysis of flow in a cryogenic fuel tank. This model employs the full set of Navier-Stokes equations, except that viscous dissipation is neglected in the energy equation. An explicit finite difference technique in two-dimensional generalized coordinates, approximated to second-order accuracy in both space and time is used. The stiffness resulting from the low Mach number is resolved by using artificial compressibility. The model simulates the transient, two-dimensional draining of a fuel tank cross section. To calculate the slosh wave dynamics the interface between the ullage gas and liquid fuel is modeled as a free surface. Then, experimental data for free convection i...

Donald Greer Research; Donald Greer

1999-01-01T23:59:59.000Z

352

Alden Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Tow Tank Tow Tank Jump to: navigation, search Basic Specifications Facility Name Alden Tow Tank Overseeing Organization Alden Research Laboratory, Inc Hydrodynamic Testing Facility Type Tow Tank Length(m) 30.5 Beam(m) 1.2 Depth(m) 1.2 Water Type Freshwater Cost(per day) Depends on study Towing Capabilities Towing Capabilities Yes Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities Yes Wind Velocity Range(m/s) Designed as needed for study objectives Other Characteristics Point measurement capability Control and Data Acquisition Description Differential pressure transducers, acoustic profiling, propeller meters, load cells, computer data acquisition systems. Number of channels Designed as needed

353

Overview of Integrated Waste Treatment Unit  

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

Integrated Waste Treatment Unit Overview Integrated Waste Treatment Unit Overview Overview for the DOE High Level Waste Corporate Board March 5, 2009 safety  performance  cleanup  closure M E Environmental Management Environmental Management 2 2 Integrated Waste Treatment Unit Mission * Mission - Project mission is to provide treatment of approximately 900,000 gallons of tank farm waste - referred to as sodium bearing waste (SBW) - stored at the Idaho Tank Farm Facility to a stable waste form suitable for disposition at the Waste Isolation Pilot Plant (WIPP). - Per the Idaho Cleanup Project contract, the resident Integrated Waste Treatment Unit (IWTU) facility, shall have the capability for future packaging and shipping of the existing high level waste (HLW) calcine to the geologic

354

RECENT PROGRESS IN DOE WASTE TANK CLOSURE  

SciTech Connect

The USDOE complex currently has over 330 underground storage tanks that have been used to process and store radioactive waste generated from the production of weapons materials. These tanks contain over 380 million liters of high-level and low-level radioactive waste. The waste consists of radioactively contaminated sludge, supernate, salt cake or calcine. Most of the waste exists at four USDOE locations, the Hanford Site, the Savannah River Site, the Idaho Nuclear Technology and Engineering Center and the West Valley Demonstration Project. A summary of the DOE tank closure activities was first issued in 2001. Since then, regulatory changes have taken place that affect some of the sites and considerable progress has been made in closing tanks. This paper presents an overview of the current regulatory changes and drivers and a summary of the progress in tank closures at the various sites over the intervening six years. A number of areas are addressed including closure strategies, characterization of bulk waste and residual heel material, waste removal technologies for bulk waste, heel residuals and annuli, tank fill materials, closure system modeling and performance assessment programs, lessons learned, and external reviews.

Langton, C

2008-02-01T23:59:59.000Z

355

Analysis of ICPP tank farm infiltration  

SciTech Connect

This report addresses water seeping into underground vaults which contain high-level liquid waste (HLLW) storage tanks at the Idaho Chemical Processing Plant (ICPP). Each of the vaults contains from one to three sumps. The original purpose of the sumps was to serve as a backup leak detection system for release of HLLW from the storage tanks. However, water seeps into most of the vaults, filling the sumps, and defeating their purpose as a leak detection system. Leak detection for the HLLW storage tanks is based on measuring the level of liquid inside the tank. The source of water leaking into the vaults was raised as a concern by the State of Idaho INEL Oversight Group because this source could also be leaching contaminants released to soil in the vicinity of the tank farm and transporting contaminants to the aquifer. This report evaluates information concerning patterns of seepage into vault sumps, the chemistry of water in sumps, and water balances for the tank farm to determine the sources of water seeping into the vaults.

Richards, B.T.

1993-10-01T23:59:59.000Z

356

Underground storage tank management plan  

Science Conference Proceedings (OSTI)

The Underground Storage Tank (UST) Management Program at the Oak Ridge Y-12 Plant was established to locate UST systems in operation at the facility, to ensure that all operating UST systems are free of leaks, and to establish a program for the removal of unnecessary UST systems and upgrade of UST systems that continue to be needed. The program implements an integrated approach to the management of UST systems, with each system evaluated against the same requirements and regulations. A common approach is employed, in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance, when corrective action is mandated. This Management Plan outlines the compliance issues that must be addressed by the UST Management Program, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Management Plan provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. (There are no underground radioactive waste UST systems located at Y-12.) The plan is divided into four major sections: (1) regulatory requirements, (2) implementation requirements, (3) Y-12 Plant UST Program inventory sites, and (4) UST waste management practices. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Management Program, and the procedures and guidance used for compliance with applicable regulations.

NONE

1994-09-01T23:59:59.000Z

357

ANALYSIS OF SAMPLES FROM TANK 6F CHEMICAL CLEANING  

SciTech Connect

Savannah River Remediation (SRR) is preparing Tank 6F for closure. The first step in preparing the tank for closure is mechanical sludge removal. In mechanical sludge removal, personnel add liquid (e.g., inhibited water or supernate salt solution) to the tank to form a slurry. They mix the liquid and sludge with pumps, and transfer the slurry to another tank for further processing. Mechanical sludge removal effectively removes the bulk of the sludge from a tank, but is not able to remove all of the sludge. In Tank 6F, SRR estimated a sludge heel of 5,984 gallons remained after mechanical sludge removal. To remove this sludge heel, SRR performed chemical cleaning. The chemical cleaning included two oxalic acid strikes, a spray wash, and a water wash. SRR conducted the first oxalic acid strike as follows. Personnel added 110,830 gallons of 8 wt % oxalic acid to Tank 6F and mixed the contents of Tank 6F with two submersible mixer pumps (SMPs) for approximately four days. Following the mixing, they transferred 115,903 gallons of Tank 6F material to Tank 7F. The SMPs were operating when the transfer started and were shut down approximately five hours after the transfer started. SRR collected a sample of the liquid from Tank 6F and submitted it to SRNL for analysis. Mapping of the tank following the transfer indicated that 2,400 gallons of solids remained in the tank. SRR conducted the second oxalic acid strike as follows. Personnel added 28,881 gallons of 8 wt % oxalic acid to Tank 6F. Following the acid addition, they visually inspected the tank and transferred 32,247 gallons of Tank 6F material to Tank 7F. SRR collected a sample of the liquid from Tank 6F and submitted it to SRNL for analysis. Mapping of the tank following the transfer indicated that 3,248 gallons of solids remained in the tank. Following the oxalic acid strikes, SRR performed Spray Washing with oxalic acid to remove waste collected on internal structures, cooling coils, tank top internals, and tank walls. The Acid Spray Wash was followed by a Water Spray Wash to remove oxalic acid from the tank internals. SRR conducted the Spray Wash as follows. Personnel added 4,802 gallons of 8 wt % oxalic acid to Tank 6F through the spray mast installed in Riser 2, added 4,875 gallons of oxalic acid through Riser 7, added 5,000 gallons of deionized water into the tank via Riser 2, and 5,000 gallons of deionized water into the tank via Riser 7. Following the Spray Wash, they visually inspected the tank and transferred 22,430 gallons of Tank 6F material to Tank 7F. SRR collected a sample of the liquid from Tank 6F and submitted it to SRNL for analysis. Following the Spray Wash and transfer, Savannah River Site (SRS) added 113,935 gallons of well water to Tank 6F. They mixed the tank contents with a single SMP and transferred 112,699 gallons from Tank 6F to Tank 7F. SRR collected a sample of the liquid from Tank 6F and submitted to SRNL for analysis. Mapping of the tank following the transfer indicated that 3,488 gallons of solids remained in the tank. Following the Water Wash, SRR personnel collected a solid sample and submitted it to SRNL for analysis to assess the effectiveness of the chemical cleaning and to provide a preliminary indication of the composition of the material remaining in the tank.

