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Sample records for underground tank leak

  1. Leak detection for underground storage tanks

    International Nuclear Information System (INIS)

    Durgin, P.B.; Young, T.M.

    1993-01-01

    This symposium was held in New Orleans, Louisiana on January 29, 1992. The purpose of this conference was to provide a forum for exchange of state-of-the-art information on leak detection for underground storage tanks that leaked fuel. A widespread concern was protection of groundwater supplies from these leaking tanks. In some cases, the papers report on research that was conducted two or three years ago but has never been adequately directed to the underground storage tank leak-detection audience. In other cases, the papers report on the latest leak-detection research. The symposium was divided into four sessions that were entitled: Internal Monitoring; External Monitoring; Regulations and Standards; and Site and Risk Evaluation. Individual papers have been cataloged separately for inclusion in the appropriate data bases

  2. Leaking Underground Storage Tank Sites in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Leaking Underground Storage Tank (LUST) sites where petroleum contamination has been found. There may be more than one LUST site per UST site.

  3. Underground storage tanks

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Environmental contamination from leaking underground storage tanks poses a significant threat to human health and the environment. An estimated five to six million underground storage tanks containing hazardous substances or petroleum products are in use in the US. Originally placed underground as a fire prevention measure, these tanks have substantially reduced the damages from stored flammable liquids. However, an estimated 400,000 underground tanks are thought to be leaking now, and many more will begin to leak in the near future. Products released from these leaking tanks can threaten groundwater supplies, damage sewer lines and buried cables, poison crops, and lead to fires and explosions. As required by the Hazardous and Solid Waste Amendments (HSWA), the EPA has been developing a comprehensive regulatory program for underground storage tanks. The EPA proposed three sets of regulations pertaining to underground tanks. The first addressed technical requirements for petroleum and hazardous substance tanks, including new tank performance standards, release detection, release reporting and investigation, corrective action, and tank closure. The second proposed regulation addresses financial responsibility requirements for underground petroleum tanks. The third addressed standards for approval of state tank programs

  4. VOLUMETRIC LEAK DETECTION IN LARGE UNDERGROUND STORAGE TANKS - VOLUME I

    Science.gov (United States)

    A set of experiments was conducted to determine whether volumetric leak detection system presently used to test underground storage tanks (USTs) up to 38,000 L (10,000 gal) in capacity could meet EPA's regulatory standards for tank tightness and automatic tank gauging systems whe...

  5. Method of disposing of earth contaminated by leaking underground storage tanks

    International Nuclear Information System (INIS)

    Ruehl, P.A.

    1993-01-01

    A process is described for disposing of earth contaminated with petroleum products from a leaking underground storage tank wherein the earth contains a significant amount of material comprised primarily of a mixture of one part Al 2 O 3 and two to three parts SiO 2 , the process comprising: digging up a leaking underground storage tank and the surrounding contaminated earth; separating the excavated earth into a Al 2 O 3 +SiO 2 material and a non-Al 2 O 3 + SiO 2 material; mixing the Al 2 O 3 + SiO 2 material and other cement precursor raw materials together to form a mixture, and grinding the mixture to form a feed mix; introducing the feed mix into a rotary cement kiln causing any remaining petroleum product contained therein to be volatilized and burned within the kiln as cement clinker is being produced; and grinding the cement clinker together to form cement which is free of petroleum product

  6. Indian Country Leaking Underground Storage Tanks, Region 9, 2016

    Science.gov (United States)

    This GIS dataset contains point features that represent Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. This dataset contains facility name and locational information, status of LUST case, operating status of facility, inspection dates, and links to No Further Action letters for closed LUST cases. This database contains 1230 features, with 289 features having a LUST status of open, closed with no residual contamination, or closed with residual contamination.

  7. Leaking Underground Storage Tank Points, Region 9 Indian Country, 2017, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains point features that represent Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. This dataset contains facility name and...

  8. VOLUMETRIC LEAK DETECTION IN LARGE UNDERGROUND STORAGE TANKS - VOLUME II: APPENDICES A-E

    Science.gov (United States)

    The program of experiments conducted at Griffiss Air Force Base was devised to expand the understanding of large underground storage tank behavior as it impacts the performance of volumetric leak detection testing. The report addresses three important questions about testing the ...

  9. Indian Country Leaking Underground Storage Tank (LUST) Points, Region 9, 2016, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains point features that represent Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. This dataset contains facility name and...

  10. Indian Country Leaking Underground Storage Tanks (LUST) Map Service, Region 9, 2016, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — This map service displays Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. The service is composed of three layers; one for each unique LUST...

  11. Testing underground tanks for leak tightness at LLNL

    International Nuclear Information System (INIS)

    Henry, R.K.; Sites, R.L.; Sledge, M.

    1986-01-01

    Two types of tank systems are present at the Livermore Site: tanks and associated piping for the storage of fuel (forty-three systems), and tanks or sumps and associated piping for the retention of potentially contaminated wastewater (forty systems). The fuel systems were tested using commercially available test methods: Petro-Tite, Hunter Leak Lokator, Ezy-Chek, and Associated Environmental Systems (A.E.S.). In contrast to fuel tank systems, wastewater systems have containers that are predominantly open at the top and not readily testable. Therefore, a project to test and evaluate all available testing methods was initiated and completed. The commercial method Tank Auditor was determined to be appropriate for testing open-top tanks and sumps and this was the method used to test the majority of the open-top containers. Of the 81 tanks tested, 61 were found to be leak tight, 9 were shown to have leaks, and 11 yielded inconclusive results. Two tanks have not yet been tested because of operational constraints; they are sheduled to be tested within the next two months. Schedules are being developed for the retesting of tanks and for remedial actions

  12. Lower Colorado River GRP Leaking Underground Storage Tank Sites (Closed), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  13. Lower Colorado River GRP Leaking Underground Storage Tank Sites (Open), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  14. Location of leaks in pressurized underground pipelines

    International Nuclear Information System (INIS)

    Eckert, E.G.; Maresca, J.W. Jr.

    1993-01-01

    Millions of underground storage tanks (UST) are used to store petroleum and other chemicals. The pressurized underground pipelines associated with USTs containing petroleum motor fuels are typically 2 in. in diameter and 50 to 200 ft in length. These pipelines typically operate at pressures of 20 to 30 psi. Longer lines, with diameters up to 4 in., are found in some high-volume facilities. There are many systems that can be used to detect leaks in pressurized underground pipelines. When a leak is detected, the first step in the remediation process is to find its location. Passive-acoustic measurements, combined with advanced signal-processing techniques, provide a nondestructive method of leak location that is accurate and relatively simple, and that can be applied to a wide variety of pipelines and pipeline products

  15. Leaking Underground Tanks in Rhode Island; LUSTs12

    Data.gov (United States)

    University of Rhode Island Geospatial Extension Program — This dataset shows the location of storage tanks and associated piping used for petroleum and certain hazardous substances that have experienced leaks as determined...

  16. Environmental Protection: Improved Inspections and Enforcement Would Ensure Safer Underground Storage Tanks

    National Research Council Canada - National Science Library

    Stephenson, John

    2001-01-01

    ...) Underground Storage Tank (UST) program. 1 The program is relevant to today's hearing because studies have shown that tanks that leak hazardous substances, such as methyl tertiary butyl ether (MTBE...

  17. Underground storage tanks containing hazardous chemicals

    International Nuclear Information System (INIS)

    Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.; Hillger, R.W.; Tafuri, A.N.

    1991-01-01

    The regulations issued by the United States Environmental Protection Agency in 1988 require, with several exceptions, that underground storage tank systems containing petroleum fuels and hazardous chemicals be routinely tested for releases. This paper summarizes the release detection regulations for tank systems containing chemicals and gives a preliminary assessment of the approaches to release detection currently being used. To make this assessment, detailed discussions were conducted with providers and manufacturers of leak detection equipment and testing services, owners or operators of different types of chemical storage tank systems, and state and local regulators. While these discussions were limited to a small percentage of each type of organization, certain observations are sufficiently distinctive and important that they are reported for further investigation and evaluation. To make it clearer why certain approaches are being used, this paper also summarizes the types of chemicals being stored, the effectiveness of several leak detection testing systems, and the number and characteristics of the tank systems being used to store these products

  18. Feasibility studies for pump and treat technology at leaking underground storage tank sites in Michigan

    International Nuclear Information System (INIS)

    O'Brien, J.M.; Pekas, B.S.

    1993-01-01

    Releases from underground storage tanks have resulted in impacts to groundwater at thousands of sites across the US. Investigations of these sites were initiated on a national basis with the implementation of federal laws that became effective December 22, 1989 (40 CFR 280). Completion of these investigations has led to a wave of design and installation of pump and treat aquifer restoration systems where impacts to groundwater have been confirmed. The purpose of this paper is to provide managers with a demonstration of some of the techniques that can be used by the consulting industry in evaluating the feasibility of pump and treat systems. With knowledge of these tools, managers can better evaluate proposals for system design and their cost effectiveness. To evaluate the effectiveness of typical pump and treat systems for leaking underground storage tank (LUST) sites in Michigan, ten sites where remedial design had been completed were randomly chosen for review. From these ten, two sites were selected that represented the greatest contrast in the types of site conditions encountered. A release of gasoline at Site 1 resulted in contamination of groundwater and soil with benzene, toluene, ethylbenzene, and xylenes

  19. Reducing drinking water supply chemical contamination: risks from underground storage tanks.

    Science.gov (United States)

    Enander, Richard T; Hanumara, R Choudary; Kobayashi, Hisanori; Gagnon, Ronald N; Park, Eugene; Vallot, Christopher; Genovesi, Richard

    2012-12-01

    Drinking water supplies are at risk of contamination from a variety of physical, chemical, and biological sources. Ranked among these threats are hazardous material releases from leaking or improperly managed underground storage tanks located at municipal, commercial, and industrial facilities. To reduce human health and environmental risks associated with the subsurface storage of hazardous materials, government agencies have taken a variety of legislative and regulatory actions--which date back more than 25 years and include the establishment of rigorous equipment/technology/operational requirements and facility-by-facility inspection and enforcement programs. Given a history of more than 470,000 underground storage tank releases nationwide, the U.S. Environmental Protection Agency continues to report that 7,300 new leaks were found in federal fiscal year 2008, while nearly 103,000 old leaks remain to be cleaned up. In this article, we report on an alternate evidence-based intervention approach for reducing potential releases from the storage of petroleum products (gasoline, diesel, kerosene, heating/fuel oil, and waste oil) in underground tanks at commercial facilities located in Rhode Island. The objective of this study was to evaluate whether a new regulatory model can be used as a cost-effective alternative to traditional facility-by-facility inspection and enforcement programs for underground storage tanks. We conclude that the alternative model, using an emphasis on technical assistance tools, can produce measurable improvements in compliance performance, is a cost-effective adjunct to traditional facility-by-facility inspection and enforcement programs, and has the potential to allow regulatory agencies to decrease their frequency of inspections among low risk facilities without sacrificing compliance performance or increasing public health risks. © 2012 Society for Risk Analysis.

  20. Closure report for underground storage tank 141-R3U1 and its associated underground piping

    Energy Technology Data Exchange (ETDEWEB)

    Mallon, B.J.; Blake, R.G.

    1994-03-01

    Underground storage tank UST 141-R3U1 at Lawrence Livermore National Laboratory (LLNL), was registered with the State Water Resources Control Board on June 27, 1984. This tank system consisted of a concrete tank, lined with polyvinyl chloride, and approximately 100 feet of PVC underground piping. UST 141-R3U1 had a capacity of 450 gallons. The underground piping connected three floor drains and one sink inside Building 141 to UST 141-R3U1. The wastewater collected in UST 141-R3U1 contained organic solvents, metals, and inorganic acids. On November 30, 1987, the 141-R3U1 tank system failed a precision tank test. The 141-R3U1 tank system was subsequently emptied and removed from service pending further precision tests to determine the location of the leak within the tank system. A precision tank test on February 5, 1988, was performed to confirm the November 30, 1987 test. Four additional precision tests were performed on this tank system between February 25, 1988, and March 6, 1988. The leak was located where the inlet piping from Building 141 penetrates the concrete side of UST 141-R3U1. The volume of wastewater that entered the backfill and soil around and/or beneath UST 141-R3U1 is unknown. On December 13, 1989, the LLNL Environmental Restoration Division submitted a plan to close UST 141-R3U1 and its associated piping to the Alameda County Department of Environmental Health. UST 141-R3U1 was closed as an UST, and shall be used instead as additional secondary containment for two aboveground storage tanks.

  1. Closure report for underground storage tank 141-R3U1 and its associated underground piping

    International Nuclear Information System (INIS)

    Mallon, B.J.; Blake, R.G.

    1994-03-01

    Underground storage tank UST 141-R3U1 at Lawrence Livermore National Laboratory (LLNL), was registered with the State Water Resources Control Board on June 27, 1984. This tank system consisted of a concrete tank, lined with polyvinyl chloride, and approximately 100 feet of PVC underground piping. UST 141-R3U1 had a capacity of 450 gallons. The underground piping connected three floor drains and one sink inside Building 141 to UST 141-R3U1. The wastewater collected in UST 141-R3U1 contained organic solvents, metals, and inorganic acids. On November 30, 1987, the 141-R3U1 tank system failed a precision tank test. The 141-R3U1 tank system was subsequently emptied and removed from service pending further precision tests to determine the location of the leak within the tank system. A precision tank test on February 5, 1988, was performed to confirm the November 30, 1987 test. Four additional precision tests were performed on this tank system between February 25, 1988, and March 6, 1988. The leak was located where the inlet piping from Building 141 penetrates the concrete side of UST 141-R3U1. The volume of wastewater that entered the backfill and soil around and/or beneath UST 141-R3U1 is unknown. On December 13, 1989, the LLNL Environmental Restoration Division submitted a plan to close UST 141-R3U1 and its associated piping to the Alameda County Department of Environmental Health. UST 141-R3U1 was closed as an UST, and shall be used instead as additional secondary containment for two aboveground storage tanks

  2. Underground storage tanks cause environmental chaos

    International Nuclear Information System (INIS)

    Cruver, P.C.

    1991-01-01

    This paper reports that during the 1950s and the subsequent three decades, petroleum products were stored in single-walled steel underground tanks; an out-of-sight, out-of-mind philosophy prevailed. Unfathomable amounts of toxic petroleum products leaking into the nation's ground water supplies has prompted enactment of recent and much needed legislation and regulation to remedy this major problem. Is the public aware of this serious ecological imbroglio? No, not as yet; except for the closing of many rural service stations and the plethora of dug-up, exposed tanks at urban stations, one could never imagine the severity of this debacle confronting the petroleum industry and the nation's environment

  3. Testing and correction of underground tanks at LLNL: Workplan and schedule

    International Nuclear Information System (INIS)

    Henry, R.K.; Schwartz, W.W.; Castro, D.J.

    1987-01-01

    This report defines a workplan and time schedule for leak tightness testing of underground tank systems and for corrective measures for systems shown by testing to leak. The systems addressed by this report failed a leak tightness test or the test results were inconclusive. The workplan prescribes testing all systems to yield conclusive results. Systems shown to leak will be repaired, retested, and either left in service or be closed. Materials effected by leakage will be cleaned up or removed. 2 figs., 2 tabs

  4. Results of Tank-Leak Detection Demonstration Using Geophysical Techniques at the Hanford Mock Tank Site-Fiscal Year 2001

    International Nuclear Information System (INIS)

    Barnett, D BRENT.; Gee, Glendon W.; Sweeney, Mark D.

    2002-01-01

    During July and August of 2001, Pacific Northwest National Laboratory (PNNL), hosted researchers from Lawrence Livermore and Lawrence Berkeley National laboratories, and a private contractor, HydroGEOPHYSICS, Inc., for deployment of the following five geophysical leak-detection technologies at the Hanford Site Mock Tank in a Tank Leak Detection Demonstration (TLDD): Electrical Resistivity Tomography (ERT); Cross-Borehole Electromagnetic Induction (CEMI) ; High-Resolution Resistivity (HRR); Cross-Borehole Radar (XBR); Cross-Borehole Seismic Tomography (XBS). Under a ''Tri-party Agreement'' with Federal and state regulators, the U.S. Department of Energy will remove wastes from single-shell tanks (SSTs) and other miscellaneous underground tanks for storage in the double-shell tank system. Waste retrieval methods are being considered that use very little, if any, liquid to dislodge, mobilize, and remove the wastes. As additional assurance of protection of the vadose zone beneath the SSTs, tank wastes and tank conditions may be aggressively monitored during retrieval operations by methods that are deployed outside the SSTs in the vadose zone

  5. 40 CFR 280.220 - Ownership of an underground storage tank or underground storage tank system or facility or...

    Science.gov (United States)

    2010-07-01

    ... tank or underground storage tank system or facility or property on which an underground storage tank or underground storage tank system is located. 280.220 Section 280.220 Protection of Environment ENVIRONMENTAL... underground storage tank or underground storage tank system or facility or property on which an underground...

  6. SINGLE-SHELL TANKS LEAK INTEGRITY ELEMENTS/SX FARM LEAK CAUSES AND LOCATIONS - 12127

    Energy Technology Data Exchange (ETDEWEB)

    VENETZ TJ; WASHENFELDER D; JOHNSON J; GIRARDOT C

    2012-01-25

    Washington River Protection Solutions, LLC (WRPS) developed an enhanced single-shell tank (SST) integrity project in 2009. An expert panel on SST integrity was created to provide recommendations supporting the development of the project. One primary recommendation was to expand the leak assessment reports (substitute report or LD-1) to include leak causes and locations. The recommendation has been included in the M-045-9IF Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) as one of four targets relating to SST leak integrity. The 241-SX Farm (SX Farm) tanks with leak losses were addressed on an individual tank basis as part of LD-1. Currently, 8 out of 23 SSTs that have been reported to having a liner leak are located in SX Farm. This percentage was the highest compared to other tank farms which is why SX Farm was analyzed first. The SX Farm is comprised of fifteen SSTs built 1953-1954. The tanks are arranged in rows of three tanks each, forming a cascade. Each of the SX Farm tanks has a nominal I-million-gal storage capacity. Of the fifteen tanks in SX Farm, an assessment reported leak losses for the following tanks: 241-SX-107, 241-SX-108, 241-SX-109, 241-SX-111, 241-SX-112, 241-SX-113, 241-SX-114 and 241-SX-115. The method used to identify leak location consisted of reviewing in-tank and ex-tank leak detection information. This provided the basic data identifying where and when the first leaks were detected. In-tank leak detection consisted of liquid level measurement that can be augmented with photographs which can provide an indication of the vertical leak location on the sidewall. Ex-tank leak detection for the leaking tanks consisted of soil radiation data from laterals and drywells near the tank. The in-tank and ex-tank leak detection can provide an indication of the possible leak location radially around and under the tank. Potential leak causes were determined using in-tank and ex-tank information that is not directly related to

  7. Single-Shell Tanks Leak Integrity Elements/ SX Farm Leak Causes and Locations - 12127

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal [URS- Safety Management Solutions, Richland, Washington 99352 (United States); Harlow, Don [ELR Consulting Richland, Washington 99352 (United States); Venetz, Theodore; Washenfelder, Dennis [Washington River Protection Solutions, LLC Richland, Washington 99352 (United States); Johnson, Jeremy [U.S. Department of Energy, Office of River Protection Richland, Washington 99352 (United States)

    2012-07-01

    Washington River Protection Solutions, LLC (WRPS) developed an enhanced single-shell tank (SST) integrity project in 2009. An expert panel on SST integrity was created to provide recommendations supporting the development of the project. One primary recommendation was to expand the leak assessment reports (substitute report or LD-1) to include leak causes and locations. The recommendation has been included in the M-045-91F Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) as one of four targets relating to SST leak integrity. The 241-SX Farm (SX Farm) tanks with leak losses were addressed on an individual tank basis as part of LD-1. Currently, 8 out of 23 SSTs that have been reported to having a liner leak are located in SX Farm. This percentage was the highest compared to other tank farms which is why SX Farm was analyzed first. The SX Farm is comprised of fifteen SSTs built 1953-1954. The tanks are arranged in rows of three tanks each, forming a cascade. Each of the SX Farm tanks has a nominal 1-million-gal storage capacity. Of the fifteen tanks in SX Farm, an assessment reported leak losses for the following tanks: 241-SX-107, 241-SX-108, 241-SX-109, 241-SX- 111, 241-SX-112, 241-SX-113, 241-SX-114 and 241-SX-115. The method used to identify leak location consisted of reviewing in-tank and ex-tank leak detection information. This provided the basic data identifying where and when the first leaks were detected. In-tank leak detection consisted of liquid level measurement that can be augmented with photographs which can provide an indication of the vertical leak location on the sidewall. Ex-tank leak detection for the leaking tanks consisted of soil radiation data from laterals and dry-wells near the tank. The in-tank and ex-tank leak detection can provide an indication of the possible leak location radially around and under the tank. Potential leak causes were determined using in-tank and ex-tank information that is not directly related to

  8. Results of Tank-Leak Detection Demonstration Using Geophysical Techniques at the Hanford Mock Tank Site-Fiscal Year 2001

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, D BRENT.; Gee, Glendon W.; Sweeney, Mark D.

    2002-03-01

    During July and August of 2001, Pacific Northwest National Laboratory (PNNL), hosted researchers from Lawrence Livermore and Lawrence Berkeley National laboratories, and a private contractor, HydroGEOPHYSICS, Inc., for deployment of the following five geophysical leak-detection technologies at the Hanford Site Mock Tank in a Tank Leak Detection Demonstration (TLDD): (1) Electrical Resistivity Tomography (ERT); (2) Cross-Borehole Electromagnetic Induction (CEMI); (3) High-Resolution Resistivity (HRR); (4) Cross-Borehole Radar (XBR); and (5) Cross-Borehole Seismic Tomography (XBS). Under a ''Tri-party Agreement'' with Federal and state regulators, the U.S. Department of Energy will remove wastes from single-shell tanks (SSTs) and other miscellaneous underground tanks for storage in the double-shell tank system. Waste retrieval methods are being considered that use very little, if any, liquid to dislodge, mobilize, and remove the wastes. As additional assurance of protection of the vadose zone beneath the SSTs, tank wastes and tank conditions may be aggressively monitored during retrieval operations by methods that are deployed outside the SSTs in the vadose zone.

  9. Lower Colorado River GRP Underground Storage Tank Sites (Closed), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  10. Lower Colorado River GRP Underground Storage Tank Sites (Open), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  11. Underground Storage Tanks - Storage Tank Locations

    Data.gov (United States)

    NSGIC Education | GIS Inventory — A Storage Tank Location is a DEP primary facility type, and its sole sub-facility is the storage tank itself. Storage tanks are aboveground or underground, and are...

  12. Assessment of ground-water contamination from a leaking underground storage tank at a defense supply center near Richmond, Virginia

    International Nuclear Information System (INIS)

    Powell, J.D.; Wright, W.G.

    1990-01-01

    During 1988-89, 24 wells were installed in the vicinity of the post-exchange gasoline station on the Defense General Supply Center, near Richmond, Virginia, to collect and analyze groundwater samples for the presence of gasoline contamination from a leaking underground storage tank. Concentrations of total petroleum hydrocarbons and benzene were as high as 8.2 mg/L and 9,000 microg/L, respectively, in water from wells in the immediate vicinity of the former leaking tank, and benzene concentrations were as high as 2,300 microg/L in a well 600 ft down gradient from the gasoline station. Groundwater flow rate are estimated to be about 60 to 80 ft/yr; on the basis of these flow rates, the contaminants may have been introduced into the groundwater as long as 7-10 yrs ago. Groundwater might infiltrate a subsurface storm sewer, where the sewer is below the water table, and discharge into a nearby stream. Preliminary risk assessment for the site identified no potential human receptors to the groundwater contamination because there were no groundwater users identified in the area. Remediation might be appropriate if exposure of future potential users is concern. Alternatives discussed for remediation of groundwater contamination in the upper aquifer at the PX Service Station include no-action, soil vapor extraction, and groundwater pumping and treatment alternatives

  13. 40 CFR 280.230 - Operating an underground storage tank or underground storage tank system.

    Science.gov (United States)

    2010-07-01

    ... underground storage tank or underground storage tank system. (a) Operating an UST or UST system prior to...) Operating an UST or UST system after foreclosure. The following provisions apply to a holder who, through..., the purchaser must decide whether to operate or close the UST or UST system in accordance with...

  14. Regulatory analysis for the use of underground barriers at the Hanford Site tank farms

    International Nuclear Information System (INIS)

    Hampsten, K.L.

    1994-01-01

    Sixty-seven of the single-shell tanks at the Hanford Site, Richland, Washington, are assumed to have leaked in the past. Some of the waste retrieval options being considered, such as past-practice sluicing (a process that uses hot water to dislodge waste for subsequent removal by pumping), have the potential for increasing releases of dangerous waste from these tanks. Underground barrier systems are being evaluated as a method to mitigate releases of tank waste to the soil and groundwater that may occur during retrieval activities. The following underground barrier system options are among those being evaluated to determine whether their construction at the Single-Shell Tank Farms is viable. (1) A desiccant barrier would be created by circulating air through the subsurface soil to lower and then maintain the water saturation below the levels required for liquids to flow. (2) An injected materials barrier would be created by injecting materials such as grout or silica into the subsurface soils to form a barrier around and under a given tank or tank farm. (3) A cryogenic barrier would be created by freezing subsurface soils in the vicinity of a tank or tank farm. An analysis is provided of the major regulatory requirements that may impact full scale construction and operation of an underground barrier system and a discussion of factors that should be considered throughout the barrier selection process, irrespective of the type of underground barrier system being considered. However, specific barrier systems will be identified when a given regulation will have significant impact on a particular type of barrier technology. Appendix A provides a matrix of requirements applicable to construction and operation of an underground barrier system

  15. Double Shell Tank AY-102 Radioactive Waste Leak Investigation

    International Nuclear Information System (INIS)

    Washenfelder, Dennis J.

    2014-01-01

    PowerPoint. The objectives of this presentation are to: Describe Effort to Determine Whether Tank AY-102 Leaked; Review Probable Causes of the Tank AY-102 Leak; and, Discuss Influence of Leak on Hanford's Double-Shell Tank Integrity Program

  16. A risk-based approach to prioritize underground storage tanks

    International Nuclear Information System (INIS)

    Chidambariah, V.; Travis, C.C.; Trabalka, J.R.; Thomas, J.K.

    1992-01-01

    The purpose of this paper is to present a risk-based approach for rapid prioritization of low level liquid radioactive waste underground storage tanks (LLLW USTs) for possible interim corrective measures and/or ultimate closure. The ranking of LLLW USTs is needed to ensure that tanks with the greatest potential for adverse impact on the environment and human health receive top priority for further evaluation and remediation. Wastes from the LLLW USTs at the Oak Ridge National Laboratory (ORNL) were pumped out at the time the tanks were removed from service. The residual liquids and sludge contain a mixture of radionuclides and chemicals. Contaminants of concern that were identified in the liquid phase of the inactive LLLW USTs include, the radionuclides, 9O Sr, 137 Cs and 233 U and the chemicals, carbon tetrachloride, trichloroethene, tetrachloroethene, methyl ethyl ketone, mercury, lead and chromium. The risk-based approach for prioritization of the LLLW USTs is based upon three major criteria: (1) leaking characteristics of the tank; (2) location of the tanks; and (3) toxic potential of the tank contents

  17. Cathode protection for underground steel tanks

    International Nuclear Information System (INIS)

    Angelovski, Zoran

    1998-01-01

    Cathodic protection of underground petroleum storage tanks and piping systems is acceptable for both economic and ecological reasons. With out the cathodic protection of underground steel reservoirs, short time after the exploitation, there was a bore as a result of underground corrosion. The bore causes ecological consequences and at the same time its repair needs big investments. Furthermore, there are great number of tanks placed near cities, so in the future this problem needs a special attention in order to preserve ecological surrounding. The topic of this paper is underground corrosion as well as cathodic protection of steel tanks for oil derivatives storage. (author)

  18. Engineering study of tank leaks related to hydraulic retrieval of sludge from tank 241-C-106

    International Nuclear Information System (INIS)

    Lowe, S.S.; Carlos, W.C.; Irwin, J.J.; Khaleel, R.; Kline, N.W.; Ludowise, J.D.; Marusich, R.M.; Rittman, P.D.

    1993-01-01

    This study evaluates hydraulic retrieval (sluicing) of the waste in single-shell tank 241-C-106 with respect to the likelihood of tank leaks, gross volumes of potential leaks, and their consequences. A description of hydraulic retrieval is developed to establish a baseline for the study. Leak models are developed based on postulated leak mechanisms to estimate the amount of waste that could potentially leak while sluicing. Transport models describe the movement of the waste constituents in the surrounding soil and groundwater after a leak occurs. Environmental impact and risk associated with tank leaks are evaluated. Transport of leaked material to the groundwater is found to be dependent on the rate of recharge of moisture in the soil for moderate-sized leaks. Providing a cover over the tank and surrounding area would eliminate the recharge. The bulk of any leaked material would remain in the vicinity of the tank for remedial action

  19. Accessing leaking underground storage tank case studies and publications through the EPA's Computerized On-Line Information System (COLIS)

    International Nuclear Information System (INIS)

    Hillger, R.; Tibay, P.

    1991-01-01

    The US EPA's regulations for underground storage tanks (USTs) require corrective action to be taken in response to leaking USTs. Recent developments of UST programs nationwide as well as the introduction of new technologies to clean up UST sites have increased the diversity of experience levels among personnel involved with this type of work. The EPA's Computerized On-Line Information System (COLIS) has been developed to facilitate technology transfer among the personnel involved in UST cleanup. The system allows for the quick and simple retrieval of data relating to UST incidents, as well as other hazardous waste-related information. The system has been used by response personnel at all levels of government, academia, and private industry. Although it has been in existence for many years, users are just now realizing the potential wealth of information stored in this system. COLIS access can be accomplished via telephone lines utilizing a personal computer and a modem

  20. An algorithm for leak point detection of underground pipelines

    International Nuclear Information System (INIS)

    Lee, Young Sup; Yoon, Dong Jin

    2004-01-01

    Leak noise is a good source to identify the exact location of a leak point of underground water pipelines. Water leak generates broadband noise from a leak location and can be propagated to both directions of water pipes. However, the necessity of long-range detection of this leak location makes to identify low-frequency acoustic waves rather than high frequency ones. Acoustic wave propagation coupled with surrounding boundaries including cast iron pipes is theoretically analyzed and the wave velocity was confirmed with experiment. The leak locations were identified both by the acoustic emission (AE) method and the cross-correlation method. In a short-range distance, both the AE method and cross-correlation method are effective to detect leak position. However, the detection for a long-range distance required a lower frequency range accelerometers only because higher frequency waves were attenuated very quickly with the increase of propagation paths. Two algorithms for the cross-correlation function were suggested, and a long-range detection has been achieved at real underground water pipelines longer than 300 m.

  1. Underground Storage Tanks in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Underground storage tank (UST) sites which store petroleum in Iowa. Includes sites which have been reported to DNR, and have active or removed underground storage...

  2. Operational tank leak detection and minimization during retrieval

    International Nuclear Information System (INIS)

    Hertzel, J.S.

    1996-03-01

    This report evaluates the activities associated with the retrieval of wastes from the single-shell tanks proposed under the initial Single-Shell Tank Retrieval System. This report focuses on minimizing leakage during retrieval by using effective leak detection and mitigating actions. After reviewing the historical data available on single-shell leakage, and evaluating current leak detection technology, this report concludes that the only currently available leak detection method which can function within the most probable leakage range is the mass balance system. If utilized after each sluicing campaign, this method should allow detection at a leakage value well below the leakage value where significant health effects occur which is calculated for each tank. Furthermore, this report concludes that the planned sequence or sluicing activities will serve to further minimize the probability and volume of leaks by keeping liquid away from areas with the greatest potential for leaking. Finally, this report identifies a series of operational responses which when used in conjunction with the recommended sluicing sequence and leak detection methods will minimize worker exposure and environmental safety health risks

  3. Tank car leaks gasoline

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    On January 27, 1994, a Canadian National (CN) tank car loaded with gasoline began to leak from a crack in the tank shell on the end of the car near the stub sill. The tank car had been damaged from impact switching. A part of the tank car was sent for laboratory analysis which concluded that: (1) the fracture originated in two locations in welds, (2) the cracks propagated in a symmetrical manner and progressed into the tank plate, (3) the fracture surface revealed inadequate weld fusion. A stress analysis of the tank car was conducted to determine the coupling force necessary to cause the crack. It was noted that over the last decade several problems have occurred pertaining to stub sill areas of tank cars that have resulted in hazardous material spills. An advisory was sent to Transport Canada outlining many examples where tank cars containing serious defects had passed CN inspections that were specifically designed to identify such defects. 4 figs

  4. Underground storage tank management plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    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.

  5. Underground storage tank management plan

    International Nuclear Information System (INIS)

    1994-09-01

    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

  6. Risks from Past, Current, and Potential Hanford Single Shell Tank Leaks

    Energy Technology Data Exchange (ETDEWEB)

    Triplett, Mark B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Watson, David J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wellman, Dawn M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-05-01

    Due to significant delays in constructing and operating the Waste Treatment Plant, which is needed to support retrieval of waste from Hanford’s single shell tanks (SSTs), SSTs may now be required to store tank waste for two to three more decades into the future. Many SSTs were built almost 70 years ago, and all SSTs are well beyond their design lives. Recent examination of monitoring data suggests several of the tanks, which underwent interim stabilization a decade or more ago, may be leaking small amounts (perhaps 150–300 gallons per year) to the subsurface environment. A potential leak from tank T-111 is estimated to have released approximately 2,000 gallons into the subsurface. Observations of past leak events, recently published simulation results, and new simulations all suggest that recent leaks are unlikely to affect underlying groundwater above regulatory limits. However, these recent observations remind us that much larger source terms are still contained in the tanks and are also present in the vadose zone from historical intentional and unintentional releases. Recently there have been significant improvements in methods for detecting and characterizing soil moisture and contaminant releases, understanding and controlling mass-flux, and remediating deep vadose zone and groundwater plumes. To ensure extended safe storage of tank waste in SSTs, the following actions are recommended: 1) Improve capabilities for intrusion and leak detection. 2) Develop defensible conceptual models of intrusion and leak mechanisms. 3) Apply enhanced subsurface characterization methods to improve detection and quantification of moisture changes beneath tanks. 4) Maintain a flux-based assessment of past, present, and potential tank leaks to assess risks and to maintain priorities for applying mitigation actions. 5) Implement and maintain effective mitigation and remediation actions to protect groundwater resources. These actions will enable limited resources to be applied to

  7. Hanford Double-Shell Tank AY-102 Radioactive Waste Leak Investigation Update

    International Nuclear Information System (INIS)

    Washenfelder, Dennis J.

    2015-01-01

    The presentation outline is: Briefly review leak integrity status of tank AY-102 and current leak behavior; Summarize recent initiatives to understand leak mechanism and to verify integrity of remaining waste confinement structures; describe planned waste recovery activities; and, introduce other papers on tank AY-102 topics.

  8. Hanford Double-Shell Tank AY-102 Radioactive Waste Leak Investigation Update

    Energy Technology Data Exchange (ETDEWEB)

    Washenfelder, Dennis J. [Washington River Protection Solutions, Richland, WA (United States)

    2015-02-03

    The presentation outline is: Briefly review leak integrity status of tank AY-102 and current leak behavior; Summarize recent initiatives to understand leak mechanism and to verify integrity of remaining waste confinement structures; describe planned waste recovery activities; and, introduce other papers on tank AY-102 topics.

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

    International Nuclear Information System (INIS)

    Harrington, Stephanie J.; Sams, Terry L.