Poirier, M.; Fink, S.

2010-02-02T23:59:59.000Z

358

Tank characterization report for single-shell Tank 241-T-105  

SciTech Connect

Single-Shell Tank 241-T-105, an underground storage tank containing radioactive waste, was most recently sampled in March and May of 1993. Sampling and characterization of the waste in Tank 241-T-105 contribute toward the fulfillment of Milestone M-44-05 of the Hanford Federal Facility Agreement and Consent Order. Tank 241-T-105, located in the 200 West Area T Tank Farm, was constructed in 1944 and went into service in July of 1946 by receiving second cycle decontamination waste from the T Plant. During the service life of the tank, other wastes were added including T Plant first cycle waste, PUREX Plant coating waste, laboratory waste, decontamination waste from T Plant, B Plant low level waste, and B Plant ion exchange waste. The tank currently contains 98,000 gal of non-complexed waste, existing primarily as sludge. Approximately 23,000 gal of drainable interstitial liquid remain. The waste is heterogeneous. Tank 241-T-105 is classified as a non-Watch List tank, with no Unreviewed Safety Questions associated with it at this time. The tank was Interim Stabilized in 1987 and Intrusion Prevention was completed in 1988. The waste in Tank 241-T-105 is comprised of precipitated salts, some of which contain traces of radioactive isotopes. The most prevalent analytes include aluminum, iron, silicon, manganese, sodium, uranium, nitrate, nitrite, and sulfate. The water digested sample results demonstrated that cadmium, chromium, lead, mercury, selenium, and silver concentrations were greater than their Toxicity Characteristic regulatory thresholds. The major radionuclide constituents are {sup 90}Sr and {sup 137}Cs. The waste is 74.1% solids by weight.

DiCenso, A.T.; Amato, L.C.; Franklin, J.D.; Nuttall, G.L.; Johnson, K.W. [Los Alamos Technical Associates, Kennewick, WA (United States); Simpson, B.C. [Westinghouse Hanford Co., Richland, WA (United States)

1994-09-01T23:59:59.000Z

359

Atmospheric Rivers and Flooding over the Central United States  

Science Conference Proceedings (OSTI)

This paper undertakes a hydrometeorological analysis of flood events in the central United States. Vertically integrated horizontal water vapor transport over 19792011 is calculated in the ECMWF Interim Re-Analysis (ERA-Interim) and used in an ...

David A. Lavers; Gabriele Villarini

2013-10-01T23:59:59.000Z

360

ICPP tank farm closure study. Volume 2: Engineering design files  

SciTech Connect

Volume 2 contains the following topical sections: Tank farm heel flushing/pH adjustment; Grouting experiments for immobilization of tank farm heel; Savannah River high level waste tank 20 closure; Tank farm closure information; Clean closure of tank farm; Remediation issues; Remote demolition techniques; Decision concerning EIS for debris treatment facility; CERCLA/RCRA issues; Area of contamination determination; Containment building of debris treatment facility; Double containment issues; Characterization costs; Packaging and disposal options for the waste resulting from the total removal of the tank farm; Take-off calculations for the total removal of soils and structures at the tank farm; Vessel off-gas systems; Jet-grouted polymer and subsurface walls; Exposure calculations for total removal of tank farm; Recommended instrumentation during retrieval operations; High level waste tank concrete encasement evaluation; Recommended heavy equipment and sizing equipment for total removal activities; Tank buoyancy constraints; Grout and concrete formulas for tank heel solidification; Tank heel pH requirements; Tank cooling water; Evaluation of conservatism of vehicle loading on vaults; Typical vault dimensions and approximately tank and vault void volumes; Radiological concerns for temporary vessel off-gas system; Flushing calculations for tank heels; Grout lift depth analysis; Decontamination solution for waste transfer piping; Grout lift determination for filling tank and vault voids; sprung structure vendor data; Grout flow properties through a 2--4 inch pipe; Tank farm load limitations; NRC low level waste grout; Project data sheet calculations; Dose rates for tank farm closure tasks; Exposure and shielding calculations for grout lines; TFF radionuclide release rates; Documentation of the clean closure of a system with listed waste discharge; and Documentation of the ORNL method of radionuclide concentrations in tanks.

NONE

1998-02-01T23:59:59.000Z

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


361

High-expansion foam for LNG vapor mitigation. Topical report, September 1987-December 1989  

SciTech Connect

One of the purposes of these high expansion foam systems is to reduce the extent of the hazardous vapor cloud generated during an accidental LNG release. Should the LNG ignite, these systems serve the additional function of controlling the LNG fire and minimizing its radiation to the surroundings. Foam generators have been installed along the tops of dike walls surrounding some LNG storage tanks, and around other fenced containment areas where LNG may be accidentally released, such as LNG pump pits and pipe rack trenches. To date there are no technically justifiable guidelines for the design and installation of these systems. Furthermore, there are no models that may be used describe the vapor source so as to be able to predict the reduction in the hazardous vapor cloud zone when high expansion foam is applied to an LNG spill. Information is essential not only for the optimal design of high expansion foam systems, but also for comparing the cost effectiveness of alternative LNG vapor mitigation measures.

Atallah, S.; Shah, J.N.; Peterlinz, M.E.