    2013-01-01

    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

  10. Hanford Single-Shell Tank Leak Causes and Locations - 241-B Farm

    International Nuclear Information System (INIS)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-01-01

    This document identifies 241-B Tank Farm (B Farm) leak cause and locations for the 100 series leaking tank (241-B-107) identified in RPP-RPT-49089, Hanford B-Farm Leak Inventory Assessments Report. This document satisfies the B Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F

  11. Non-uniform regulations of underground storage tanks in the United States

    International Nuclear Information System (INIS)

    Nadim, F.; Hoag, G.E.; Liu, S.; Carley, R.J.; Zack, P.

    2000-01-01

    Leaking underground storage tanks (USTs) are one of the major sources of ground water contamination. United States federal regulations for USTs were established in September of 1988. Since that time little or no amendments have been made to these regulations. In order to protect sensitive areas such as aquifer recharge zones for public water supply wells and wetlands, different states have been obligated to apply more stringent standards than the federal UST regulations. This practice however, has led to a non-uniform application of regulations for USTs throughout the country. In this article, United States regulations for USTs are reviewed and its deficits are highlighted. Based on these regulations and the experience of northeastern states of United States, a sequence of leak and spill preventive measures for USTs is proposed. Application of the proposed measures could substantially reduce the possibility of UST failure and would be more protective of the subsurface environment. (author)

  12. Hanford Single-Shell Tank Leak Causes and Locations - 241-C Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-07-30

    This document identifies 241-C Tank Farm (C Farm) leak causes and locations for the 100 series leaking tanks (241-C-101 and 241-C-105) identified in RPP-RPT-33418, Rev. 2, Hanford C-Farm Leak Inventory Assessments Report. This document satisfies the C Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  13. Hanford Single Shell Tank Leak Causes and Locations - 241-TX Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, C. L.; Harlow, D> G.

    2014-07-22

    This document identifies 241-TX Tank Farm (TX Farm) leak causes and locations for the 100 series leaking tanks (241-TX-107 and 241-TX-114) identified in RPP-RPT-50870, Rev. 0, Hanford 241-TX Farm Leak Inventory Assessment Report. This document satisfies the TX Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  14. Hanford Single-Shell Tank Leak Causes and Locations - 241-A Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-09-10

    This document identifies 241-A Tank Farm (A Farm) leak causes and locations for the 100 series leaking tanks (241-A-104 and 241-A-105) identified in RPP-ENV-37956, Hanford A and AX Farm Leak Assessment Report. This document satisfies the A Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  15. Underground or aboveground storage tanks - A critical decision

    International Nuclear Information System (INIS)

    Rizzo, J.A.

    1992-01-01

    With the 1988 promulgation of the comprehensive Resource Conservation and Recovery Act (RCRA) regulations for underground storage of petroleum and hazardous substances, many existing underground storage tank (UST) owners have been considering making the move to aboveground storage. While on the surface, this may appear to be the cure-all to avoiding the underground leakage dilemma, there are many other new and different issues to consider with aboveground storage. The greatest misconception is that by storing materials above ground, there is no risk of subsurface environmental problems. It should be noted that with the aboveground storage tank (AGST) systems, there is still considerable risk of environmental contamination, either by the failure of onground tank bottoms or the spillage of product onto the ground surface where it subsequently finds its way to the ground water. In addition, there are added safety concerns that must be addressed. The greatest interest in AGSTs comes from managers with small volumes of used oil, fresh oil, solvents, chemicals, or heating oil. Dealing with small capacity tanks is not so different than large bulk storage - and, in fact, it lends itself to more options, such as portable storage, tank within tank configurations and inside installations. So what are the other specific areas of concern besides environmental to be addressed when making the decision between underground and aboveground tanks? The primary issues that will be addressed in this presentation are: (1) safety; (2) product losses; (3) cost comparison of USTs vs AGSTs; (4) space availability/accessibility; (5) precipitation handling; (6) aesthetics and security; (7) pending and existing regulations

  16. Energy Policy Act of 2005 and Underground Storage Tanks (USTs)

    Science.gov (United States)

    The Energy Policy Act of 2005 significantly affected federal and state underground storage tank programs, required major changes to the programs, and is aimed at reducing underground storage tank releases to our environment.

  17. Underground storage tank program

    International Nuclear Information System (INIS)

    Lewis, M.W.

    1994-01-01

    Underground storage tanks, UST'S, have become a major component of the Louisville District's Environmental Support Program. The District's Geotechnical and Environmental Engineering Branch has spear-headed an innovative effort to streamline the time, effort and expense for removal, replacement, upgrade and associated cleanup of USTs at military and civil work installations. This program, called Yank-A-Tank, creates generic state-wide contracts for removal, remediation, installation and upgrade of storage tanks for which individual delivery orders are written under the basic contract. The idea is to create a ''JOC type'' contract containing all the components of work necessary to remove, reinstall or upgrade an underground or above ground tank. The contract documents contain a set of generic specifications and unit price books in addition to the standard ''boiler plate'' information. Each contract requires conformance to the specific regulations for the state in which it is issued. The contractor's bid consists of a bid factor which in the multiplier used with the prices in the unit price book. The solicitation is issued as a Request for Proposal (RPP) which allows the government to select a contractor based on technical qualification an well as bid factor. Once the basic contract is awarded individual delivery orders addressing specific areas of work are scoped, negotiated and awarded an modifications to the original contract. The delivery orders utilize the prepriced components and the contractor's factor to determine the value of the work

  18. Pipeline leak detection using volatile tracers

    International Nuclear Information System (INIS)

    Thompson, G.M.; Golding, R.D.

    1993-01-01

    A method of leak detection for underground storage tanks and pipelines adds volatile tracers to the products in the tanks and analyzes the surrounding shallow soil gases for tracer vapors. This method has several advantages: the success of the test is not limited by the size and structural design of the vessels, tanks can be tested at any fill level without taking the tank out of service, the location of a leak along a pipeline is clearly marked by the location of the tracer, and liquid leaks as small as 0.2 liters per hour (lph) can be detected. A limitation is: the backfill material must have some degree of air permeability in the zone above the water table. Several field tests document the success achieved using this method. A tracer leak detection system was installed at Homestead AFB after several other testing methods failed to locate a leak at a valve pit location along approximately 4 kilometers of fuel transfer piping. The leak was detected to the side of the valve pit at a depth of approximately 2.5 meters below the ground surface. Another installation of Edwards AFB involved the collection of 415 soil gas samples along approximately 3,050 meters of 15.25-centimeter fiberglass pipeline. Fourteen separate leaks were detected

  19. Frequencies of leaks and probability of ignition sources in the H-area tank farm

    International Nuclear Information System (INIS)

    Cramer, D.S.

    1994-01-01

    Point estimates are developed for the probability of an ignition source for tetraphenylborate (TPB) solids in H-area which leak into the annulus of Tank 48 and/or in the Filter Cell. Additionally, leak frequencies and leak rates are estimated for: the inner cell wall of Tank 48; Hanford connectors and single-wall transfer lines in the Filter Cell of the In-Tank Precipitation (ITP) Facility; and the double-wall transfer lines between tank 48, the Filter Cell, Tank 49 and the 'Late Wash' Tank

  20. Permanent Closure of the TAN-664 Underground Storage Tank

    Energy Technology Data Exchange (ETDEWEB)

    Bradley K. Griffith

    2011-12-01

    This closure package documents the site assessment and permanent closure of the TAN-664 gasoline underground storage tank in accordance with the regulatory requirements established in 40 CFR 280.71, 'Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.'

  1. Assessment of historical leak model methodology as applied to the REDOX high-level waste tank SX-108

    International Nuclear Information System (INIS)

    JONES, T.E.

    1999-01-01

    Using the Historical Leak Model approach, the estimated leak rate (and therefore, projected leak volume) for Tank 241-SX-108 could not be reproduced using the data included in the initial document describing the leak methodology. An analysis of parameters impacting tank heat load calculations strongly suggest that the historical tank operating data lack the precision and accuracy required to estimate tank leak volumes using the Historical Leak Model methodology

  2. Hanford Single-Shell Tank Leak Causes and Locations - 241-SX Farm

    International Nuclear Information System (INIS)

    Girardot, Crystal L.; Harlow, Donald G.

    2014-01-01

    This document identifies 241-SX Tank Farm (SX Farm) leak causes and locations for the 100 series leaking tanks (241-SX-107, 241-SX-108, 241-SX-109, 241-SX-111, 241-SX-112, 241-SX-113, 241-SX-114, and 241-SX-115) identified in RPP-ENV-39658, Rev. 0, Hanford SX-Farm Leak Assessments Report. This document satisfies the SX Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F

  3. Hanford Single-Shell Tank Leak Causes and Locations - 241-SX Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L. [Washington River Protection Solutions (United States); Harlow, Donald G. [Washington River Protection Solutions (United States)

    2014-01-08

    This document identifies 241-SX Tank Farm (SX Farm) leak causes and locations for the 100 series leaking tanks (241-SX-107, 241-SX-108, 241-SX-109, 241-SX-111, 241-SX-112, 241-SX-113, 241-SX-114, and 241-SX-115) identified in RPP-ENV-39658, Rev. 0, Hanford SX-Farm Leak Assessments Report. This document satisfies the SX Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  4. Risk-based prioritization for the interim remediation of inactive low-level liquid radioactive waste underground storage tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Chidambariah, V.; Travis, C.C.; Trabalka, J.R.; Thomas, J.K.

    1992-09-01

    The paper presents a risk-based approach for rapid prioritization of low-level liquid radioactive waste underground storage tanks (LLLW USTs), for possible interim corrective measures and/or ultimate closure. The ranking of LLLW USTs is needed to ensure that tanks with the greatest potential for adverse impact on the environment and human health receive top priority for further evaluation and remediation. Wastes from the LLLW USTs at Oak Ridge National Laboratory were pumped out when the tanks were removed from service. The residual liquids and sludge contain a mixture of radionuclides and chemicals. Contaminants of concern that were identified in the liquid phase of the inactive LLLW USTs include the radionuclides 90 Sr, 137 Cs, and 233 U and the chemicals carbon tetrachloride, trichloroethane, tetrachloroethene, methyl ethyl ketone, mercury, lead, and chromium. The risk-based approach for prioritization of the LLLW USTs is based upon three major criteria: (1) leaking characteristics of the tank, (2) location of the tanks, and (3) toxic potential of the tank contents. Leaking characteristics of LLLW USTs will aid in establishing the potential for the release of contaminants to environmental media. In this study, only the liquid phase was assumed to be released to the environment. Scoring criteria for release potential of LLLW USTs was determined after consideration of the magnitude of any known leaks and the tank type for those that are not known to leak

  5. State Certification of Underground Storage Tanks

    National Research Council Canada - National Science Library

    Granetto, Paul

    1998-01-01

    .... The audit was performed in response to a Senate Armed Services Committee inquiry about whether state environmental regulatory agencies would be able to certify that DoD underground storage tanks...

  6. Basis UST leak detection systems

    International Nuclear Information System (INIS)

    Silveria, V.

    1992-01-01

    This paper reports that gasoline and other petroleum products are leaking from underground storage tanks (USTs) at an alarming rate, seeping into soil and groundwater. Buried pipes are an even greater culprit, accounting for most suspected and detected leaks according to Environmental Protection Agency (EPA) estimates. In response to this problem, the EPA issued regulations setting standards for preventing, detecting, reporting, and cleaning up leaks, as well as fiscal responsibility. However, federal regulations are only a minimum; some states have cracked down even harder Plant managers and engineers have a big job ahead of them. The EPA estimates that there are more than 75,000 fuel USTs at US industrial facilities. When considering leak detection systems, the person responsible for making the decision has five primary choices: inventory reconciliation combined with regular precision tightness tests; automatic tank gauging; groundwater monitoring; interstitial monitoring of double containment systems; and vapor monitoring

  7. Environmental risk comparisons with internal methods of UST leak detection

    International Nuclear Information System (INIS)

    Durgin, P.B.

    1993-01-01

    The past five years have seen a variety of advances in how leaks can be detected from within underground storage tanks. Any leak-detection approach employed within a storage tanks must be conducted at specific time intervals and meet certain leak-rate criteria according to federal and state regulations. Nevertheless, the potential environmental consequences of leak detection approaches differ widely. Internal, volumetric UST monitoring techniques have developed over time including: (1) inventory control with stick measurements, (2) precision tank testing, (3) automatic tank gauging (ATG), (4) statistical inventory reconciliation (SIR), and (5) statistical techniques with automatic tank gauging. An ATG focuses on the advantage of precise data but measured for only a brief period. On the other hand, stick data has less precision but when combined with SIR over extended periods it too can detect low leak rates. Graphs demonstrate the comparable amounts of fuel than can leak out of a tank before being detected by these techniques. The results indicate that annual tank testing has the greatest potential for large volumes of fuel leaking without detection while new statistical approaches with an ATG have the least potential. The environmental implications of the volumes of fuel leaked prior to detection are site specific. For example, if storage tank is surrounded by a high water table and in a sole-source aquifer even small leaks may cause problems. The user must also consider regulatory risks. The level of environmental and regulatory risk should influence selection of the UST leak detection method

  8. Tank drive : ZCL takes its composite tank technology worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Byfield, M.

    2010-06-15

    Edmonton-based ZCL Composites Inc. is North America's largest manufacturer and supplier of fibreglass reinforced plastic (FRP) underground storage tanks. The company has aggressively pursued new markets in the oil sands, shale gas gas, and other upstream petroleum industries. The manufacturer also targets water and sewage applications, and provides customized corrosion solutions for a variety of industries. The company developed its double-walled FRP tanks in response to Canadian Environmental Protection Act rules requiring cathodic protection for steel tanks, leak detection, and secondary containment. ZCL supplies approximately 90 per cent of the new tanks installed by gasoline retailers in Canada. Future growth is expected to be strong, as many old tanks will soon need to be replaced. The company has also developed a method of transforming underground single wall tanks into secondarily contained systems without digging them out. The company has also recently signed licence agreements with tank manufacturers in China. 3 figs.

  9. Annular Air Leaks in a liquid hydrogen storage tank

    Science.gov (United States)

    Krenn, AG; Youngquist, RC; Starr, SO

    2017-12-01

    Large liquid hydrogen (LH2) storage tanks are vital infrastructure for NASA, the DOD, and industrial users. Over time, air may leak into the evacuated, perlite filled annular region of these tanks. Once inside, the extremely low temperatures will cause most of the air to freeze. If a significant mass of air is allowed to accumulate, severe damage can result from nominal draining operations. Collection of liquid air on the outer shell may chill it below its ductility range, resulting in fracture. Testing and analysis to quantify the thermal conductivity of perlite that has nitrogen frozen into its interstitial spaces and to determine the void fraction of frozen nitrogen within a perlite/frozen nitrogen mixture is presented. General equations to evaluate methods for removing frozen air, while avoiding fracture, are developed. A hypothetical leak is imposed on an existing tank geometry and a full analysis of that leak is detailed. This analysis includes a thermal model of the tank and a time-to-failure calculation. Approaches to safely remove the frozen air are analyzed, leading to the conclusion that the most feasible approach is to allow the frozen air to melt and to use a water stream to prevent the outer shell from chilling.

  10. 200 Area plateau inactive miscellaneous underground storage tanks locations

    International Nuclear Information System (INIS)

    Brevick, C.H.

    1997-01-01

    Fluor Daniel Northwest (FDNW) has been tasked by Lockheed Martin Hanford Corporation (LMHC) to incorporate current location data for 64 of the 200-Area plateau inactive miscellaneous underground storage tanks (IMUST) into the centralized mapping computer database for the Hanford facilities. The IMUST coordinate locations and tank names for the tanks currently assigned to the Hanford Site contractors are listed in Appendix A. The IMUST are inactive tanks installed in underground vaults or buried directly in the ground within the 200-East and 200-West Areas of the Hanford Site. The tanks are categorized as tanks with a capacity of less than 190,000 liters (50,000 gal). Some of the IMUST have been stabilized, pumped dry, filled with grout, or may contain an inventory or radioactive and/or hazardous materials. The IMUST have been out of service for at least 12 years

  11. Double-Shell Tank Visual Inspection Changes Resulting from the Tank 241-AY-102 Primary Tank Leak

    International Nuclear Information System (INIS)

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

    2013-01-01

    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-102 (AY-102) 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-102 1eak 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

  12. Underground storage tanks: State regulations and compliance strategies

    International Nuclear Information System (INIS)

    Robinson, J.E.

    1988-01-01

    In an effort to resolve underground storage tank (UST) management problems, several states and localities have moved ahead of EPA in the promulgation of UST regulations. Developed independently, these regulations represent different strategies for ensuring compliance: from an extensive set of permitting requirements that allow for the implementation of site-specific control measures to a uniform set of technical and operational requirements that vary according to installation date. For the tank owner, complying with these regulations can be a time-consuming and frustrating endeavor. However, during the course of several environmental audits of similar facilities in different states, useful strategies were observed or developed that enabled facilities to respond more effectively to requirements: these included computerization of files, designation of tank custodians, installation of low-maintenance equipment, and increased use of above-ground tanks. Of special additional interest was the wide variation in costs for similar tank services quoted by both private and government sources. These strategies are coupled with general observations on the efficacy of the various regulatory approaches to provide a field view that may be useful to tank owners and others involved in underground tank management and evaluation

  13. Polymers for subterranean containment barriers for underground storage tanks (USTs)

    International Nuclear Information System (INIS)

    Heiser, J.H.; Colombo, P.; Clinton, J.

    1992-12-01

    The US Department of Energy (DOE) set up the Underground Storage Tank Integrated Demonstration Program (USTID) to demonstrate technologies for the retrieval and treatment of tank waste, and closure of underground storage tanks (USTs). There are more than 250 underground storage tanks throughout the DOE complex. These tanks contain a wide variety of wastes including high level, low level, transuranic, mixed and hazardous wastes. Many of the tanks have performed beyond the designed lifetime resulting in leakage and contamination of the local geologic media and groundwater. To mitigate this problem it has been proposed that an interim subterranean containment barrier be placed around the tanks. This would minimize or prevent future contamination of soil and groundwater in the event that further tank leakages occur before or during remediation. Use of interim subterranean barriers can also provide sufficient time to evaluate and select appropriate remediation alternatives. The DOE Hanford site was chosen as the demonstration site for containment barrier technologies. A panel of experts for the USTID was convened in February, 1992, to identify technologies for placement of subterranean barriers. The selection was based on the ability of candidate grouts to withstand high radiation doses, high temperatures and aggressive tank waste leachates. The group identified and ranked nine grouting technologies that have potential to place vertical barriers and five for horizontal barriers around the tank. The panel also endorsed placement technologies that require minimal excavation of soil surrounding the tanks

  14. Analysis of ICPP tank farm infiltration

    International Nuclear Information System (INIS)

    Richards, B.T.

    1993-10-01

    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

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

    International Nuclear Information System (INIS)

    Harrington, Stephanie J.; Sams, Terry L.

    2013-01-01

    Full text - Long Abstract. A routine video inspection of the annulus region of double-shell tank 241-A Y-102 in August of 2012 indicated the presence material in the annulus space between the primary and secondary liners. A comparison was made to previous inspections performed in 2006 and 2007. which indicated that a change had occurred. The material was observed at two locations on the floor of the annulus and one location at the top of the annulus region where the primary and secondary top knuckles meet (RPP-ASMT-53793). Subsequent inspections were performed. leading to additional material observed on the floor of the annulus space in a region that had not previously been inspected (WRPS-PER-2012-1363). The annulus Continuous Air Monitor (CAM) was still operational and was not indicating elevated radiation levels in the annulus region. When the camera from the inspections was recovered. it also did not indicate increased radiation above minimum contamination levels (WRPS-PER-2012-1363). A formal leak assessment team was established August 10, 2012 to review tank 241-AY-102 construction and operating histories and to determine whether the material observed in the annulus had resulted from a leak in the primary tank. The team consisted of individuals from Engineering. Base Operations and Environmental Protection. As this was a first-of-its-kind task. a method for obtaining a sample of the material in the annulus was needed. The consistency of the material was unknown.and the location of a majority of the material was not conducive to using the sampling devices that were currently available at Hanford. A subcontractor was tasked with the development fabrication.and testing of a sampling device that would be able to obtain multiple samples from the material on the annulus floor. as well as the material originating from a refractory air-slot near the floor of the annulus space. This sampler would need to be able to collect and dispense the material it collected into a

  16. Hanford Single-Shell Tank Leak Causes and Locations - 241-BY and 241-TY Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2014-09-04

    This document identifies 241-BY Tank Farm (BY Farm) and 241-TY Tank Farm (TY Farm) lead causes and locations for the 100 series leaking tanks (241-BY-103, 241-TY-103, 241-TY-104, 241-TY-105 and 241-TY-106) identified in RPP-RPT-43704, Hanford BY Farm Leak Assessments Report, and in RPP-RPT-42296, Hanford TY Farm Leak Assessments Report. This document satisfies the BY and TY Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  17. Tank Waste Remediation System Inactive Miscellaneous Underground Storage Tanks Program Plan

    International Nuclear Information System (INIS)

    Gustavson, R.D.

    1995-12-01

    The Program Management Plan (PMP) describes the approach that will be used to manage the Tank Waste Remediation System (TWRS) Inactive Miscellaneous Underground Storage Tank (IMUST) Program. The plan describes management, technical, and administrative control systems that will be used to plan and control the IMUSTs Program performance. The technical data to determine the IMUSTs status for inclusion in the Single Shell Tank Farm Controlled Clean and Stable (CCS) Program. The second is to identify and implement surveillance, characterization, stabilization, and modifications to support CCS prior to final closure

  18. Automated Leak Detection Of Buried Tanks Using Geophysical Methods At The Hanford Nuclear Site

    International Nuclear Information System (INIS)

    Calendine, S.; Schofield, J.S.; Levitt, M.T.; Fink, J.B.; Rucker, D.F.

    2011-01-01

    At the Hanford Nuclear Site in Washington State, the Department of Energy oversees the containment, treatment, and retrieval of liquid high-level radioactive waste. Much of the waste is stored in single-shelled tanks (SSTs) built between 1943 and 1964. Currently, the waste is being retrieved from the SSTs and transferred into newer double-shelled tanks (DSTs) for temporary storage before final treatment. Monitoring the tanks during the retrieval process is critical to identifying leaks. An electrically-based geophysics monitoring program for leak detection and monitoring (LDM) has been successfully deployed on several SSTs at the Hanford site since 2004. The monitoring program takes advantage of changes in contact resistance that will occur when conductive tank liquid leaks into the soil. During monitoring, electrical current is transmitted on a number of different electrode types (e.g., steel cased wells and surface electrodes) while voltages are measured on all other electrodes, including the tanks. Data acquisition hardware and software allow for continuous real-time monitoring of the received voltages and the leak assessment is conducted through a time-series data analysis. The specific hardware and software combination creates a highly sensitive method of leak detection, complementing existing drywell logging as a means to detect and quantify leaks. Working in an industrial environment such as the Hanford site presents many challenges for electrical monitoring: cathodic protection, grounded electrical infrastructure, lightning strikes, diurnal and seasonal temperature trends, and precipitation, all of which create a complex environment for leak detection. In this discussion we present examples of challenges and solutions to working in the tank farms of the Hanford site.

  19. Microseismic response characteristics modeling and locating of underground water supply pipe leak

    Science.gov (United States)

    Wang, J.; Liu, J.

    2015-12-01

    In traditional methods of pipeline leak location, geophones must be located on the pipe wall. If the exact location of the pipeline is unknown, the leaks cannot be identified accurately. To solve this problem, taking into account the characteristics of the pipeline leak, we propose a continuous random seismic source model and construct geological models to investigate the proposed method for locating underground pipeline leaks. Based on two dimensional (2D) viscoacoustic equations and the staggered grid finite-difference (FD) algorithm, the microseismic wave field generated by a leaking pipe is modeled. Cross-correlation analysis and the simulated annealing (SA) algorithm were utilized to obtain the time difference and the leak location. We also analyze and discuss the effect of the number of recorded traces, the survey layout, and the offset and interval of the traces on the accuracy of the estimated location. The preliminary results of the simulation and data field experiment indicate that (1) a continuous random source can realistically represent the leak microseismic wave field in a simulation using 2D visco-acoustic equations and a staggered grid FD algorithm. (2) The cross-correlation method is effective for calculating the time difference of the direct wave relative to the reference trace. However, outside the refraction blind zone, the accuracy of the time difference is reduced by the effects of the refracted wave. (3) The acquisition method of time difference based on the microseismic theory and SA algorithm has a great potential for locating leaks from underground pipelines from an array located on the ground surface. Keywords: Viscoacoustic finite-difference simulation; continuous random source; simulated annealing algorithm; pipeline leak location

  20. Technical bases for leak detection surveillance of waste storage tanks. Revision 1

    International Nuclear Information System (INIS)

    Johnson, M.G.; Badden, J.J.

    1995-01-01

    This document provides the technical bases for specification limits, monitoring frequencies and baselines used for leak detection and intrusion (for single shell tanks only) in all single and double shell radioactive waste storage tanks, waste transfer lines, and most catch tanks and receiver tanks in the waste tank farms and associated areas at Hanford

  1. Permanent Closure of MFC Biodiesel Underground Storage Tank 99ANL00013

    Energy Technology Data Exchange (ETDEWEB)

    Kerry L. Nisson

    2012-10-01

    This closure package documents the site assessment and permanent closure of the Materials and Fuels Complex biodiesel underground storage tank 99ANL00013 in accordance with the regulatory requirements established in 40 CFR 280.71, “Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.”

  2. Engineering evaluation of alternatives: Managing the assumed leak from single-shell Tank 241-T-101

    International Nuclear Information System (INIS)

    Brevick, C.H.; Jenkins, C.

    1996-02-01

    At mid-year 1992, the liquid level gage for Tank 241-T-101 indicated that 6,000 to 9,000 gal had leaked. Because of the liquid level anomaly, Tank 241-T-101 was declared an assumed leaker on October 4, 1992. SSTs liquid level gages have been historically unreliable. False readings can occur because of instrument failures, floating salt cake, and salt encrustation. Gages frequently self-correct and tanks show no indication of leak. Tank levels cannot be visually inspected and verified because of high radiation fields. The gage in Tank 241-T-101 has largely corrected itself since the mid-year 1992 reading. Therefore, doubt exists that a leak has occurred, or that the magnitude of the leak poses any immediate environmental threat. While reluctance exists to use valuable DST space unnecessarily, there is a large safety and economic incentive to prevent or mitigate release of tank liquid waste into the surrounding environment. During the assessment of the significance of the Tank 241-T-101 liquid level gage readings, Washington State Department of Ecology determined that Westinghouse Hanford Company was not in compliance with regulatory requirements, and directed transfer of the Tank 241-T-101 liquid contents into a DST. Meanwhile, DOE directed WHC to examine reasonable alternatives/options for safe interim management of Tank 241-T-101 wastes before taking action. The five alternatives that could be used to manage waste from a leaking SST are: (1) No-Action, (2) In-Tank Stabilization, (3) External Tank Stabilization, (4) Liquid Retrieval, and (5) Total Retrieval. The findings of these examinations are reported in this study

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

    Energy Technology Data Exchange (ETDEWEB)

    Piepho, M.G.

    1995-03-01

    At the Hanford site in SE Washington, there are 149 single-shell tanks containing radionuclide wastes in the form of liquids, sludges and salt cakes. One of the tanks, tank 241-C-106, is heated to the boiling point due to radionuclide decay (primarily Sr-90). Water is added to the tank, which is ventilated, in order to cool the tank. 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 outs, its temperature is expected to greatly increase, which could affect the structural integrity of the concrete tank dome. Hence, it is of interest to know how fast the temperature in a leaky tank increases, so that mitigation procedures can be planned and implemented in a timely manner. 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.

  4. Vitrification of underground storage tanks: Technology development, regulatory issues, and cost analysis

    International Nuclear Information System (INIS)

    Tixier, J.S.; Corathers, L.A.; Anderson, L.D.

    1992-03-01

    In situ vitrification (ISV), developed by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE), is a thermal treatment process for the remediation of hazardous, radioactive, or mixed waste sites. The process has been broadly patented both domestically and abroad. Since the inception of ISV in 1980, developmental activities have been focused on applications to contaminated soils, and more recently the potential for application to buried wastes and underground structures (tanks). Research performed to date on the more advanced ISV applications (i.e., application to buried wastes and underground tanks) shows that significant technical and economic potential exists for using ISV to treat buried wastes and underground structures containing radionuclides and/or hazardous constituents. Present ISV applications are directed to the treatment of contaminated soils; the likelihood of using ISV to treat underground tanks depends on the resolution of significant technical and institutional issues related to this advanced application. This paper describes the ISV process and summarizes the technical progress of underground tank vitrification (UTV), discusses pertinent regulatory issues facing the use of UTV, and presents the potential cost of UTV relative to other remedial action alternatives

  5. Model based, sensor-directed remediation of underground storage tanks

    International Nuclear Information System (INIS)

    Harrigan, R.W.; Thunborg, S.

    1990-01-01

    Sensor-rich, intelligent robots that function with respect to models of their environment have significant potential to reduce the time and cost for the cleanup of hazardous waste while increasing operator safety. Sandia National Laboratories (SNL) is performing technology development and experimental investigations into the application of intelligent robot control technology to the problem of cleaning up waste stored in underground tanks. The tasks addressed in the SNL experiments are in situ physical characterizations of underground storage tanks (USTs) as well as the contained waste and the removal of the waste from the tank both for laboratory analysis and as part of the tank cleanup process. Both fully automatic and manual robot control technologies are being developed and demonstrated. The SNL-developed concept of human-assisted computer control will be employed whenever manual control of the robot is required. The UST Robot Technology Development Laboratory (URTDL) consists of a commercial gantry robot modified to allow hybrid force/position control

  6. Remote inspection of underground storage tanks

    International Nuclear Information System (INIS)

    Griebenow, B.L.; Martinson, L.M.

    1992-01-01

    Westinghouse Idaho Nuclear Company, Inc. (WINCO) operates the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy. The ICPP's mission is to process government-owned spent nuclear fuel. The process involves dissolving the fuel, extracting off uranium, and calcining the waste to a solid form for storage, Prior to calcining, WINCO temporarily stores the liquid waste from this process in eleven 1,135,600-l(300,000-gal), 15,2-m (50-ft)-diam, high-level liquid waste tanks. Each of these stainless steel tanks is contained within an underground concrete vault. The only access to the interior of the tanks is through risers that extend from ground level to the dome of the tanks. WINCO is replacing these tanks because of their age and the fact that they do not meet all of the current design requirements. The tanks will be replaced in two phases. WINCO is now in the Title I design stage for four new tank and vault systems to replace five of the existing systems. The integrity of the six remaining tanks must be verified to continue their use until they can be replaced in the second phase. To perform any integrity analysis, the inner surface of the tanks must be inspected. The remote tank inspection (RTI) robotic system, designed by RedZone Robotics of Pittsburgh, Pennsylvania, was developed to access the interior of the tanks and position various end effectors required to perform tank wall inspections

  7. Chemical information on tank supernatants, Cs adsorption from tank liquids onto Hanford sediments, and field observations of Cs migration from past tank leaks

    Energy Technology Data Exchange (ETDEWEB)

    Serne, R.J.; Zachara, J.M.; Burke, D.S.

    1998-01-01

    Borehole gamma-logging profiles beneath the SX-Tank Farm suggest that contamination from Cs-137 extends to at least a depth of 40 m (130 ft), and may extend even deeper. What is presently not known is the pathway that Cs-137 has taken to reach these depths. In this report we provide an analysis of the chemistry of tank supernates with emphasis on the REDOX waste stream disposed in SX tanks, Cs chemistry in aqueous solutions and adsorption properties onto minerals, available data on Cs adsorption onto Hanford sediments, and information on Cs migration from other Hanford tank leaks that have been studied. The data in this report was used to help guide the vadose zone transport analysis of the SX Tank Farm presented in a companion report. The goal of the vadose zone transport modelling is to attempt to explain the depth and extent of the Cs-137 plume under the SX Tank farm, specifically in the vicinity of the greatest leak, near the SX-109 Tank as inferred from the gamma logs (DOE 1996). In solution Cs is present as the monovalent cation and shows very little tendency to form aqueous complexes with inorganic or organic ligands. Cs is expected to adsorb primarily onto selective minerals that have unique adsorption sites. The small Cs{sup +} ion is accommodated on these frayed edge and interlayer sites. Adsorption within the interlayers often leads to collapse of the layers such that the Cs{sup +} ion is effectively trapped and not readily exchangeable by all other common cations. The degree of adsorption is thus only moderately dependent on the types and high concentrations of other cations in leaking tank liquors.

  8. Chemical information on tank supernatants, Cs adsorption from tank liquids onto Hanford sediments, and field observations of Cs migration from past tank leaks

    International Nuclear Information System (INIS)

    Serne, R.J.; Zachara, J.M.; Burke, D.S.

    1998-01-01

    Borehole gamma-logging profiles beneath the SX-Tank Farm suggest that contamination from Cs-137 extends to at least a depth of 40 m (130 ft), and may extend even deeper. What is presently not known is the pathway that Cs-137 has taken to reach these depths. In this report we provide an analysis of the chemistry of tank supernates with emphasis on the REDOX waste stream disposed in SX tanks, Cs chemistry in aqueous solutions and adsorption properties onto minerals, available data on Cs adsorption onto Hanford sediments, and information on Cs migration from other Hanford tank leaks that have been studied. The data in this report was used to help guide the vadose zone transport analysis of the SX Tank Farm presented in a companion report. The goal of the vadose zone transport modelling is to attempt to explain the depth and extent of the Cs-137 plume under the SX Tank farm, specifically in the vicinity of the greatest leak, near the SX-109 Tank as inferred from the gamma logs (DOE 1996). In solution Cs is present as the monovalent cation and shows very little tendency to form aqueous complexes with inorganic or organic ligands. Cs is expected to adsorb primarily onto selective minerals that have unique adsorption sites. The small Cs + ion is accommodated on these frayed edge and interlayer sites. Adsorption within the interlayers often leads to collapse of the layers such that the Cs + ion is effectively trapped and not readily exchangeable by all other common cations. The degree of adsorption is thus only moderately dependent on the types and high concentrations of other cations in leaking tank liquors

  9. Regulatory approaches to hydrocarbon contamination from underground storage tanks

    International Nuclear Information System (INIS)

    Daugherty, S.J.

    1991-01-01

    Action or lack of action by the appropriate regulatory agency is often the most important factor in determining remedial action or closure requirements for hydrocarbon contaminated sites. This paper reports that the diversity of regulatory criteria is well known statewide and well documented nationally. In California, the diversity of approaches is due to: that very lack of a clear understanding of the true impact of hydrocarbon contamination: lack of state or federal standards for soil cleanup, and state water quality objectives that are not always achievable; vagueness in the underground storage tank law; and the number and diversity of agencies enforcing the underground storage tank regulations

  10. Decision analysis of Hanford underground storage tank waste retrieval systems

    International Nuclear Information System (INIS)

    Merkhofer, M.W.; Bitz, D.A.; Berry, D.L.; Jardine, L.J.

    1994-05-01

    A decision analysis approach has been proposed for planning the retrieval of hazardous, radioactive, and mixed wastes from underground storage tanks. This paper describes the proposed approach and illustrates its application to the single-shell storage tanks (SSTs) at Hanford, Washington

  11. Large underground radioactive waste storage tanks successfully cleaned at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Billingsley, K.; Burks, B.L.; Johnson, M.; Mims, C.; Powell, J.; Hoesen, D. van

    1998-05-01

    Waste retrieval operations were successfully completed in two large underground radioactive waste storage tanks in 1997. The US Department of Energy (DOE) and the Gunite Tanks Team worked cooperatively during two 10-week waste removal campaigns and removed approximately 58,300 gallons of waste from the tanks. About 100 gallons of a sludge and liquid heel remain in each of the 42,500 gallon tanks. These tanks are 25 ft. in diameter and 11 ft. deep, and are located in the North Tank Farm in the center of Oak Ridge National Laboratory. Less than 2% of the radioactive contaminants remain in the tanks, proving the effectiveness of the Radioactive Tank Cleaning System, and accomplishing the first field-scale cleaning of contaminated underground storage tanks with a robotic system in the DOE complex

  12. Underground storage tank soft waste dislodging and conveyance

    International Nuclear Information System (INIS)

    Wellner, A.F.S.