1990-05-01T23:59:59.000Z

362

Tank characterization report for single-shell tank 241-S-104  

SciTech Connect

In July and August 1992, Single-Shell Tank 241-S-104 was sampled as part of the overall characterization effort directed by the Hanford Federal Facility Agreement and Consent Order. Sampling was also performed to determine proper handling of the waste, to address corrosivity and compatibility issues, and to comply with requirements of the Washington Administrative Code. This Tank Characterization Report presents an overview of that tank sampling and analysis effort, and contains observations regarding waste characteristics. It also presents expected concentration and bulk inventory data for the waste contents based on this latest sampling data and background historical and surveillance tank information. Finally, this report makes recommendations and conclusions regarding operational safety. The purpose of this report is to describe the characteristics the waste in Single-Shell Tank 241-S-104 (hereafter, Tank 241-S-104) based on information obtained from a variety of sources. This report summarizes the available information regarding the chemical and physical properties of the waste in Tank 241-S-104, and using the historical information to place the analytical data in context, arranges this information in a format useful for making management and technical decisions concerning waste tank safety and disposal issues. In addition, conclusions and recommendations are presented based on safety issues and further characterization needs.

DiCenso, A.T.; Simpson, B.C.

1994-09-29T23:59:59.000Z

363

Stress evaluation of the primary tank of a double-shell underground storage tank facility  

SciTech Connect

A facility called the Multi-Function Waste Tank Facility (MWTF) is being designed at the Department of Energy`s Hanford site. The MWTF is expected to be completed in 1998 and will consist of six underground double-shell waste storage tanks and associated systems. These tanks will provide safe and environmentally acceptable storage capacity to handle waste generated during single-shell and double-shell tank safety mitigation and remediation activities. This paper summarizes the analysis and qualification of the primary tank structure of the MWTF, as performed by ICF Kaiser Hanford during the latter phase of Title 1 (Preliminary) design. Both computer finite element analysis (FEA) and hand calculations methods based on the so-called Tank Seismic Experts Panel (TSEP) Guidelines were used to perform the analysis and evaluation. Based on the evaluations summarized in this paper, it is concluded that the primary tank structure of the MWTF satisfies the project design requirements. In addition, the hand calculations performed using the methodologies provided in the TSEP Guidelines demonstrate that, except for slosh height, the capacities exceed the demand. The design accounts for the adverse effect of the excessive slosh height demand, i.e., inadequate freeboard, by increasing the hydrodynamic wall and roof pressures appropriately, and designing the tank for such increased pressures.

Atalay, M.B. [ICF Kaiser Engineers, Inc., Oakland, CA (United States); Stine, M.D. [ICF Kaiser Hanford Co., Richland, WA (United States); Farnworth, S.K. [Westinghouse Hanford Co., Richland, WA (United States)

1994-12-01T23:59:59.000Z

364

Discovery of the First Leaking Double-Shell Tank - Hanford Tank 241-AY-102-14222  

SciTech Connect

A routine video inspection of the annulus space between the primary tank and secondary liner of double-shell tank 241-AY-102 was performed in August 2012. During the inspection, unexpected material was discovered. A subsequent video inspection revealed additional unexpected material on the opposite side of the tank, none of which had been observed during inspections performed in December 2006 and January 2007. A formal leak assessment team was established to review the tank's construction and operating histories, and preparations for sampling and analysis began to determine the material's origin. A new sampling device was required to collect material from locations that were inaccessible to the available sampler. Following its design and fabrication, a mock-up test was performed for the new sampling tool to ensure its functionality and capability of performing the required tasks. Within three months of the discovery of the unexpected material, sampling tools were deployed, material was collected, and analyses were performed. Results indicated that some of the unknown material was indicative of soil, whereas the remainder was consistent with tank waste. This, along with the analyses performed by the leak assessment team on the tank's construction history, lead to the conclusion that the primary tank was leaking into the annulus. Several issues were encountered during the deployment of the samplers into the annulus. As this was the first time samples had been required from the annulus of a double-shell tank, a formal lessons learned was created concerning designing equipment for unique purposes under time constraints.

Harrington, Stephanie J.; Sams, Terry L.

2013-11-06T23:59:59.000Z

365

Results for the DWPF Slurry Mix Evaporator Condensate Tank, Off Gas Condensate Tank, And Recycle Collection Tank Samples  

Science Conference Proceedings (OSTI)

The Defense Waste Processing Facility, DWPF, currently generates approximately 1.4 million gallons of recycle water per year during Sludge-Only operations. DWPF has minimized condensate generation to 1.4 million gallons by not operating the Steam Atomized Scrubbers, SASs, for the melter off gas system. By not operating the SASs, DWPF has reduced the total volume by approximately 800,000 gallons of condensate per year. Currently, the recycle stream is sent to back to the Tank Farm and processed through the 2H Evaporator system. To alleviate the load on the 2H Evaporator system, an acid evaporator design is being considered as an alternate processing and/or concentration method for the DWPF recycle stream. In order to support this alternate processing option, the DWPF has requested that the chemical and radionuclide compositions of the Off Gas Condensate Tank, OGCT, Slurry Mix Evaporator Condensate Tank, SMECT, Recycle Collection Tank, RCT, and the Decontamination Waste Treatment Tank, DWTT, be determined as a part of the process development work for the acid evaporator design. Samples have been retrieved from the OGCT, RCT, and SMECT and have been sent to the Savannah River National Laboratory, SRNL for this characterization. The DWTT samples have been recently shipped to SRNL. The results for the DWTT samples will be issued at later date.

TERRI, FELLINGER

2004-12-21T23:59:59.000Z

366

TANK 21 AND TANK 24 BLEND AND FEED STUDY: BLENDING TIMES, SETTLING TIMES, AND TRANSFERS  

SciTech Connect

The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where salt solutions of up to 1.2 million gallons will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. In particular, Tanks 21 and 24 are planned to be used for blending and transferring to the SDI feed tank. These tanks were evaluated here to determine blending times, to determine a range of settling times for disturbed sludge, and to determine that the SWPF Waste Acceptance Criteria that less than 1200 mg/liter of solids will be entrained in salt solutions during transfers from the Tank 21 and Tank 24 will be met. Overall conclusions for Tank 21 and Tank 24 operations include: (1) Experimental correction factors were applied to CFD (computational fluid dynamics) models to establish blending times between approximately two and five hours. As shown in Phase 2 research, blending times may be as much as ten times greater, or more, if lighter fluids are added to heavier fluids (i.e., water added to salt solution). As the densities of two salt solutions converge this effect may be minimized, but additional confirmatory research was not performed. (2) At the current sludge levels and the presently planned operating heights of the transfer pumps, solids entrainment will be less than 1200 mg/liter, assuming a conservative, slow settling sludge simulant. (3) Based on theoretical calculations, particles in the density range of 2.5 to 5.0 g/mL must be greater than 2-4 {micro}m in diameter to ensure they settle adequately in 30-60 days to meet the SWPF feed criterion (<1200 mg/l). (4) Experimental tests with sludge batch 6 simulant and field turbidity data from a recent Tank 21 mixing evolution suggest the solid particles have higher density and/or larger size than indicated by previous analysis of SRS sludge and sludge simulants. (5) Tank 21 waste characterization, laboratory settling tests, and additional field turbidity measurements during mixing evolutions are recommended to better understand potential risk for extended (> 60 days) settling times in Tank 21.