    1993-01-01

    The primary objective of this task is to demonstrate potential technical solutions and to acquire engineering data and information on the retrieval technologies applicable for use in retrieving waste from underground storage tanks. This task focuses on soft waste dislodging and conveyance technologies that would be used in conjunction with a manipulator-based retrieval system. This retrieval task focuses on Hanford single-shell tanks, but the results may also have applications to other waste retrieval problems. This work is part of the U.S. Department of Energy's (DOE's) Office of Technology Development, sponsored by the DOE's Richland Operations Office under the Underground Storage Tanks Integrated Demonstration (USTID) program. This task is one element of the whole waste dislodging and conveyance system in the USTID. The tank wastes contain both hazardous and radioactive constituents. This task focuses on the processes for dislodging and retrieving soft wastes, mainly sludge. Sludge consists primarily of heavy-metal, iron, and aluminum precipitates. Sludges vary greatly in their physical properties and may contain pockets of liquid. Sludges have been described as varying in consistency from thick slurry to sticky clay and as sandy with hard chunks of material. The waste is believed to have adhesive and cohesive properties. The quantitative physical properties of the wastes have yet to be measured. The waste simulants used in the testing program emulate the physical properties of the tank waste

  13. Tank issues: Design and placement of floating liquid monitoring wells. Final report

    International Nuclear Information System (INIS)

    Bedinger, M.S.

    1993-02-01

    Liquid product monitoring is the predominant method of external leak detection where the water table is within the zone of excavation. The paper discusses the use of liquid product monitors at new and old tank installations for detecting leaks from underground hydrocarbon storage tanks. The paper discusses the site conditions under which liquid product monitors can be effectively used, conditions which may mitigate or prevent the effective use of liquid product monitors, and the construction and placement of liquid product monitoring wells. Liquid product monitors are not used to determine the rate of tank leak. The rate of tank lead can be determined by other methods such as inventory or internal monitoring methods. Effective use of liquid product monitors or any other method of leak detection requires training and experience on the part of the user

  14. Underground Storage Tank Integrated Demonstration (UST-ID)

    International Nuclear Information System (INIS)

    1994-02-01

    The DOE complex currently has 332 underground storage tanks (USTs) that have been used to process and store radioactive and chemical mixed waste generated from weapon materials production. Very little of the over 100 million gallons of high-level and low-level radioactive liquid waste has been treated and disposed of in final form. Two waste storage tank design types are prevalent across the DOE complex: single-shell wall and double-shell wall designs. They are made of stainless steel, concrete, and concrete with carbon steel liners, and their capacities vary from 5000 gallons (19 m 3 ) to 10 6 gallons (3785 m 3 ). The tanks have an overburden layer of soil ranging from a few feet to tens of feet. Responding to the need for remediation of tank waste, driven by Federal Facility Compliance Agreements (FFCAs) at all participating sites, the Underground Storage Tank Integrated Demonstration (UST-ID) Program was created by the US DOE Office of Technology Development in February 1991. Its mission is to focus the development, testing, and evaluation of remediation technologies within a system architecture to characterize, retrieve, treat to concentrate, and dispose of radioactive waste stored in USTs at DOE facilities. The ultimate goal is to provide safe and cost-effective solutions that are acceptable to the public and the regulators. The UST-ID has focused on five DOE locations: the Hanford Site, which is the host site, in Richland, Washington; the Fernald Site in Fernald, Ohio; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; the Oak Ridge Reservation in Oak Ridge, Tennessee, and the Savannah River Site in Savannah River, South Carolina

  15. Detailed leak detection test plan and schedule for Oak Ridge National Laboratory liquid low-level waste active tanks

    International Nuclear Information System (INIS)

    1995-01-01

    This document provides a plan and schedule for leak testing a portion of the Liquid Low-Level Waste (LLLW) system at the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. It is a concise version of a more general leak testing plan that was prepared in response to the requirements of the Federal Facility Agreement (FFA) for the Oak Ridge Reservation (ORR). This plan includes a schedule for the initial reporting of the leak test results from the various tanks that will be tested. The FFA distinguishes four categories of tank and pipeline systems: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA specifically requires leak testing of the Category C systems; there are 14 such tanks addressed in this plan, plus one tank (W-12) that has been temporarily returned to service based on EPA and TDEC concurrence. A schedule for testing these tanks is also included. The plan and schedule also addresses an additional 15 Category B tanks have been demonstrated to meet secondary containment requirements. While these 15 tanks are addressed in this plan for the sake of completeness, they have been removed from the leak testing program based on the design demonstrations that show secondary containment. It is noted that the general plan included 42 tanks. Since that report was issued, 26 of those tanks have passed secondary containment design demonstrations and subsequently have been removed from this leak testing plan. In addition, one tank (LA-104) has been removed from service. Accordingly, this document addresses 15 of the LLLW tanks in the system; plans for testing the pipelines will be described in a separate document

  16. Detailed leak detection test plan and schedule for Oak Ridge National Laboratory liquid low-level waste active tanks

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

    This document provides a plan and schedule for leak testing a portion of the Liquid Low-Level Waste (LLLW) system at the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. It is a concise version of a more general leak testing plan that was prepared in response to the requirements of the Federal Facility Agreement (FFA) for the Oak Ridge Reservation (ORR). This plan includes a schedule for the initial reporting of the leak test results from the various tanks that will be tested. The FFA distinguishes four categories of tank and pipeline systems: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA specifically requires leak testing of the Category C systems; there are 14 such tanks addressed in this plan, plus one tank (W-12) that has been temporarily returned to service based on EPA and TDEC concurrence. A schedule for testing these tanks is also included. The plan and schedule also addresses an additional 15 Category B tanks have been demonstrated to meet secondary containment requirements. While these 15 tanks are addressed in this plan for the sake of completeness, they have been removed from the leak testing program based on the design demonstrations that show secondary containment. It is noted that the general plan included 42 tanks. Since that report was issued, 26 of those tanks have passed secondary containment design demonstrations and subsequently have been removed from this leak testing plan. In addition, one tank (LA-104) has been removed from service. Accordingly, this document addresses 15 of the LLLW tanks in the system; plans for testing the pipelines will be described in a separate document.

  17. Corrosion Evaluation of Tank 40 Leak Detection Box

    Energy Technology Data Exchange (ETDEWEB)

    Mickalonis, J.I.

    1999-07-29

    'Leak detection from the transfer lines in the tank farm has been a concern for many years because of the need to minimize exposure of personnel and contamination of the environment. The leak detection box (LDB) is one line of defense, which must be maintained to meet this objective. The evaluation of a failed LDB was one item from an action plan aimed at minimizing the degradation of LDBs. The Tank 40 LDB, which failed in service, was dug up and shipped to SRTC for evaluation. During a video inspection while in service, this LDB was found to have black tubercles on the interior, which suggested possible microbial involvement. The failure point, however, was believed to have occurred in the drain line from the transfer line jacket. Visual, metallurgical, and biological analyses were performed on the LDB. The analysis results showed that there was not any adverse microbiological growth or significant localized corrosion. The corrosion of the LDB was caused by exposure to aqueous environments and was typical of carbon steel pipes in soil environments.'

  18. Analysis of SX farm leak histories - Historical leak model (HLM)

    International Nuclear Information System (INIS)

    Fredenburg, E.A.

    1998-01-01

    This report uses readily available historical information to better define the volume, chemical composition, and Cs-137/Sr-90 amounts for leaks that have occurred in the past for tanks SX-108, SX-109, SX-111, and SX-112. In particular a Historical Leak Model (HLM) is developed that is a month by month reconciliation of tank levels, fill records, and calculated boil-off rates for these tanks. The HLM analysis is an independent leak estimate that reconstructs the tank thermal histories thereby deriving each tank's evaporative volume loss and by difference, its unaccounted losses as well. The HLM analysis was meant to demonstrate the viability of its approach, not necessarily to establish the HLM leak estimates as being definitive. Past leak estimates for these tanks have invariably resorted to soil wetting arguments but the extent of soil contaminated by each leak has always been highly uncertain. There is also a great deal of uncertainty with the HLM that was not quantified in this report, but will be addressed later. These four tanks (among others) were used from 1956 to 1975 for storage of high-level waste from the Redox process at Hanford. During their operation, tank waste temperatures were often as high as 150 C (300 F), but were more typically around 130 C. The primary tank cooling was by evaporation of tank waste and therefore periodic replacement of lost volume with water was necessary to maintain each tank's inventory. This active reflux of waste resulted in very substantial turnovers in tank inventory as well as significant structural degradation of these tanks. As a result of the loss of structural integrity, each of these tanks leaked during their active periods of operation. Unfortunately, the large turnover in tank volume associated with their reflux cooling has made a determination of leak volumes very difficult. During much of these tanks operational histories, inventory losses because of evaporative cooling could have effectively masked any volume

  19. SURFACE GEOPHYSICAL EXPLORATION DEVELOPING NONINVASIVE TOOLS TO MONITOR PAST LEAKS AROUND HANFORD TANK FARMS

    Energy Technology Data Exchange (ETDEWEB)

    MYERS DA; RUCKER DF; LEVITT MT; CUBBAGE B; NOONAN GE; MCNEILL M; HENDERSON C

    2011-06-17

    A characterization program has been developed at Hanford to image past leaks in and around the underground storage tank facilities. The program is based on electrical resistivity, a geophysical technique that maps the distribution of electrical properties of the subsurface. The method was shown to be immediately successful in open areas devoid of underground metallic infrastructure, due to the large contrast in material properties between the highly saline waste and the dry sandy host environment. The results in these areas, confirmed by a limited number of boreholes, demonstrate a tendency for the lateral extent of the underground waste plume to remain within the approximate footprint of the disposal facility. In infrastructure-rich areas, such as tank farms, the conventional application of electrical resistivity using small point-source surface electrodes initially presented a challenge for the resistivity method. The method was then adapted to directly use the buried infrastructure as electrodes for both transmission of electrical current and measurements of voltage. For example, steel-cased wells that surround the tanks were used as long electrodes, which helped to avoid much of the infrastructure problems. Overcoming the drawbacks of the long electrode method has been the focus of our work over the past seven years. The drawbacks include low vertical resolution and limited lateral coverage. The lateral coverage issue has been improved by supplementing the long electrodes with surface electrodes in areas devoid of infrastructure. The vertical resolution has been increased by developing borehole electrode arrays that can fit within the small-diameter drive casing of a direct push rig. The evolution of the program has led to some exceptional advances in the application of geophysical methods, including logistical deployment of the technology in hazardous areas, development of parallel processing resistivity inversion algorithms, and adapting the processing tools

  20. Local Leak Detection and Health Monitoring of Pressurized Tanks

    Science.gov (United States)

    Polzin, Kurt; Witherow, William; Korman, Valentin; Sinko, John; Hendrickson, Adam

    2011-01-01

    An optical gas-detection sensor safely monitors pressurized systems (such as cryogenic tanks) and distribution systems for leaks. This sensor system is a fiber-coupled, solid optical body interferometer that allows for the miniaturized sensing element of the device to be placed in the smallest of recesses, and measures a wide range of gas species and densities (leaks). The deflection of the fringe pattern is detected and recorded to yield the time-varying gas density in the gap. This technology can be used by manufacturers or storage facilities with toxic, hazardous, or explosive gases. The approach is to monitor the change in the index of refraction associated with low-level gas leaks into a vacuum environment. The completion of this work will provide NASA with an enabling capability to detect gas system leaks in space, and to verify that pressurized systems are in a safe (i.e. non-leaking) condition during manned docking and transit operations. By recording the output of the sensor, a time-history of the leak can be constructed to indicate its severity. Project risk is mitigated by having several interferometric geometries and detection techniques available, each potentially leveraging hardware and lessons learned to enhance detectability.

  1. Regulated underground storage tanks

    International Nuclear Information System (INIS)

    1992-06-01

    This guidance package is designed to assist DOE Field operations by providing thorough guidance on the underground storage tank (UST) regulations. [40 CFR 280]. The guidance uses tables, flowcharts, and checklists to provide a ''roadmap'' for DOE staff who are responsible for supervising UST operations. This package is tailored to address the issues facing DOE facilities. DOE staff should use this guidance as: An overview of the regulations for UST installation and operation; a comprehensive step-by-step guidance for the process of owning and operating an UST, from installation to closure; and a quick, ready-reference guide for any specific topic concerning UST ownership or operation

  2. An Underground Storage Tank Integrated Demonstration report

    International Nuclear Information System (INIS)

    Quadrel, M.J.; Hunter, V.L.; Young, J.K.; Lini, D.C.; Goldberg, C.

    1993-04-01

    The Waste Characterization Data and Technology Development Needs Assessment provides direct support to the Underground Storage Tank Integrated Demonstration (UST-ID). Key users of the study's products may also include individuals and programs within the US Department of Energy (DOE) Office of Technology Development (EM-50), the Office of Waste Operations (EM-30), and the Office of Environmental Restoration (EM-40). The goal of this work is to provide the UST-ID with a procedure for allocating funds across competing characterization technologies in a timely and defensible manner. It resulted in three primary products: 1. It organizes and summarizes information on underground storage tank characterization data needs. 2. It describes current technology development activity related to each need and flags areas where technology development may be beneficial. 3. It presents a decision process, with supporting software, for evaluating, prioritizing, and integrating possible technology development funding packages. The data presented in this document can be readily updated as the needs of the Waste Operations and Environmental Restoration programs mature and as new and promising technology development options emerge

  3. Robotic system for remote inspection of underground storage tanks

    International Nuclear Information System (INIS)

    Griebenow, B.L.; Martinson, L.M.

    1990-01-01

    Westinghouse Idaho Nuclear Company, Inc. (WINCO), operates the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy (DOE). WINCO's mission is to process government owned spent nuclear fuel. The process involves dissolving the fuel and extracting off uranium. The waste from this process is temporarily stored at the ICPP in underground storage tanks. The tanks were put in service between 1953 and 1966 and are operating 10 to 15 years beyond their design life. Five of the tanks will be replaced by 1998. The integrity of the remaining six tanks must be verified to continue their use until they can be replaced at a later data. In order to verify the tank integrity, a complete corrosion analysis must be performed. This analysis will require a remote visual inspection of the tank surfaces

  4. Consequences of a radioactive surface pool resulting from waste transfer operations between tanks 214-C-106 and 241-AY-102

    International Nuclear Information System (INIS)

    Van Vleet, R.J.

    1997-01-01

    This document contains supporting calculations for quantifying the dose consequences from a pool formed from an underground leak or a-leak from an above grade structure for the Waste Retrieval Sluicing System (Project W-320), i.e., sluicing the contents of Tank 241-C-106 (high heat, SST) into Tank 241-AY-102 (aging waste, DST)

  5. Consequences of a radioactive surface pool resulting from waste transfer operations between tanks 214-C-106 and 241-AY-102

    Energy Technology Data Exchange (ETDEWEB)

    Van Vleet, R.J.

    1997-08-05

    This document contains supporting calculations for quantifying the dose consequences from a pool formed from an underground leak or a-leak from an above grade structure for the Waste Retrieval Sluicing System (Project W-320), i.e., sluicing the contents of Tank 241-C-106 (high heat, SST) into Tank 241-AY-102 (aging waste, DST).

  6. Evaluation of Technologies for Retrieval of Waste from Leaking Tanks

    International Nuclear Information System (INIS)

    Bamberger, Judith A.; Hatchell, Brian K.; Lewis, Benjamin E.; Randolph, John D.; Killough, Stephen M.

    2000-01-01

    The US Department of Energy Environmental and Waste Management Tanks Focus Area selected as a strategic initiative the need to identify and develop technologies for remediation of tanks that are known or are suspected to leak. This investigation identified and evaluated technical options for single-shell tank waste retrieval applicable to retrieve waste from potentially leaking tanks. Technologies that minimize leakage use minimal water, and dry retrieval technologies were evaluated. Safety, cost, authorization basis, and schedule risks were identified for each technology to provide River Protection Program with information to evaluate technical and programmatic risk. A workshop was held to identify technology needs and solutions. These approaches grouped into five categories: those related to waste dislodging, waste conveyance, both waste dislodging and conveyance, the deployment platform, and technologies related to leak detection, monitoring, and mitigation. Based on the ranking, six technologies were selected as potential candidates for further evaluation. These items were prioritized into four technologies to recommend for further evaluation (1) Air assisted TORE(R). The TORE(R) produces a processing vortex core with the ability to convey solids at pre-determined slurry concentrations over great distances. The dry TORE(R) concept uses air to develop the vortex to fluidize dry solids. The TORE(R)the solids in a slurry transport line. (2) Sonication for waste dislodging utilizes ultrasonic energy to fracture and dislodge hard waste types such as salt cake and sludge. (3) Novel long-reach manipulators concept is to investigate novel cost effective approaches for long-reach manipulator technology. (4) Next generation crawler technology envisions a non-umbilical dislodger, possibly radio controlled and powered remotely to provide a deployment platform not affected by path, or the need to retrace steps

  7. Test Plan for the Demonstration of Geophysical Techniques for Single-Shell Tank Leak Detection at the Hanford Mock Tank Site: Fiscal Year 2001

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, D. Brent; Gee, Glendon W.; Sweeney, Mark D.

    2001-07-31

    As part of the Leak Detection, Monitoring and Mitigation (LDMM) program conducted by CH2M HILL 105-A during FY 2001. These tests are being conducted to assess the applicability of these methods (Electrical Resistance Tomography [ERT], High Resolution Resistivity [HRR], Cross-Borehole Seismography [XBS], Cross-Borehole Radar [XBR], and Cross-Borehole Electromagnetic Induction [CEMI]) to the detection and measurement of Single Shell Tank (SST) leaks into the vadose zone during planned sluicing operations. The testing in FY 2001 will result in the selection of up to two methods for further testing in FY 2002. In parallel with the geophysical tests, a Partitioning Interwell Tracer Test (PITT) study will be conducted simultaneously at the Mock Tank to assess the effectiveness of this technology in detecting and quantifying tank leaks in the vadose zone. Preparatory and background work using Cone Penetrometer methods (CPT) will be conducted at the Mock Tank site and an adjacent test area to derive soil properties for groundtruthing purposes for all methods.

  8. Acoustic imaging of underground storage tank wastes

    International Nuclear Information System (INIS)

    Mech, S.J.

    1995-09-01

    Acoustics is a potential tool to determine the properties of high level wastes stored in Underground Storage Tanks. Some acoustic properties were successfully measured by a limited demonstration conducted in 114-TX. This accomplishment provides the basis for expanded efforts to qualify techniques which depend on the acoustic properties of tank wastes. This work is being sponsored by the Department of Energy under the Office of Science and Technology. In FY-1994, limited Tank Waste Remediation Systems EM-30 support was available at Hanford and Los Alamos National Laboratory. The Massachusetts Institute of Technology (MIT) and Earth Resources Laboratory (ERL) were engaged for analysis support, and Elohi Geophysics, Inc. for seismic testing services. Westinghouse-Hanford Company provided the testing and training, supplied the special engineering and safety analysis equipment and procedures, and provided the trained operators for the actual tank operations. On 11/9/94, limited in-tank tests were successfully conducted in tank 114-TX. This stabilized Single Shell Tank was reported as containing 16.8 feet of waste, the lower 6.28 feet of which contained interstitial liquid. Testing was conducted over the lower 12 feet, between two Liquid Observation Wells thirty feet apart. The ''quick-look'' data was reviewed on-site by MIT and Elohi

  9. The electrostatic properties of Fiber-Reinforced-Plastics double wall underground storage gasoline tanks

    International Nuclear Information System (INIS)

    Li, Yipeng; Liu, Quanzhen; Meng, He; Sun, Lifu; Zhang, Yunpeng

    2013-01-01

    At present Fiber Reinforced Plastics (FRP) double wall underground storage gasoline tanks are wildly used. An FRP product with a resistance of more than 10 11 Ω is a static non-conductor, so it is difficult for the static electricity in the FRP product to decay into the earth. In this paper an experimental system was built to simulate an automobile gasoline filling station. Some electrostatic parameters of the gasoline, including volume charge density, were tested when gasoline was unloaded into a FRP double wall underground storage tank. Measurements were taken to make sure the volume charge density in the oil-outlet was similar to the volume charge density in the tank. In most cases the volume charge density of the gasoline was more than 22.7 μC m −3 , which is likely to cause electrostatic discharge in FRP double wall underground storage gasoline tanks. On the other hand, it would be hard to ignite the vapor by electrostatic discharge since the vapor pressure in the tanks is over the explosion limit. But when the tank is repaired or re-used, the operators must pay attention to the static electricity and some measurements should be taken to avoid electrostatic accident. Besides the relaxation time of charge in the FRP double wall gasoline storage tanks should be longer.

  10. Technology Successes in Hanford Tank Waste Storage and Retrieval

    International Nuclear Information System (INIS)

    Cruz, E. J.

    2002-01-01

    The U. S. Department of Energy (DOE), Office of River Protection (ORP) is leading the River Protection Project (RPP), which is responsible for dispositioning approximately 204,000 cubic meters (54 million gallons) of high-level radioactive waste that has accumulated in 177 large underground tanks at the Hanford Site since 1944. The RPP is comprised of five major elements: storage of the waste, retrieval of the waste from the tanks, treatment of the waste, disposal of treated waste, and closure of the tank facilities. Approximately 3785 cubic meters (1 million gallons) of waste have leaked from the older ''single-shell tanks.'' Sixty-seven of the 147 single shell tanks are known or assumed ''leakers.'' These leaks have resulted in contaminant plumes that extend from the tank to the groundwater in a number of tank farms. Retrieval and closure of the leaking tanks complicates the ORP technical challenge because cleanup decisions must consider the impacts of past leaks along with a strategy for retrieving the waste in the tanks. Completing the RPP mission as currently planned and with currently available technologies will take several decades and tens of billions of dollars. RPP continue to pursue the benefits from deploying technologies that reduce risk to human health and the environment, as well as, the cost of cleanup. This paper discusses some of the recent technology partnering activities with the DOE Office of Science and Technology activities in tank waste retrieval and storage

  11. Underground tank remediation by use of in situ vitrification

    International Nuclear Information System (INIS)

    Thompson, L.E.

    1991-02-01

    Pacific Northwest Laboratory (PNL) is developing a remedial action technology for underground storage tanks through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment processes that was originally developed for the stabilization of contaminated soil contaminated with transuranic waste at the Hanford Site in southeastern Washington for the Department of Energy (DOE). The application of ISV to underground storage tanks represents an entirely new application of the ISV technology and is being performed in support of the DOE primarily for the Hanford site and the Oak Ridge National Laboratory (ORNL). A field scale test was conducted in September 1990 at Hanford on a small cement and stainless steel tank (1-m dia.) that contained a simulated refractory sludge representing a worst-case sludge composition. The tank design and sludge composition was based on conditions present at the ORNL. The sludge contained high concentrations of heavy metals including lead, mercury, and cadmium, and also contained high levels of stable cesium and strontium to represent the predominant radionuclide species present in the tank wastes. The test was highly successful in that the entire tank and surrounding soil was transformed into a highly leach resistant glass and crystalline block with a mass of approximately 30 tons. During the process, the metal shell of the tank forms a metal pool at the base of the molten soil. Upon cooling, the glass and metal phases were subjected to TCLP (toxic characteristic leach procedure) testing and passed the TCLP criteria. Additional sampling and analyses are ongoing to determine the bulk composition of the waste forms, the fraction of volatile or semi-volatile species released to the off-gas treatment system, and to determine whether any soil surrounding the monolith was contaminated as a result of the ISV process. 4 refs., 5 figs., 3 tabs

  12. Electrical resistivity tomography for early vadose leak detection under single shell storage tanks

    International Nuclear Information System (INIS)

    Narbutovshih, S.M.

    1996-01-01

    This document describes planned testing with Electrical Resistivity Tomography (ERT). It is prepared in support of TTP RL46WT51 Rev. 1, funded by the Tank Focus Area through the Office of Technology Integration. The primary goal of the testing for fiscal year 1996 (FY96) is to develop and demonstrate the ability to place vertical electrode arrays (VEA) with the cone penetrometer technology (CPT) to depths below existing single shell tanks (SST) at the DOE Hanford Site. It is desirable to have the capability to use CPT for this application for obvious reasons. First, current methods of emplacement, drilled boreholes, are expensive with respect to the rest of the ERT operation. Cone penetrometer VEA emplacements offer the opportunity to significantly reduce installation costs. Second, use of CPT will reduce emplacement time from weeks or months to just several days depending on the number of VEAs and the depth of placement. ERT is preferable to other monitoring methods since operation costs and turn around time are less than the current baselines of either groundwater sampling networks or borehole logging techniques. ERT cost savings can be substantial and will continue into the future. ERT can also provide complete coverage under a tank or other facility which is an important supplement to existing monitoring methods. Groundwater sampling provides one data point per well and borehole logging provides data along a line in the ground. Neither provide information from beneath a facility and thus, are not able to locate release points. These electrode arrays are used to acquire subsurface electrical resistance data in a manner appropriate for tomographic inversion. The resulting tomograms can then be used to detect, monitor and track contaminated moisture plumes leaking from underground storage tanks during waste retrieval operations

  13. Pursing other deep pockets: California's underground storage tank cleanup fund and insurance policies

    International Nuclear Information System (INIS)

    Almanza, P.R.

    1995-01-01

    When faced with a potentially very expensive environmental cleanup, most companies and individuals try to do the only sensible thing, which is to find out if anyone else will pay the bill. This presentation will outline two avenues that may provide a substantial financial contribution to environmental cleanups: (a) California's Underground Storage Tank Cleanup Fund and (b) insurance policies. The Underground Storage Tank Cleanup Fund was established in 1989 to help eligible owners and operators of petroleum underground storage tanks (USTs) to: (a) get reimbursed for costs of unauthorized releases of petroleum from USTs; (b) get reimbursed for damages awarded to third parties as a result of unauthorized releases of petroleum from USTs; and (c) meet federal and state requirements that the UST owner and/or operator be able to pay for cleanup costs and damages to third parties caused by unauthorized releases of petroleum

  14. ACOUSTIC LOCATION OF LEAKS IN PRESSURIZED UNDER- GROUND PETROLEUM PIPELINES

    Science.gov (United States)

    Experiments were conducted at the Underground Storage Tank (UST) Test Apparatus Pipeline in which three acoustic sensors separated by a maximum distance of 38.1 m (125 ft) were used to monitor signals produced by 11.4-, 5.7-, and 3.8-L/h (3.0-, 1.5-, and 1.0-gal/h) leaks in th...

  15. An alarm instrument for monitoring leakage of oil storage tanks and the location of their leak position using radioisotope tracers

    International Nuclear Information System (INIS)

    Lu Qingqian; Sun Xiaolei; Hu Xusheng

    1990-01-01

    Usually it is difficult to find out gasoline leakage at the bottom of a storage tank from the very beginning. In order to solve this problem, a leak-monitoring technique and an instrument based on the detection of nuclear radiation have been successfully developed. The instrument possesses high sensitivity, short reaction time, excellent stability and rellability. When very small leaks at the bottom of a tank appear, the instrument will show a leak signal and give an alarm. In the meantime, however, the tank can be still used until the preparations for repairing are completed. Then its leak position can be accurately located by using radioisotope tracers

  16. Analysis of dissolved benzene plumes and methyl tertiary butyl ether (MTBE) plumes in ground water at leaking underground fuel tank (LUFT) sites

    International Nuclear Information System (INIS)

    Happel, A.M.; Rice, D.; Beckenbach, E.; Savalin, L.; Temko, H.; Rempel, R.; Dooher, B.

    1996-11-01

    The 1990 Clean Air Act Amendments mandate the addition of oxygenates to gasoline products to abate air pollution. Currently, many areas of the country utilize oxygenated or reformulated fuel containing 15- percent and I I-percent MTBE by volume, respectively. This increased use of MTBE in gasoline products has resulted in accidental point source releases of MTBE containing gasoline products to ground water. Recent studies have shown MTBE to be frequently detected in samples of shallow ground water from urban areas throughout the United States (Squillace et al., 1995). Knowledge of the subsurface fate and transport of MTBE in ground water at leaking underground fuel tank (LUFT) sites and the spatial extent of MTBE plumes is needed to address these releases. The goal of this research is to utilize data from a large number of LUFT sites to gain insights into the fate, transport, and spatial extent of MTBE plumes. Specific goals include defining the spatial configuration of dissolved MTBE plumes, evaluating plume stability or degradation over time, evaluating the impact of point source releases of MTBE to ground water, and attempting to identify the controlling factors influencing the magnitude and extent of the MTBE plumes. We are examining the relationships between dissolved TPH, BTEX, and MTBE plumes at LUFT sites using parallel approaches of best professional judgment and a computer-aided plume model fitting procedure to determine plume parameters. Here we present our initial results comparing dissolved benzene and MTBE plumes lengths, the statistical significance of these results, and configuration of benzene and MTBE plumes at individual LUFT sites

  17. Application of intrinsic germanium spectral gamma-ray logging for characterization of high-level nuclear waste tank leaks

    International Nuclear Information System (INIS)

    Brodeur, J.R.; Kiesler, J.P.; Kos, S.E.; Koizumi, C.J.; Nicaise, W.F.; Price, R.K.

    1993-11-01

    Spectral gamma-ray logging with a high-resolution, intrinsic germanium logging system was completed in boreholes surrounding two high-level nuclear waste tanks at the US Department of Energy's Hanford Site. The purpose was to characterize the concentrations of man-made radionuclides in the unsaturated zone sediments and identify any new leaks from the tanks. An intrinsic germanium detection system was used for this work because it was important to positively identify the specific radionuclides and to precisely assay those radionuclides. The spectral gamma log data were processed and displayed as log plots for each individual borehole and as three-dimensional plots of 137 Cs radionuclide concentrations. These data were reviewed to identify the sources of the contamination. The investigation did not uncover a new or active leak from either of the tanks. Most of the contamination found could be related to known pipeline leaks, to surface contamination from aboveground liquid spills, or to leaks from other tanks. The current spectral gamma ray data now provide a new baseline from which to compare future log data and identify any changes in the radioelement concentration

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

    Energy Technology Data Exchange (ETDEWEB)

    D. H. Cox

    2001-06-01

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots

  19. Advancing the US Department of Energy's Technologies through the Underground Storage Tank: Integrated Demonstration Program

    International Nuclear Information System (INIS)

    Gates, T.E.

    1993-01-01

    The principal objective of the Underground Storage Tank -- Integrated Demonstration Program is the demonstration and continued development of technologies suitable for the remediation of waste stored in underground storage tanks. The Underground Storage Tank Integrated Demonstration Program is the most complex of the integrated demonstration programs established under the management of the Office of Technology Development. The Program has the following five participating sites: Oak Ridge, Idaho, Fernald, Savannah River, and Hanford. Activities included within the Underground Storage Tank -- Integrated Demonstration are (1) characterizating radioactive and hazardous waste constituents, (2) determining the need and methodology for improving the stability of the waste form, (3) determining the performance requirements, (4) demonstrating barrier performance by instrumented field tests, natural analog studies, and modeling, (5) determining the need and method for destroying and stabilizing hazardous waste constituents, (6) developing and evaluating methods for retrieving, processing (pretreatment and treatment), and storing the waste on an interim basis, and (7) defining and evaluating waste packages, transportation options, and ultimate closure techniques including site restoration. The eventual objective is the transfer of new technologies as a system to full-scale remediation at the US Department of Energy complexes and sites in the private sector

  20. Stabilization of in-tank residual wastes and external tank soil contamination for the Hanford tank closure program: application to the AX tank farm

    Energy Technology Data Exchange (ETDEWEB)

    SONNICHSEN, J.C.

    1998-10-12

    Mixed high-level waste is currently stored in underground tanks at the US Department of Energy's (DOE's) Hanford Site. The plan is to retrieve the waste, process the water, and dispose of the waste in a manner that will provide less long-term health risk. The AX Tank Farm has been identified for purposes of demonstration. Not all the waste can be retrieved from the tanks and some waste has leaked from these tanks into the underlying soil. Retrieval of this waste could result in additional leakage. During FY1998, the Sandia National Laboratory was under contract to evaluate concepts for immobilizing the residual waste remaining in tanks and mitigating the migration of contaminants that exist in the soil column. Specifically, the scope of this evaluation included: development of a layered tank fill design for reducing water infiltration; development of in-tank getter technology; mitigation of soil contamination through grouting; sequestering of specific radionuclides in soil; and geochemical and hydrologic modeling of waste-water-soil interactions. A copy of the final report prepared by Sandia National Laboratory is attached.

  1. Estimating Residual Solids Volume In Underground Storage Tanks

    International Nuclear Information System (INIS)

    Clark, Jason L.; Worthy, S. Jason; Martin, Bruce A.; Tihey, John R.

    2014-01-01

    The Savannah River Site liquid waste system consists of multiple facilities to safely receive and store legacy radioactive waste, treat, and permanently dispose waste. The large underground storage tanks and associated equipment, known as the 'tank farms', include a complex interconnected transfer system which includes underground transfer pipelines and ancillary equipment to direct the flow of waste. The waste in the tanks is present in three forms: supernatant, sludge, and salt. The supernatant is a multi-component aqueous mixture, while sludge is a gel-like substance which consists of insoluble solids and entrapped supernatant. The waste from these tanks is retrieved and treated as sludge or salt. The high level (radioactive) fraction of the waste is vitrified into a glass waste form, while the low-level waste is immobilized in a cementitious grout waste form called saltstone. Once the waste is retrieved and processed, the tanks are closed via removing the bulk of the waste, chemical cleaning, heel removal, stabilizing remaining residuals with tailored grout formulations and severing/sealing external penetrations. The comprehensive liquid waste disposition system, currently managed by Savannah River Remediation, consists of 1) safe storage and retrieval of the waste as it is prepared for permanent disposition; (2) definition of the waste processing techniques utilized to separate the high-level waste fraction/low-level waste fraction; (3) disposition of LLW in saltstone; (4) disposition of the HLW in glass; and (5) closure state of the facilities, including tanks. This paper focuses on determining the effectiveness of waste removal campaigns through monitoring the volume of residual solids in the waste tanks. Volume estimates of the residual solids are performed by creating a map of the residual solids on the waste tank bottom using video and still digital images. The map is then used to calculate the volume of solids remaining in the waste tank. The ability to

  2. ENVIRONMENTAL MONITORING OF LEAKS USING TIME LAPSED LONG ELECTRODE ELECTRICAL RESISTIVITY

    International Nuclear Information System (INIS)

    Myers, D.A.; Rucker, D.F.; Fink, J.B.; Loke, M.H.