Lee, S.; Leishear, R.; Poirier, M.

2012-05-31T23:59:59.000Z

367

Microsoft Word - Tank Waste Report 9-30-05.doc  

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

Accelerated Tank Waste Retrieval Accelerated Tank Waste Retrieval Activities at the Hanford Site DOE/IG-0706 October 2005 REPORT ON THE ACCELERATED TANK WASTE RETRIEVAL ACTIVITIES AT THE HANFORD SITE TABLE OF CONTENTS Tank Waste Retrieval Details of Finding 1 Recommendations and Comments 4 Appendices Objective, Scope, and Methodology 6 Prior Reports 7 Management Comments 8 Tank Waste Retrieval Page 1 Details of Finding Tank Waste The Department will not meet Tri-Party Agreement (Agreement) Retrieval Activities milestones for the retrieval of waste from the single-shell tanks located at the C-Tank Farm within schedule and cost. Based on the current C-Tank Farm retrieval schedule and the amount of waste retrieved to date, the Department will not accomplish its

368

Independent Activity Report, Hanford Tank Farms - April 2013 | Department  

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

Tank Farms - April 2013 Tank Farms - April 2013 Independent Activity Report, Hanford Tank Farms - April 2013 April 2013 Operational Awareness at the Hanford Tank Farms [HIAR-HANFORD-2013-04-15] The Office of Health, Safety and Security (HSS) Office of Safety and Emergency Management Evaluations (HS-45) Site Lead conducted an operational awareness visit to the Office of River Protection (ORP) to tour the Hanford Tank Farms, observe video inspection of single shell and double shell tanks, and observe Tank Farm project and staff meetings. Independent Activity Report, Hanford Tank Farms - April 2013 More Documents & Publications Independent Oversight Activity Report, Office of River Protection - May 2013 Independent Oversight Activity Report, Hanford Tank Farms - June 2013 Independent Activity Report, Office of River Protection Waste Treatment

369

Savings Project: Insulate Your Water Heater Tank | Department of Energy  

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

Savings Project: Insulate Your Water Heater Tank Savings Project: Insulate Your Water Heater Tank Savings Project: Insulate Your Water Heater Tank Addthis Project Level medium Energy Savings $20-$45 annually Time to Complete 1.5 hours Overall Cost $30 Insulate your hot water tank to save energy and money. | Photo courtesy of iStockphoto.com/glennebo Insulate your hot water tank to save energy and money. | Photo courtesy of iStockphoto.com/glennebo Just like insulating your walls or roof, insulating your hot water tank is an easy and inexpensive way to improve energy efficiency and save you money each month. If your water tank is new, it is likely already insulated. If you have an older hot water tank, check to see if it has insulation with an R-value of at least 24. If not, consider insulating your water tank, which

370

Independent Oversight Review, Hanford Tank Farms - November 2011 |  

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

Review, Hanford Tank Farms - November 2011 Review, Hanford Tank Farms - November 2011 Independent Oversight Review, Hanford Tank Farms - November 2011 November 2011 Review of Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades The U.S. Department of Energy (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted an independent oversight review of the draft amendment to the Hanford Tank Farms safety basis for upgrading the double-shell tank (DST) primary tank ventilation (PTV) systems to safety-significant designation. The Tank Farms are Hazard Category 2 DOE nuclear facilities. The review was performed during the period July 25 - August 12, 2011 by the HSS Office of Enforcement and Oversight's Office of Safety and Emergency Management

371

System for removing liquid waste from a tank  

DOE Patents (OSTI)

A tank especially suited for nuclear applications is disclosed. The tank comprises a tank shell for protectively surrounding the liquid contained therein; an inlet positioned on the tank for passing a liquid into the tank; a sump positioned in an interior portion of the tank for forming a reservoir of the liquid; a sloped incline for resting the tank thereon and for creating a natural flow of the liquid toward the sump; a pump disposed adjacent the tank for pumping the liquid; and a pipe attached to the pump and extending into the sump for passing the liquid therethrough. The pump pumps the liquid in the sump through the pipe and into the pump for discharging the liquid out of the tank.

Meneely, Timothy K. (Penn Hills, PA); Sherbine, Catherine A. (N. Versailles Township, Allegheny County, PA)

1994-01-01T23:59:59.000Z

372

System for removing liquid waste from a tank  

DOE Patents (OSTI)

A tank especially suited for nuclear applications is disclosed. The tank comprises a tank shell for protectively surrounding the liquid contained therein; an inlet positioned on the tank for passing a liquid into the tank; a sump positioned in an interior portion of the tank for forming a reservoir of the liquid; a sloped incline for resting the tank thereon and for creating a natural flow of the liquid toward the sump; a pump disposed adjacent the tank for pumping the liquid; and a pipe attached to the pump and extending into the sump for passing the liquid there through. The pump pumps the liquid in the sump through the pipe and into the pump for discharging the liquid out of the tank. 2 figures.

Meneely, T.K.; Sherbine, C.A.

1994-04-26T23:59:59.000Z

373

Tank characterization report for single-shell tank 241-C-109  

SciTech Connect

One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-C-109. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241 C-109 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices.

Simpson, B.C.

1997-05-23T23:59:59.000Z

374

Tank characterization report for Double-Shell Tank 241-AP-103  

SciTech Connect

This document provides the characterization information and interprets the data for Double-Shell Tank AP-103. The results of the analyses have been compared to the dangerous waste codes in the Washington Dangerous Waste Regulations (WAC 173-303). This assessment was conducted by comparing tank analyses against dangerous waste characteristics (D waste codes) and against state waste codes. It did not include checking tank analyses against U, P, F, or K waste codes since application of these codes is dependent on the source of the waste and not on particular constituent concentrations. The results indicate that the waste in this tank is adequately described in the Dangerous Waste Permit Application for the Double-Shell Tank System.

DeLorenzo, D.S.; DiCenso, A.T.; Amato, L.C.; Franklin, J.D.; Lambie, R.W. [Los Alamos Technical Associates, Inc., Kennewick, WA (United States); Simpson, B.C. [Westinghouse Hanford Co., Richland, WA (United States)

1994-07-01T23:59:59.000Z

375

Coupling apparatus for a metal vapor laser  

DOE Patents (OSTI)

Coupling apparatus for a large bore metal vapor laser is disclosed. The coupling apparatus provides for coupling high voltage pulses (approximately 40 KV) to a metal vapor laser with a high repetition rate (approximately 5 KHz). The coupling apparatus utilizes existing thyratron circuits and provides suitable power input to a large bore metal vapor laser while maintaining satisfactory operating lifetimes for the existing thyratron circuits.

Ball, D.G.; Miller, J.L.

1993-02-23T23:59:59.000Z

376

Legend Units  

Science Conference Proceedings (OSTI)

... Syntax: LEGEND UNIT units> where is an integer number or parameter in the range 1 to 100 that specifies the legend identifier; and ...

2013-11-27T23:59:59.000Z

377

Mercury Vapor (Kooten, 1987) | Open Energy Information  

Open Energy Info (EERE)

Mercury Vapor (Kooten, 1987) Mercury Vapor (Kooten, 1987) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Mercury Vapor (Kooten, 1987) Exploration Activity Details Location Unspecified Exploration Technique Mercury Vapor Activity Date Usefulness useful DOE-funding Unknown Notes Surface soil-mercury surveys are an inexpensive and useful exploration tool for geothermal resources. ---- Surface geochemical surveys for mercury were conducted in 16 areas in 1979-1981 by ARCO Oil and Gas Company as part of its geothermal evaluation program. Three techniques used together have proved satisfactory in evaluating surface mercury data. These are contouring, histograms and cumulative frequency plots of the data. Contouring geochemical data and constructing histograms are standard

378

Thermoplastic Composite with Vapor Grown Carbon Fiber.  

E-Print Network (OSTI)

??Vapor grown carbon fiber (VGCF) is a new class of highly graphitic carbon nanofiber and offers advantages of economy and simpler processing over continuous-fiber composites. (more)

Lee, Jaewoo

2005-01-01T23:59:59.000Z

379

Moisture Durability of Vapor Permeable Insulating Sheathing ...  

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

Existing Homes, Building Technologies Office (BTO) In this project, Building America team Building Science Corporation researched some of the ramifications of using exterior, vapor...

380

Vapor phase modifiers for oxidative coupling  

DOE Patents (OSTI)

Volatilized metal compounds are described which are capable of retarding vapor phase alkane conversion reactions in oxidative coupling processes that convert lower alkanes to higher hydrocarbons.

Warren, B.K.

1991-12-17T23:59:59.000Z

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


381

Water Vapor Fields Deduced from METEOSAT-1 Water Vapor Channel Data  

Science Conference Proceedings (OSTI)

A quasi-operational process for the determination of water vapor fields from METEPSAT-1 water vapor channel data is described. Each count of the WV picture is replaced by the corresponding mean relative humidity value using both the calibration ...

M. M. Poc; M. Roulleau

1983-09-01T23:59:59.000Z

382

Computer modeling of ORNL storage tank sludge mobilization and mixing  

SciTech Connect

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

Terrones, G.; Eyler, L.L.

1993-09-01T23:59:59.000Z

383

Ferrocyanide tank waste stability. Supplement 2  

Science Conference Proceedings (OSTI)

Ferrocyanide wastes were generated at the Hanford Site during the mid to late 1950s as a result of efforts to create more tank space for the storage of high-level nuclear waste. The ferrocyanide process was developed to remove {sup 137}CS from existing waste and newly generated waste that resulted from the recovery of valuable uranium in Hanford Site waste tanks. During the course of research associated with the ferrocyanide process, it was recognized that ferrocyanide materials, when mixed with sodium nitrate and/or sodium nitrite, were capable of violent exothermic reaction. This chemical reactivity became an issue in the 1980s, when safety issues associated with the storage of ferrocyanide wastes in Hanford Site tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety issues associated with these wastes, as well as current research and waste management programs. Testing to provide information on the nature of possible tank reactions is ongoing. This document supplements the information presented in Summary of Single-Shell Tank Waste Stability, WHC-EP-0347, March 1991 (Borsheim and Kirch 1991), which evaluated several issues. This supplement only considers information particular to ferrocyanide wastes.

Fowler, K.D.

1993-01-01T23:59:59.000Z

384

Rethinking the Hanford Tank Waste Program  

Science Conference Proceedings (OSTI)

The program to treat and dispose of the highly radioactive wastes stored in underground tanks at the U.S. Department of Energy's Hanford site has been studied. A strategy/management approach to achieve an acceptable (technically sound) end state for these wastes has been developed in this study. This approach is based on assessment of the actual risks and costs to the public, workers, and the environment associated with the wastes and storage tanks. Close attention should be given to the technical merits of available waste treatment and stabilization methodologies, and application of realistic risk reduction goals and methodologies to establish appropriate tank farm cleanup milestones. Increased research and development to reduce the mass of non-radioactive materials in the tanks requiring sophisticated treatment is highly desirable. The actual cleanup activities and milestones, while maintaining acceptable safety standards, could be more focused on a risk-to-benefit cost effectiveness, as agreed to by the involved stakeholders and in accordance with existing regulatory requirements. If existing safety standards can be maintained at significant cost savings under alternative plans but with a change in the Tri-Party Agreement (a regulatory requirement), those plans should be carried out. The proposed strategy would also take advantage of the lessons learned from the activities and efforts in the first phase of the two-phased cleanup of the Hanford waste tank farms.

Parker, F. L.; Clark, D. E.; Morcos, N.

2002-02-26T23:59:59.000Z

385

An analysis of tank and pump pit flammable gas data in support of saltwater pumping safety basis simplification  

DOE Green Energy (OSTI)

Hanford Site high-level waste tanks are interim stabilized by pumping supernatant and interstitial waste liquids to double-shell tanks (DSTs) through a saltwell pump (SWP). The motor to this SWP is located atop the tank, inside a pump pit. A pumping line extends down from the pump motor into the well area, located in the salt/sludge solids in the tank below. Pumping of these wastes is complicated by the fact that some of the wastes generate and retain potentially hazardous amounts of hydrogen, nitrous oxide, and ammonia. Monitoring of flammable gas concentrations during saltwell pumping activities has shown that one effect of pumping is acceleration in the release of accumulated hydrogen. A second effect is that of a temporarily increased hydrogen concentration in both the dome space and pump pit. There is a safety concern that the hydrogen concentration during saltwell pumping activities might approach the lower flammability limit (LFL) in either the tank dome space or the pump pit. The current Final Safety Analysis Report (FSAR) (CHG 2000) for saltwell pumping requires continuous flammable gas monitoring in both the pump pit and the tank vapor space during saltwell pumping. The FSAR also requires that portable exhauster fans be available by most of the passively ventilated tanks to be saltwell pumped in the event that additional air flow is required to dilute the headspace concentration of flammable gases to acceptable levels. The first objective of this analysis is to review the need for an auxiliary exhauster. Since the purpose of the exhauster is to diffuse unacceptably high flammable gas concentrations, discovery of an alternate method of accomplishing the same task may provide cost savings. The method reviewed is that of temporarily stopping the saltwell pumps. This analysis also examines the typical hydrogen concentration peaks and the rates of increase in hydrogen levels already witnessed in tanks during saltwell pumping activities. The historical data show that these rates and maximum concentrations are so low as to make it unlikely that the LFL concentration would ever be approached. The second objective of this analysis is to review the data provided by two separate flammable gas measurement systems on each tank being saltwell pumped to see if there is an unnecessary redundancy. Eliminating redundant measurement systems would provide cost savings if the quality of data and resultant margin of safety during saltwell pumping activity are not compromised.