    2009-01-01

    Highly industrialized areas pose challenges for surface electrical resistivity characterization due to metallic infrastructure. The infrastructure is typically more conductive than the desired targets and will mask the deeper subsurface information. These challenges may be minimized if steel-cased wells are used as long electrodes in the area near the target. We demonstrate a method of using long electrodes to electrically monitor a simulated leak from an underground storage tank with both synthetic examples and a field demonstration. The synthetic examples place a simple target of varying electrical properties beneath a very low resistivity layer. The layer is meant to replicate the effects of infrastructure. Both surface and long electrodes are tested on the synthetic domain. The leak demonstration for the field experiment is simulated by injecting a high conductivity fluid in a perforated well within the S tank farm at Hanford, and the resistivity measurements are made before and after the leak test. All data are processed in four dimensions, where a regularization procedure is applied in both the time and space domains. The synthetic test case shows that the long electrode ERM could detect relative changes in resistivity that are commensurate with the differing target properties. The surface electrodes, on the other hand, had a more difficult time matching the original target's footprint. The field results shows a lowered resistivity feature develop south of the injection site after cessation of the injections. The time lapsed regularization parameter has a strong influence on the differences in inverted resistivity between the pre and post injection datasets, but the interpretation of the target is consistent across all values of the parameter. The long electrode ERM method may provide a tool for near real-time monitoring of leaking underground storage tanks.

  3. Decision and systems analysis for underground storage tank waste retrieval systems and tank waste remediation system

    International Nuclear Information System (INIS)

    Bitz, D.A.; Berry, D.L.; Jardine, L.J.

    1994-03-01

    Hanford's underground tanks (USTs) pose one of the most challenging hazardous and radioactive waste problems for the Department of Energy (DOE). Numerous schemes have been proposed for removing the waste from the USTs, but the technology options for doing this are largely unproven. To help assess the options, an Independent Review Group (IRG) was established to conduct a broad review of retrieval systems and the tank waste remediation system. The IRG consisted of the authors of this report

  4. Underground storage tank management plan, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    The Underground Storage Tank (UST) Program at the Oak Ridge Y-12 Plant was established to locate UST systems at the facility and to ensure that all operating UST systems are free of leaks. UST systems have been removed or upgraded in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance. With the closure of a significant portion of the USTs, the continuing mission of the UST Management Program is to manage the remaining active UST systems and continue corrective actions in a safe regulatory compliant manner. This Program outlines the compliance issues that must be addressed, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Program provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. The plan is divided into three major sections: (1) regulatory requirements, (2) active UST sites, and (3) out-of-service UST sites. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Program, and the procedures and guidance for compliance.

  5. Underground storage tank management plan, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-09-01

    The Underground Storage Tank (UST) Program at the Oak Ridge Y-12 Plant was established to locate UST systems at the facility and to ensure that all operating UST systems are free of leaks. UST systems have been removed or upgraded in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance. With the closure of a significant portion of the USTs, the continuing mission of the UST Management Program is to manage the remaining active UST systems and continue corrective actions in a safe regulatory compliant manner. This Program outlines the compliance issues that must be addressed, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Program provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. The plan is divided into three major sections: (1) regulatory requirements, (2) active UST sites, and (3) out-of-service UST sites. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Program, and the procedures and guidance for compliance

  6. Specialized video systems for use in underground storage tanks

    International Nuclear Information System (INIS)

    Heckendom, F.M.; Robinson, C.W.; Anderson, E.K.; Pardini, A.F.

    1994-01-01

    The Robotics Development Groups at the Savannah River Site and the Hanford site have developed remote video and photography systems for deployment in underground radioactive waste storage tanks at Department of Energy (DOE) sites as a part of the Office of Technology Development (OTD) program within DOE. Figure 1 shows the remote video/photography systems in a typical underground storage tank environment. Viewing and documenting the tank interiors and their associated annular spaces is an extremely valuable tool in characterizing their condition and contents and in controlling their remediation. Several specialized video/photography systems and robotic End Effectors have been fabricated that provide remote viewing and lighting. All are remotely deployable into and from the tank, and all viewing functions are remotely operated. Positioning all control components away from the facility prevents the potential for personnel exposure to radiation and contamination. Overview video systems, both monaural and stereo versions, include a camera, zoom lens, camera positioner, vertical deployment system, and positional feedback. Each independent video package can be inserted through a 100 mm (4 in.) diameter opening. A special attribute of these packages is their design to never get larger than the entry hole during operation and to be fully retrievable. The End Effector systems will be deployed on the large robotic Light Duty Utility Arm (LDUA) being developed by other portions of the OTD-DOE programs. The systems implement a multi-functional ''over the coax'' design that uses a single coaxial cable for all data and control signals over the more than 900 foot cable (or fiber optic) link

  7. 100-N Area underground storage tank closures

    Energy Technology Data Exchange (ETDEWEB)

    Rowley, C.A.

    1993-08-01

    This report describes the removal/characterization actions concerning underground storage tanks (UST) at the 100-N Area. Included are 105-N-LFT, 182-N-1-DT, 182-N-2-DT, 182-N-3-DT, 100-N-SS-27, and 100-N-SS-28. The text of this report gives a summary of remedial activities. In addition, correspondence relating to UST closures can be found in Appendix B. Appendix C contains copies of Unusual Occurrence Reports, and validated sampling data results comprise Appendix D.

  8. 100-N Area underground storage tank closures

    International Nuclear Information System (INIS)

    Rowley, C.A.

    1993-01-01

    This report describes the removal/characterization actions concerning underground storage tanks (UST) at the 100-N Area. Included are 105-N-LFT, 182-N-1-DT, 182-N-2-DT, 182-N-3-DT, 100-N-SS-27, and 100-N-SS-28. The text of this report gives a summary of remedial activities. In addition, correspondence relating to UST closures can be found in Appendix B. Appendix C contains copies of Unusual Occurrence Reports, and validated sampling data results comprise Appendix D

  9. Viewing Systems for Large Underground Storage Tanks

    International Nuclear Information System (INIS)

    Heckendorn, F.M.; Robinson, C.W.; Anderson, E.K.; Pardini, A.F.

    1996-01-01

    Specialized remote video systems have been successfully developed and deployed in a number of large radiological Underground Storage Tanks (USTs)that tolerate the hostile tank interior, while providing high resolution video to a remotely located operator. The deployment is through 100 mm (4 in) tank openings, while incorporating full video functions of the camera, lights, and zoom lens. The usage of remote video minimizes the potential for personnel exposure to radiological and hazardous conditions, and maximizes the quality of the visual data used to assess the interior conditions of both tank and contents. The robustness of this type of remote system has a direct effect on the potential for radiological exposure that personnel may encounter. The USTs typical of the Savannah River and Hanford Department Of Energy - (DOE) sites are typically 4.5 million liter (1.2 million gal) units under earth. or concrete overburden with limited openings to the surface. The interior is both highly contaminated and radioactive with a wide variety of nuclear processing waste material. Some of the tanks are -flammable rated -to Class 1, Division 1,and personnel presence at or near the openings should be minimized. The interior of these USTs must be assessed periodically as part of the ongoing management of the tanks and as a step towards tank remediation. The systems are unique in their deployment technology, which virtually eliminates the potential for entrapment in a tank, and their ability to withstand flammable environments. A multiplicity of components used within a common packaging allow for cost effective and appropriate levels of technology, with radiation hardened components on some units and lesser requirements on other units. All units are completely self contained for video, zoom lens, lighting, deployment,as well as being self purging, and modular in construction

  10. Regulatory analysis of the Underground Storage Tank-Integrated Demonstration Program

    International Nuclear Information System (INIS)

    Smith, E.H.

    1992-01-01

    The Underground Storage Tank-Integrated Demonstration (UST-ID) Program has been developed to identify, demonstrate, test, and evaluate technologies that will provide alternatives to the current underground storage tank remediation program. The UST-ID Program is a national program that consists of five participating US Department of Energy (DOE) sites where technologies can be developed an ultimately demonstrated. Once these technologies are demonstrated, the UST-ID Program will transfer the developed technology system to industry (governmental or industrial) for application or back to Research and Development for further evaluation and modification, as necessary. In order to ensure that the UST-ID Program proceeds without interruption, it will be necessary to identify regulatory requirements along with associated permitting and notification requirements early in the technology development process. This document serves as a baseline for identifying certain federal and state regulatory requirements that may impact the UST-ID Program and the demonstration of any identified technologies

  11. T Tank Farm Interim Surface Barrier Demonstration--Vadose Zone Monitoring Plan

    International Nuclear Information System (INIS)

    Zhang, Z. F.; Keller, Jason M.; Strickland, Christopher E.

    2007-01-01

    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 in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim barrier on the surface. Such a barrier is expected to prevent infiltrating water from reaching the plume and moving it further. A plan has been prepared to monitor and determine the effectiveness of the interim surface barrier. Soil water content and water pressure will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests were installed. Each instrument nest contains a neutron probe access tube, a capacitance probe, four heat-dissipation units, and a drain gauge to measure soil water flux. A meteorological station has been installed outside of the fence. In fiscal year 2007, two additional instrument nests are planned to be installed beneath the proposed barrier.

  12. Waste Tank Corrosion Program at Savannah River Site

    International Nuclear Information System (INIS)

    Chandler, J.R.; Hsu, T.C.; Hobbs, D.T.; Iyer, N.C.; Marra, J.E.; Zapp, P.E.

    1993-01-01

    The Savannah River Site (SRS) has approximately 30 million gallons of high level radioactive waste stored in 51 underground tanks. SRS has maintained an active corrosion research and corrosion control and monitoring program throughout the operating history of SRS nuclear waste storage tanks. This program is largely responsible for the successful waste storage experience at SRS. The program has consisted of extensive monitoring of the tanks and surrounding environment for evidence of leaks, extensive research to understand the potential corrosion processes, and development and implementation of corrosion chemistry control. Current issues associated with waste tank corrosion are primarily focused on waste processing operations and are being addressed by a number of active programs and initiatives

  13. T-TY Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring Plan

    International Nuclear Information System (INIS)

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

    2010-01-01

    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 Energy's 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.

  14. Preliminary proposed seismic design and evaluation criteria for new and existing underground hazardous materials storage tanks

    International Nuclear Information System (INIS)

    Kennedy, R.P.

    1991-01-01

    The document provides a recommended set of deterministic seismic design and evaluation criteria for either new or existing underground hazardous materials storage tanks placed in either the high hazard or moderate hazard usage catagories of UCRL-15910. The criteria given herein are consistent with and follow the same philosophy as those given in UCRL-15910 for the US Department of Energy facilities. This document is intended to supplement and amplify upon Reference 1 for underground hazardous materials storage tanks

  15. An assessment of underground and aboveground steam system failures in the SRS waste tank farms

    International Nuclear Information System (INIS)

    Hsu, T.C.; Shurrab, M.S.; Wiersma, B.J.

    1997-01-01

    Underground steam system failures in waste tank farms at the Savannah River Site (SRS) increased significantly in the 3--4 year period prior to 1995. The primary safety issues created by the failures were the formation of sub-surface voids in soil and the loss of steam jet transfer and waste evaporation capability, and the loss of heating and ventilation to the tanks. The average annual cost for excavation and repair of the underground steam system was estimated to be several million dollars. These factors prompted engineering personnel to re-consider long-term solutions to the problem. The primary cause of these failures was the inadequate thermal insulation utilized for steam lines associated with older tanks. The failure mechanisms were either pitting or localized general corrosion on the exterior of the pipe beneath the thermal insulation. The most realistic and practical solution is to replace the underground lines by installing aboveground steam systems, although this option will incur significant initial capital costs. Steam system components, installed aboveground in other areas of the tank farms have experienced few failures, while in continuous use. As a result, piecewise installation of temporary aboveground steam systems have been implemented in F-area whenever opportunities, i.e., failures, present themselves

  16. Estimated inventory of chemicals added to underground waste tanks, 1944--1975

    International Nuclear Information System (INIS)

    Allen, G.K.

    1976-03-01

    The five major chemical processes, the Bismuth Phosphate process, the Uranium Recovery process, the Redox process, the Purex process, and the Waste Fractionization process have each contributed to give the total Hanford waste chemicals. Each of these processes is studied to determine the total estimated chemicals stored in underground waste tanks. The chemical contents are derived mainly from flowsheet compositions and recorded waste volumes sent to underground storage. The major components and amounts of Hanford waste are sodium hydroxide, 230 million gram-moles (20 million pounds), sodium nitrate, 1400 million gram-moles (270 million pounds), sodium nitrite, 220 million gram-moles (34 million pounds), sodium aluminate, 400 million gram-moles (72 million pounds), and sodium phosphate, 87 million gram-moles (31 million pounds). Chemical analyses of the sludge and salt cake samples are tabulated to determine the chemical characteristics of the solids. A relative chemical toxicity of the Hanford underground waste tank chemicals is developed from maximum permissible chemical concentrations in air and water. The most toxic chemicals are assumed to be sodium phosphate--35%, sodium aluminate--28%, and chromium hydroxide--19%. If air standards set toxicity limits, the most toxic chemicals are bismuth--41%, chromium hydroxide--23%, and fluoride--10%

  17. Development of simulated tank wastes for the US Department of Energy's Underground Storage Tank Integrated Demonstration

    International Nuclear Information System (INIS)

    Elmore, M.R.; Colton, N.G.; Jones, E.O.

    1992-08-01

    The purpose of the Underground Storage Tank Integrated Demonstration (USTID) is to identify and evaluate technologies that may be used to characterize, retrieve, treat, and dispose of hazardous and radioactive wastes contained in tanks on US Department of Energy sites. Simulated wastes are an essential component of the evaluation process because they provide controlled samples for technology assessment, and minimize costs and risks involved when working with radioactive wastes. Pacific Northwest Laboratory has developed a recipe to simulate Hanford single-shell tank, (SST) waste. The recipe is derived from existing process recipes, and elemental concentrations are based on characterization data from 18 SSTs. In this procedure, salt cake and metal oxide/hydroxide sludge are prepared individually, and mixed together at varying ratios depending on the specific tank, waste to be simulated or the test being conducted. Elemental and physical properties of the stimulant are comparable with analyzed tank samples, and chemical speciation in the simulant is being improved as speciation data for actual wastes become available. The nonradioactive chemical waste simulant described here is useful for testing technologies on a small scale

  18. Structural evaluations of existing underground reinforced concrete tanks for radioactive waste storage

    International Nuclear Information System (INIS)

    Vollert, F.R.

    1979-10-01

    Structural integrity evaluations are being conducted for underground, steel-lined reinforced concrete tanks for storing radioactive wastes. The tanks sustain large soil overburden loads and elevated temperatures from the waste for long time periods. The evaluations include laboratory experiments to determine the long-term effects of elevated temperatures on the elastic properties of concrete, and to estimate the effect of the waste chemicals on concrete durability. Available concrete samples from the tanks were also tested to determine the quality of the concrete in the tanks and for comparison with the laboratory data. Finite element, nonlinear, time-dependent analyses are performed to show the thermal creep, cracking, and stresses occurring in the concrete tanks due to the service conditions. Ultimate load analyses are made to assess the safety margin in the tanks. Finally, seismic analyses of a tank in the stressed condition due to the soil and thermal loadings were conducted to determine that the structure has sufficient reserve capacity to withstand 0.25 g earthquake accelerations

  19. Structural analysis of ORNL underground gunite waste storage tanks

    International Nuclear Information System (INIS)

    Fricke, K.E.

    1995-01-01

    The North Tank Farm (NTF) and the South Tank Farm (STF) located at ORNL contains 8 underground waste storage tanks which were built around 1943. The tanks were used to collect and store the liquid portion of the radioactive and/or hazardous chemical wastes produced as part of normal facility operations at ORNL, but are no longer part of the active Low Level Liquid Waste system of the Laboratory. The tanks were constructed of gunite. The six STF tanks are 50 ft in diameter, and have a 12 ft sidewall, and an arched dome rising another 6.25 ft. The sidewall are 6 in. thick and have an additional 1.5 in. gunite liner on the inside. There is a thickened ring at the wall-dome juncture. The dome consists of two 5 in. layers of gunite. The two tanks in the NTF are similar, but smaller, having a 25 ft diameter, no inner liner, and a dome thickness of 3.5 in. Both sets of tanks have welded wire mesh and vertical rebars in the walls, welded wire mesh in the domes, and horizontal reinforcing hoop bars pre-tensioned to 35 to 40 ksi stress in the walls and thickened ring. The eight tanks are entirely buried under a 6 ft layer of soil cover. The present condition of the tanks is not accurately known, since access to them is extremely limited. In order to evaluate the structural capability of the tanks, a finite element analysis of each size tank was performed. Both static and seismic loads were considered. Three sludge levels, empty, half-full, and full were evaluated. In the STF analysis, the effects of wall deterioration and group spacing were evaluated. These analyses found that the weakest element in the tanks is the steel resisting the circumferential (or hoop) forces in the dome ring, a fact verified separately by an independent reviewer. However, the hoop steel has an adequate demand/capacity ratio. Buckling of the dome and the tank walls is not a concern

  20. Nationwide survey, assessment, and replacement designs of tank systems at 430 emergency broadcast stations

    International Nuclear Information System (INIS)

    Maraj, R.; Whitaker-Sheppard, L.

    1994-01-01

    The Federal Emergency Management Agency (FEMA), acting on behalf of the Federal Communications Commission (FCC), undertook a program to bring into compliance federally-owned underground storage tanks (USTs) at radio and television stations, which are part of the Broadcast Station Protection Program (BSPP) of the Emergency Broadcast System (EBS). These USTs supply fuel (diesel and gasoline) to emergency generators and are located on private property. Woodward-Clyde Federal Services is under contract with FEMA to provide assistance in all phases of the program. The BSPP is designed to protect selected stations that are participants in the EBS, which support emergency preparedness and response operations. Technical standards for installation, spill and overfill protection, corrosion protection, and leak detection for underground storage tanks (UST) were promulgated by the EPA, as described in 53 Federal Register 37082 (September 23, 1988). December 1998 was established as a compliance data for corrosion protection and spill/overfill protection. A compliance period of December 1989 to December 1993 was established for leak detection devices, depending on the UST installation date. Several states have promulgated underground storage tank regulations that are more stringent than the federal requirements. Local agencies in several states may have additional UST requirements. All federal, state, and local UST requirements must be satisfied under a compliance program. The approach and methodology employed by FEMA are presented

  1. A TDR-based system for the localization of leaks in newly installed, underground pipes made of any material

    International Nuclear Information System (INIS)

    Cataldo, A; Cannazza, G; De Benedetto, E; Giaquinto, N

    2012-01-01

    In this paper, a time domain reflectometry-based system for locating leaks in underground pipes (made of any material) is presented. The proposed system simply requires that a biwire should be attached to the pipe (all along its length), at the time of installation. Basically, the biwire acts as a permanent sensing element that can be connected to the measurement instrument whenever it is necessary to check for the presence of leaks. It is worth emphasizing that such a simple and low-cost system could tremendously facilitate leak detection not only in water distribution systems but also in wastewater/sewer pipelines. The proposed system was validated through measurements on a newly installed pilot plant, in which a leak was intentionally provoked. (paper)

  2. Acoustic imaging of underground storage tank wastes: A feasibility study. Final report

    International Nuclear Information System (INIS)

    Turpening, R.; Zhu, Z.; Caravana, C.; Matarese, J.