MCCAIN, D.J.

2000-07-26T23:59:59.000Z

386

Baseline Design Compliance Matrix for the Type 4 In Situ Vapor Samplers and Supernate and Sludge and Soft Saltcake Grab Sampling  

SciTech Connect

The DOE has identified a need to sample vapor space, exhaust ducts, supernate, sludge, and soft saltcake in waste tanks that store radioactive waste. This document provides the Design Compliance Matrix (DCM) for the Type 4 In-Situ Vapor Sampling (ISVS) system and the Grab Sampling System that are used for completing this type of sampling function. The DCM identifies the design requirements and the source of the requirements for the Type 4 ISVS system and the Grab Sampling system. The DCM is a single-source compilation design requirements for sampling and sampling support equipment and supports the configuration management of these systems.

BOGER, R.M.

2000-09-28T23:59:59.000Z

387

United States Government  

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

w w f.b wr w f k--w .^^- - w w f.b wr w f k--w .^^- - - r - T- - * -* p -ldt - f f - - -J -vv- A n JV DOE F 1325.8 (08-93) United States Government ------- Department of Energy memorandum DATE: June 15, 2006 REPLY TO Audit Report Number: OAS-L-06-15 ATTN OF: IG-32 (A05SR029) SUBJECT Audit of "Storage Capacity of the Iligh Level Waste Tanks at the Savannah River TO: Manager, Savannah River Operations Office INTRODUCTION AND OBJECTIVE The Savannah River Site in South Carolina currently stores about 36 million gallons of waste in 49 active underground storag,* .ks. Twenty-two of these .anks do not meet Environmcntal Protection A&-.y (EPA) requirements ybr full secondary containment and must be emptied and closed by 2022 in accordance with a closure schedule approved by the EPA and the 5oith Carolina Department

388

Technology Maturation Plan (TMP) Wet Air Oxidation (WAO) Technology for Tank 48H Treatment Project (TTP)  

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

Westinghouse Savannah River Company LLC Westinghouse Savannah River Company LLC Savannah River Site Aiken, SC 29808 LWO-SPT-2007-00247 Rev. 1 Technology Maturation Plan (TMP) Wet Air Oxidation (WAO) For Tank 48H Treatment Project (TTP) November, 2007 Technology Maturation Plan (TMP) Wet Air Oxidation (WAO) Technology for Tank 48H Treatment Project (TTP) LWO-SPT-2007-00247 Rev. 1 DISCLAIMER This report was prepared by Washington Savannah River Company (WSRC) for the United States Department of Energy under Contract No. DEA-AC09-96SR18500 and is an account of work performed under that contract. Neither the United States Department of Energy, nor WSRC, nor any of their employees makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or

389

G-Band Vapor Radiometer Precipitable Water Vapor (GVRPWV) Value-Added Product  

SciTech Connect

The G-Band Vapor Radiometer Precipitable Water Vapor (GVRPWV) value-added product (VAP) computes precipitable water vapor using neural network techniques from data measured by the GVR. The GVR reports time-series measurements of brightness temperatures for four channels located at 183.3 1, 3, 7, and 14 GHz.

Koontz, A; Cadeddu, M

2012-12-05T23:59:59.000Z

390

Near real time vapor detection and enhancement using aerosol adsorption  

DOE Patents (OSTI)

A vapor sample detection method where the vapor sample contains vapor and ambient air and surrounding natural background particles. The vapor sample detection method includes the steps of generating a supply of aerosol that have a particular effective median particle size, mixing the aerosol with the vapor sample forming aerosol and adsorbed vapor suspended in an air stream, impacting the suspended aerosol and adsorbed vapor upon a reflecting element, alternatively directing infrared light to the impacted aerosol and adsorbed vapor, detecting and analyzing the alternatively directed infrared light in essentially real time using a spectrometer and a microcomputer and identifying the vapor sample.

Novick, Vincent J.; Johnson, Stanley A.

1997-12-01T23:59:59.000Z

391

Tank Waste System Integrated Project Team  

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

Decisional Draft Decisional Draft 1 This document is intended for planning and analysis purposes, assuming a continuing constrained budget environment. Every effort will be made to comply with all applicable environmental and legal obligations, while also assuring that essential functions necessary to protect human health, the environment and national security are maintained. Tank Waste System Tank Waste System Integrated Project Team Integrated Project Team Steve Schneider Office of Engineering and Technology Tank Waste Corporate Board July 29, 2009 2 This document is intended for planning and analysis purposes, assuming a continuing constrained budget environment. Every effort will be made to comply with all applicable environmental and legal obligations, while also assuring that essential functions necessary

392

Hanford Single-Shell Tank Integrity Program  

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

Operations Contract Hanford Single Hanford Single- -Shell Shell Hanford Single Hanford Single Shell Shell Tank Integrity Tank Integrity Program Program Herbert S Berman Herbert S Berman Herbert S. Berman Herbert S. Berman July 29, 2009 July 29, 2009 1 Page 1 Tank Operations Contract Introduction * The Hanford site's principle historic mission was plutonium production for the manufacture of nuclear weapons. * Between 1944 and 1988, the site operated nine graphite- moderated light-water production reactors to irradiate moderated, light-water, production reactors to irradiate fuel and produce plutonium. * Four large chemical separations plants were run to extract plutonium from the fuel, and a variety of laboratories, support facilities, and related infrastructure to support production

393

MIT Tow Tank | Open Energy Information  

Open Energy Info (EERE)

MIT Tow Tank MIT Tow Tank Overseeing Organization Massachusetts Institute of Technology Hydrodynamics Hydrodynamic Testing Facility Type Tow Tank Length(m) 36.6 Beam(m) 2.4 Depth(m) 1.2 Water Type Saltwater Cost(per day) $750 Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 1.5 Length of Effective Tow(m) 27.4 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.1 Maximum Wave Height(m) at Wave Period(s) 3.0 Maximum Wave Length(m) 4.6 Wave Period Range(s) 3.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Arbitrary spectrum Wave Direction Uni-Directional Simulated Beach No Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition

394

Double Shell Tank (DST) Utilities Specification  

SciTech Connect

This specification establishes the performance requirements and provides the references to the requisite codes and standards to he applied during the design of the Double-Shell Tank (DST) Utilities Subsystems that support the first phase of waste feed delivery (WFD). The DST Utilities Subsystems provide electrical power, raw/potable water, and service/instrument air to the equipment and structures used to transfer low-activity waste (LAW) and high-level waste (HLW) to designated DST staging tanks. The DST Utilities Subsystems also support the equipment and structures used to deliver blended LAW and HLW feed from these staging tanks to the River Protection Project (RPP) Privatization Contractor facility where the waste will be immobilized. This specification is intended to be the basis for new projects/installations. This specification is not intended to retroactively affect previously established project design criteria without specific direction by the program.

SUSIENE, W.T.

2000-04-27T23:59:59.000Z

395

Technology development activities supporting tank waste remediation  

Science Conference Proceedings (OSTI)

This document summarizes work being conducted under the U.S. Department of Energy`s Office of Technology Development (EM-50) in support of the Tank Waste Remediation System (TWRS) Program. The specific work activities are organized by the following categories: safety, characterization, retrieval, barriers, pretreatment, low-level waste, and high-level waste. In most cases, the activities presented here were identified as supporting tank remediation by EM-50 integrated program or integrated demonstration lead staff and the selections were further refined by contractor staff. Data sheets were prepared from DOE-HQ guidance to the field issued in September 1993. Activities were included if a significant portion of the work described provides technology potentially needed by TWRS; consequently, not all parts of each description necessarily support tank remediation.

Bonner, W.F.; Beeman, G.H.

1994-06-01T23:59:59.000Z

396

T-TY Tank Farm Interim Surface Barrier DemonstrationVadose Zone Monitoring Plan  

SciTech Connect

The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank of the 241-T Tank Farm in 1973. Five tanks are assumed to have leaked in the TY Farm. Many of the contaminants from those leaks still reside within the vadose zone within the T and TY Tank Farms. The Department of Energys Office of River Protection seeks to minimize the movement of these contaminant plumes by placing interim barriers on the ground surface. Such barriers are expected to prevent infiltrating water from reaching the plumes and moving them further. The soil water regime is monitored to determine the effectiveness of the interim surface barriers. Soil-water content and water pressure are monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. Four instrument nests were installed in the T Farm in fiscal year (FY) 2006 and FY2007; two nests were installed in the TY Farm in FY2010. Each instrument nest contains a neutron probe access tube, a capacitance probe, and four heat-dissipation units. A meteorological station has been installed at the north side of the fence of the T Farm. This document summarizes the monitoring methods, the instrument calibration and installation, and the vadose zone monitoring plan for interim barriers in T farm and TY Farm.

Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

2010-09-27T23:59:59.000Z

397

Vadose zone characterization project at the Hanford Tank Farms: BY Tank Farm report  

SciTech Connect

The US Department of Energy Grand Junction Office (GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the contamination distributed in the vadoze zone sediment beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information about the vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the BY Tank Farm.

Kos, S.E.

1997-02-01T23:59:59.000Z

398

Assessment of Tank 241-S-112 Liquid Waste Mixing in Tank 241-SY-101  

SciTech Connect

The objectives of this study were to evaluate mixing of liquid waste from Tank 241-S-112 with waste in Tank 241-SY-101 and to determine the properties of the resulting waste for the cross-site transfer to avoid potential double-shell tank corrosion and pipeline plugging. We applied the time-varying, three-dimensional computer code TEMPEST to Tank SY-101 as it received the S-112 liquid waste. The model predicts that temperature variations in Tank SY-101 generate a natural convection flow that is very slow, varying from about 7 x 10{sup -5} to 1 x 10{sup -3} ft/sec (0.3 to about 4 ft/hr) in most areas. Thus, natural convection would eventually mix the liquid waste in SY-101 but would be very slow to achieve nearly complete mixing. These simulations indicate that the mixing of S-112 and SY-101 wastes in Tank SY-101 is a very slow process, and the density difference between the two wastes would further limit mixing. It is expected to take days or weeks to achieve relatively complete mixing in Tank SY-101.

Onishi, Yasuo; Trent, Donald S.; Wells, Beric E.; Mahoney, Lenna A.

2003-10-01T23:59:59.000Z

399

Tank characterization report for single-shell tank 241-SX-106  

SciTech Connect

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-106. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-106 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Documents developed for 1998.''

FIELD, J.G.

1999-02-24T23:59:59.000Z

400

Tank characterization report for single-shell tank 241-U-103  

Science Conference Proceedings (OSTI)

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-U-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-U-103 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with Waste Information Requirements Documents developed for 1998.''

SASAKI, L.M.

1999-02-24T23:59:59.000Z

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


401

" Million Housing Units, Final"  

U.S. Energy Information Administration (EIA) Indexed Site

Water Heating in U.S. Homes, by Housing Unit Type, 2009" Water Heating in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ,"Total U.S.1 (millions)" ,," Detached"," Attached"," 2 to 4 Units","5 or More Units","Mobile Homes" "Water Heating" "Total Homes",113.6,71.8,6.7,9,19.1,6.9 "Number of Storage Tank Water Heaters" 0,2.9,1.8,0.1,0.2,0.6,0.1 1,108.1,67.5,6.5,8.8,18.5,6.8 "2 or More",2.7,2.5,0.1,"Q","Q","Q" "Number of Tankless Water Heaters2" 0,110.4,69.5,6.5,8.9,18.6,6.8 1,3.1,2.2,0.2,0.2,0.5,"Q"

402

Applications of Mechanical Vapor Recompression to Evaporation and Crystallization  

E-Print Network (OSTI)

Over the past 10-15 years, mechanical vapor recompression (MVR) has become the preferred system in many industrial evaporation and crystallization applications, because of its economy and simplicity of operation. In most instances, the need for steam to provide heat for the evaporation and cooling water for condensing the overhead vapors is virtually eliminated; and, at the same time, a wide range of turndown is available. An MVR is generally found to be the most economical choice when there is no boiler plant available or when electrical power is priced competitively in comparison to steam. Vapor recompression is accomplished using centrifugal, axial-flow, or positive displacement compressors and these compressors can be powered by electricity, steam turbine or a gas turbine. The use of an MVR Evaporator/Crystallizer provides a comparatively low cost means of expanding the production capability of an existing evaporation plant either by adding a "stand alone" unit or by reconfiguring a multiple-effect system into several single-effect MVR's.

Outland, J. S.

1995-04-01T23:59:59.000Z

403

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

DOE Green Energy (OSTI)

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

Adu-Wusu, K; Paul Burket, P

2009-03-31T23:59:59.000Z

404

High-Pressure Tube Trailers and Tanks  

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

Berry Berry Salvador M. Aceves Lawrence Livermore National Laboratory (925) 422-0864 saceves@LLNL.GOV DOE Delivery Tech Team Presentation Chicago, Illinois February 8, 2005 Inexpensive delivery of compressed hydrogen with ambient temperature or cryogenic compatible vessels * Pressure vessel research at LLNL Conformable (continuous fiber and replicants) Cryo-compressed * Overview of delivery options * The thermodynamics of compressed and cryo-compressed hydrogen storage * Proposed analysis activities * Conclusions Outline We are investigating two techniques for reduced bending stress: continuous fiber vessels and vessels made of replicants Conformable tanks require internal stiffeners (ribs) to efficiently support the pressure and minimize bending stresses Spherical and cylindrical tanks

405

Alternative Inspection Methods for Single Shell Tanks  

Science Conference Proceedings (OSTI)

This document was prepared to provide evaluations and recommendations regarding nondestructive evaluation methods that might be used to determine cracks and bowing in the ceiling of waste storage tanks on the Hanford site. The goal was to determine cracks as small as 1/16 in. wide in the ceiling, and bowing as small as 0.25 in. This report describes digital video camera methods that can be used to detect a crack in the ceiling of the dome, and methods for determining the surface topography of the ceiling in the waste storage tanks to detect localized movements in the surface. A literature search, combined with laboratory testing, comprised this study.

Peters, Timothy J.; Alzheimer, James M.; Hurley, David E.

2010-01-19T23:59:59.000Z

406

Atomic vapor laser isotope separation  

SciTech Connect

Atomic vapor laser isotope separation (AVLIS) is a general and powerful technique. A major present application to the enrichment of uranium for light-water power reactor fuel has been under development for over 10 years. In June 1985 the Department of Energy announced the selection of AVLIS as the technology to meet the nation's future need for the internationally competitive production of uranium separative work. The economic basis for this decision is considered, with an indicated of the constraints placed on the process figures of merit and the process laser system. We then trace an atom through a generic AVLIS separator and give examples of the physical steps encountered, the models used to describe the process physics, the fundamental parameters involved, and the role of diagnostic laser measurements.

Stern, R.C.; Paisner, J.A.

1985-11-08T23:59:59.000Z

407

Independent Oversight Activity Report, Hanford Tank Farms - June 2013 |  

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

Oversight Activity Report, Hanford Tank Farms - June Oversight Activity Report, Hanford Tank Farms - June 2013 Independent Oversight Activity Report, Hanford Tank Farms - June 2013 June 2013 Office of River Protection Assessment of Contractor Quality Assurance, Operational Awareness at the Hanford Tank Farms [HIAR NNSS-2012-12-03] The Office of Health, Safety and Security (HSS), Office of Safety and Emergency Management Evaluations (Independent Oversight) Site Lead conducted an operational awareness visit to the ORP Hanford Tank Farms, observed a Tank Farms morning meeting, toured the C Tank Farm, and observed a heavy (34,000 pound) lift. Independent Oversight Activity Report, Hanford Tank Farms - June 2013 More Documents & Publications Independent Activity Report, Office of River Protection Waste Treatment

408

Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Publications » Technology Bulletins Publications » Technology Bulletins Printable Version Share this resource Send a link to Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory to someone by E-mail Share Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Facebook Tweet about Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Twitter Bookmark Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Google Bookmark Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Delicious Rank Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Digg Find More places to share Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on AddThis.com... Propane Tank Overfill Safety Advisory

409

High-Level Liquid Waste Tank Integrity Workshop - 2008  

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

Liquid Waste Tank Integrity Liquid Waste Tank Integrity Workshop - 2008 Karthik Subramanian Bruce Wiersma November 2008 High Level Waste Corporate Board Meeting karthik.subramanian@srnl.doe.gov bruce.wiersma@srnl.doe.gov 2 Acknowledgements * Bruce Wiersma (SRNL) * Kayle Boomer (Hanford) * Michael T. Terry (Facilitator) * SRS - Liquid Waste Organization * Hanford Tank Farms * DOE-EM 3 Background * High level radioactive waste (HLW) tanks provide critical interim confinement for waste prior to processing and permanent disposal * Maintaining structural integrity (SI) of the tanks is a critical component of operations 4 Tank Integrity Workshop - 2008 * Discuss the HLW tank integrity technology needs based upon the evolving waste processing and tank closure requirements along with its continued storage mission

410

EIS-0391: Hanford Tank Closure and Waste Management, Richland...  

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

single-shell tanks (SSTs) and 28 double-shell tanks and closure of the SST system, (2) decommissioning of the Fast Flux Test Facility, a nuclear test reactor, and (3) disposal...

411

TANK FARM INTERIM SURFACE BARRIER MATERIALS AND RUNOFF ALTERNATIVES STUDY  

SciTech Connect

This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

HOLM MJ

2009-06-25T23:59:59.000Z

412

Savings Project: Insulate Your Water Heater Tank | Department...  

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

Your Water Heater Tank Addthis Project Level medium Energy Savings 20-45 annually Time to Complete 1.5 hours Overall Cost 30 Insulate your hot water tank to save energy and...

413

Authorization basis status report (miscellaneous TWRS facilities, tanks and components)  

SciTech Connect

This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

Stickney, R.G.

1998-04-29T23:59:59.000Z

414

Tank SY-101 void fraction instrument functional design criteria  

DOE Green Energy (OSTI)

This document presents the functional design criteria for design, analysis, fabrication, testing, and installation of a void fraction instrument for Tank SY-101. This instrument will measure the void fraction in the waste in Tank SY-101 at various elevations.

McWethy, L.M.

1994-10-18T23:59:59.000Z

415

A New Global Water Vapor Dataset  

Science Conference Proceedings (OSTI)

A comprehensive and accurate global water vapor dataset is critical to the adequate understanding of water vapor's role in the earth's climate system. To begin to satisfy this need, the authors have produced a blended dataset made up of global, 5-...

David L. Randel; Thomas J. Greenwald; Thomas H. Vonder Haar; Graeme L. Stephens; Mark A. Ringerud; Cynthia L. Combs

1996-06-01T23:59:59.000Z

416

LNG fire and vapor control system technologies  

SciTech Connect

This report provides a review of fire and vapor control practices used in the liquefied natural gas (LNG) industry. Specific objectives of this effort were to summarize the state-of-the-art of LNG fire and vapor control; define representative LNG facilities and their associated fire and vapor control systems; and develop an approach for a quantitative effectiveness evaluation of LNG fire and vapor control systems. In this report a brief summary of LNG physical properties is given. This is followed by a discussion of basic fire and vapor control design philosophy and detailed reviews of fire and vapor control prac