    1995-01-01

    The objectives for this underground storage tank (UST) imaging investigation are: (1) to assess the feasibility of using acoustic methods in UST wastes, if shown to be feasible, develop and assess imaging strategies; (2) to assess the validity of using chemical simulants for the development of acoustic methods and equipment. This investigation examined the velocity of surrogates, both salt cake and sludge surrogates. In addition collected seismic cross well data in a real tank (114-TX) on the Hanford Reservation. Lastly, drawing on the knowledge of the simulants and the estimates of the velocities of the waste in tank 114-TX the authors generated a hypothetical model of waste in a tank and showed that non-linear travel time tomographic imaging would faithfully image that stratigraphy

  3. Leak testing plan for the Oak Ridge National Laboratory liquid low- level waste system (active tanks)

    International Nuclear Information System (INIS)

    Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.

    1992-06-01

    A leak testing plan for a portion of the Liquid Low-Level Waste (LLLW) system at the Oak Ridge National Laboratory (ORNL) is provided in the two volumes that form this document. This plan was prepared in response to the requirements of the Federal Facilities Agreement (FFA) between the US Department of Energy and two other agencies, the US Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC). The effective date of this agreement was 1 January 1992. The LLLW system is an interconnected complex of tanks and pipelines. The FFA distinguishes four different categories of tank and pipeline systems within this complex: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA's specific requirements for leak testing of the Category C systems is addressed in this plan. The plan also addresses leak testing of the Category B portions of the LLLW system. Leak testing of the Category B components was brought into the plan to supplement the secondary containment design demonstration effort that is under way for these components

  4. Underground radioactive waste tank remote inspection and sampling

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  5. RCRA corrective action for underground storage tanks -- Subtitle C for Subtitle I

    International Nuclear Information System (INIS)

    1995-08-01

    The purpose of this report is to provide guidance to DOE and DOE contractor personnel responsible for planning and implementation of corrective measures addressing cleanup of releases of hazardous materials or regulated substances from underground storage tanks regulated under RCRA Subtitle C or Subtitle I

  6. Stochastic Consequence Analysis for Waste Leaks

    International Nuclear Information System (INIS)

    HEY, B.E.

    2000-01-01

    This analysis evaluates the radiological consequences of potential Hanford Tank Farm waste transfer leaks. These include ex-tank leaks into structures, underneath the soil, and exposed to the atmosphere. It also includes potential misroutes, tank overflow

  7. Tank 241-AY-102 Leak Assessment Supporting Documentation: Miscellaneous Reports, Letters, Memoranda, And Data

    Energy Technology Data Exchange (ETDEWEB)

    Engeman, J. K.; Girardot, C. L.; Harlow, D. G.; Rosenkrance, C. L.

    2012-12-20

    This report contains reference materials cited in RPP-ASMT -53793, Tank 241-AY-102 Leak Assessment Report, that were obtained from the National Archives Federal Records Repository in Seattle, Washington, or from other sources including the Hanford Site's Integrated Data Management System database (IDMS).

  8. Tank 241-AY-102 Leak Assessment Supporting Documentation: Miscellaneous Reports, Letters, Memoranda, And Data

    International Nuclear Information System (INIS)

    Engeman, J. K.; Girardot, C. L.; Harlow, D. G.; Rosenkrance, C. L.

    2012-01-01

    This report contains reference materials cited in RPP-ASMT -53793, Tank 241-AY-102 Leak Assessment Report, that were obtained from the National Archives Federal Records Repository in Seattle, Washington, or from other sources including the Hanford Site's Integrated Data Management System database (IDMS)

  9. Estimating heel retrieval costs for underground storage tank waste at Hanford. Draft

    International Nuclear Information System (INIS)

    DeMuth, S.

    1996-01-01

    Approximately 100 million gallons (∼400,000 m 3 ) of existing U.S. Department of Energy (DOE) owned radioactive waste stored in underground tanks can not be disposed of as low-level waste (LLW). The current plan for disposal of UST waste which can not be disposed of as LLW is immobilization as glass and permanent storage in an underground repository. Disposal of LLW generally can be done sub-surface at the point of origin. Consequently, LLW is significantly less expensive to dispose of than that requiring an underground repository. Due to the lower cost for LLW disposal, it is advantageous to separate the 100 million gallons of waste into a small volume of high-level waste (HLW) and a large volume of LLW

  10. A survey of existing and emerging technologies for external detection of liquid leaks at the Hanford Site

    International Nuclear Information System (INIS)

    Lewis, R.E.; Teel, S.S.

    1994-10-01

    During the history of the Hanford Site, many structures were built that stored and transported liquids used for the production mission; some of these structures are still active. Active structures include underground storage tanks retention basins, and pipes and pipelines. Many of the liquids stored and transported in these structures are potentially hazardous to human health and the environment. Any leakage of liquids from active structures, has the added potential to mobilize contaminants in the unsaturated zone. Therefore, it is beneficial to monitor these structures for leaks. The purpose of tills report is to catalog existing and emerging technologies that have potential for the external monitoring of liquid leaks. The report will focus primarily on the needs at the Hanford Site tank farms that are located in the 200 Areas, but will also be relevant to other Hanford Site facilities. Leak detection systems, both external and internal, are currently used at some Hanford facilities. This report focuses on the detection of leaks as they migrate into the soils surrounding the facilities

  11. Underground storage tanks soft waste dislodging and conveyance

    International Nuclear Information System (INIS)

    Wellner, A.F.

    1993-10-01

    Currently 140 million liters (37 million gallons) of waste are stored in the single shell underground storage tanks (SSTs) at Hanford. The wastes contain both hazardous and radioactive constituents. This paper focuses on the Westinghouse Hanford Company's testing program for soft waste dislodging and conveyance technology. This program was initialized to investigate methods of dislodging and conveying soft waste. The main focus was on using air jets, water jets, and/or mechanical blades to dislodge the waste and air conveyance to convey the dislodged waste. These waste dislodging and conveyance technologies would be used in conjunction with a manipulator based retrieval system

  12. Closure Report for Underground Storage Tank 2310-U at the Pine Ridge West Repeater Station

    International Nuclear Information System (INIS)

    1994-07-01

    This document represents the Closure Report for Underground Storage Tank (UST) 2310-U at the Pine Ridge West Repeater Station, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2310-U was a 200-gal gasoline UST which serviced the emergency generator at the Repeater Station. The tank was situated in a shallow tank bay adjacent to the Repeater Station along the crest of Pine Ridge. The tank failed a tightness test in October 1989 and was removed in November 1989. The purpose of this report is to document completion of soil corrective action, present supporting analytical data, and request closure for this site

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

    International Nuclear Information System (INIS)

    Nance, T.A.

    1998-01-01

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

  14. Underground storage tank integrated demonstration: Evaluation of pretreatment options for Hanford tank wastes

    International Nuclear Information System (INIS)

    Lumetta, G.J.; Wagner, M.J.; Colton, N.G.; Jones, E.O.

    1993-06-01

    Separation science plays a central role inn the pretreatment and disposal of nuclear wastes. The potential benefits of applying chemical separations in the pretreatment of the radioactive wastes stored at the various US Department of Energy sites cover both economic and environmental incentives. This is especially true at the Hanford Site, where the huge volume (>60 Mgal) of radioactive wastes stored in underground tanks could be partitioned into a very small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). The cost associated with vitrifying and disposing of just the HLW fraction in a geologic repository would be much less than those associated with vitrifying and disposing of all the wastes directly. Futhermore, the quality of the LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. In this report, we present the results of an evaluation of the pretreatment options for sludge taken from two different single-shell tanks at the Hanford Site-Tanks 241-B-110 and 241-U-110 (referred to as B-110 and U-110, respectively). The pretreatment options examined for these wastes included (1) leaching of transuranic (TRU) elements from the sludge, and (2) dissolution of the sludge followed by extraction of TRUs and 90 Sr. In addition, the TRU leaching approach was examined for a third tank waste type, neutralized cladding removal waste

  15. Risk assessment methodology for Hanford high-level waste tanks

    International Nuclear Information System (INIS)

    Bott, T.F.; Mac Farlane, D.R.; Stack, D.W.; Kindinger, J.

    1992-01-01

    A methodology is presented for applying Probabilistic Safety Assessment techniques to quantification of the health risks posed by the high-level waste (HLW) underground tanks at the Department of Energy's Hanford reservation. This methodology includes hazard screening development of a list of potential accident initiators, systems fault trees development and quantification, definition of source terms for various release categories, and estimation of health consequences from the releases. Both airborne and liquid pathway releases to the environment, arising from aerosol and spill/leak releases from the tanks, are included in the release categories. The proposed methodology is intended to be applied to a representative subset of the total of 177 tanks, thereby providing a baseline risk profile for the HLW tank farm that can be used for setting clean-up/remediation priorities. Some preliminary results are presented for Tank 101-SY

  16. T Tank Farm Interim Cover Test - Design Plan

    International Nuclear Information System (INIS)

    Zhang, Z. F.; Keller, Jason M.

    2006-01-01

    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 in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim cover on the surface. Such a cover is expected to prevent infiltrating water from reaching the plume and moving it further. Pacific Northwest National Laboratory has prepared a design plan to monitor and determine the effectiveness of the interim cover. A three-dimensional numerical simulation of water movement beneath a cover was conducted to guide the design of the plan. Soil water content, water pressure, and temperature will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests will be installed, one inside and one outside of the proposed cover. In fiscal year 2007, two additional instrument nests, both inside the proposed cover, will be installed. Each instrument nest contains a neutron access tube and a capacitance probe (to measure water content), and four heat-dissipation units (to measure pressure head and temperature). A datalogger and a meteorological station will be installed outside of the fence. Two drain gauges will be installed in locations inside and outside the cover for the purpose of measuring soil water flux.

  17. Detailed leak detection test plan and schedule for the Oak Ridge National Laboratory LLLW active tanks

    International Nuclear Information System (INIS)

    Douglas, D.G.; Maresca, J.W. Jr.

    1993-03-01

    This document provides a detailed leak detection test plan and schedule for leak testing many of the tanks that comprise the active portion of the liquid low-level waste (LLLW) system at the Oak Ridge National Laboratory (ORNL). This plan was prepared in response to the requirements of the Federal Facility Agreement (FFA) between the US Department of Energy (DOE) and two other agencies, the US Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC)

  18. Detection of leaks in underground storage tanks using electrical resistance methods: 1996 results

    International Nuclear Information System (INIS)

    Ramirez, A.; Daily, W.

    1996-10-01

    This document provides a summary of a field experiment performed under a 15m diameter steel tank mockup located at the Hanford Reservation, Washington. The purpose of this test was to image a contaminant plume as it develops in soil under a tank already contaminated by previous leakage and to determine whether contaminant plumes can be detected without the benefit of background data. Measurements of electrical resistance were made before and during a salt water release. These measurements were made in soil which contained the remnants of salt water plumes released during previous tests in 1994 and in 1995. About 11,150 liters of saline solution were released along a portion of the tank's edge in 1996. Changes in electrical resistivity due to release of salt water conducted in 1996 were determined in two ways: (1) changes relative to the 1996 pre-spill data, and (2) changes relative to data collected near the middle of the 1996 spill after the release flow rate was increased. In both cases, the observed resistivity changes show clearly defined anomalies caused by the salt water release. These results indicate that when a plume develops over an existing plume and in a geologic environment similar to the test site environment, the resulting resistivity changes are easily detectable. Three dimensional tomographs of the resistivity of the soil under the tank show that the salt water release caused a region of low soil resistivity which can be observed directly without the benefit of comparing the tomograph to tomographs or data collected before the spill started. This means that it may be possible to infer the presence of pre-existing plumes if there is other data showing that the regions of low resistivity are correlated with the presence of contaminated soil. However, this approach does not appear reliable in defining the total extent of the plume due to the confounding effect that natural heterogeneity has on our ability to define the margins of the anomaly

  19. Los Alamos National Laboratory environmental restoration program group audit report for underground storage tank removal: Audit ER-92- 04, July 22--August 11, 1992

    International Nuclear Information System (INIS)

    Gillespie, P.F.

    1992-01-01

    Audit ER-92-04 was conducted on activities being performed by Waste Management (EM-7), Environmental Protection (EM-8), and Environmental Restoration (EM-13) groups for the LANL's underground storage tank removal program. Scope of the audit was limited to an evaluation of the implementation of the State of New Mexico requirements for underground storage-tank removal. Activities were evaluated using requirements specified in the State of New Mexico Environmental Improvement Board Underground Storage Tank Regulations, EIB/USTR. Two recommendations are made: (1) that a single organization be given the responsibility and authority for the implementation of the program, and (2) that the requirements of the NM State environmental improvement board underground storage tank regulations be reviewed and a Los Alamos procedure written to address requirements and interfaces not contained in SOP-EM7-D ampersand D-001

  20. Evaluation of pipeline leak detection systems

    International Nuclear Information System (INIS)

    Glauz, W.D.; Flora, J.D.; Hennon, G.J.

    1993-01-01

    Leaking underground storage tank system presents an environmental concern and a potential health hazard. It is well known that leaks in the piping associated with these systems account for a sizeable fraction of the leaks. EPA has established performance standards for pipeline leak detection systems, and published a document presenting test protocols for evaluating these systems against the standards. This paper discusses a number of facets and important features of evaluating such systems, and presents results from tests of several systems. The importance of temperature differences between the ground and the product in the line is shown both in theory and with test data. The impact of the amount of soil moisture present is addressed, along with the effect of frozen soil. These features are addressed both for line tightness test systems, which must detect leaks of 0.10 gal/h (0.38 L/h) at 150% of normal line pressure, or 0.20 gal/h (0.76 L/h) at normal line pressure, and for automatic line leak detectors that must detect leaks of 3 gal/h (11 L/h) at 10 psi (69 kPa) within an hour of the occurrence of the leak. This paper also addresses some statistical aspects of the evaluation of these systems. Reasons for keeping the evaluation process ''blind'' to the evaluated company are given, along with methods for assuring that the tests are blind. Most importantly, a test procedure is presented for evaluating systems that report a flow rate (not just a pass/fail decision) that is much more efficient than the procedure presented in the EPA protocol, and is just as stringent

  1. The underground storage tank is the key; Der Speicher ist der Schluessel

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Jens-Peter

    2013-08-06

    Plus energy houses also succeed withoutpassive house insulation. Because the combination of solar collectors, ventilation and heat pump achieves excellent energy efficiency, if one preserves the solar heat in an underground storage tank. [German] Plusenergiehaeuser gelingen auch ohne Passivhausdaemmung. Denn die Kombination von Sonnenkollektoren, Lueftung und Waermepumpe erreicht eine ausgezeichnete energetische Effizienz, sofern man die Solarwaerme in einem Erdspeicher konserviert.

  2. Assessment of concentration mechanisms for organic wastes in underground storage tanks at Hanford

    International Nuclear Information System (INIS)

    Gerber, M.A.; Burger, L.L.; Nelson, D.A.; Ryan, J.L.; Zollars, R.L.

    1992-09-01

    Pacific Northwest Laboratory (PNL) has conducted an initial conservative evaluation of physical and chemical processes that could lead to significant localized concentrations of organic waste constituents in the Hanford underground storage tanks (USTs). This evaluation was part of ongoing studies at Hanford to assess potential safety risks associated with USTs containing organics. Organics in the tanks could pose a potential problem if localized concentrations are high enough to propagate combustion and are in sufficient quantity to produce a large heat and/or gas release if in contact with a suitable oxidant. The major sources of oxidants are oxygen in the overhead gas space of the tanks and sodium nitrate and nitrite either as salt cake solids or dissolved in the supernatant and interstitial liquids

  3. Assessment of concentration mechanisms for organic wastes in underground storage tanks at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.A.; Burger, L.L.; Nelson, D.A.; Ryan, J.L. (Pacific Northwest Lab., Richland, WA (United States)); Zollars, R.L. (Washington State Univ., Pullman, WA (United States))

    1992-09-01

    Pacific Northwest Laboratory (PNL) has conducted an initial conservative evaluation of physical and chemical processes that could lead to significant localized concentrations of organic waste constituents in the Hanford underground storage tanks (USTs). This evaluation was part of ongoing studies at Hanford to assess potential safety risks associated with USTs containing organics. Organics in the tanks could pose a potential problem if localized concentrations are high enough to propagate combustion and are in sufficient quantity to produce a large heat and/or gas release if in contact with a suitable oxidant. The major sources of oxidants are oxygen in the overhead gas space of the tanks and sodium nitrate and nitrite either as salt cake solids or dissolved in the supernatant and interstitial liquids.

  4. Development of in-structure design spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Julyk, L.J.

    1995-09-01

    In-structure response spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site are developed on the basis of recent soil-structure-interaction analyses. Recommended design spectra are provided for various locations on the tank dome

  5. Structural Dimensions, Fabrication, Materials, and Operational History for Types I and II Waste Tanks

    International Nuclear Information System (INIS)

    Wiersma, B.J.

    2000-01-01

    Radioactive waste is confined in 48 underground storage tanks at the Savannah River Site. The waste will eventually be processed and transferred to other site facilities for stabilization. Based on waste removal and processing schedules, many of the tanks, including those with flaws and/or defects, will be required to be in service for another 15 to 20 years. Until the waste is removed from storage, transferred, and processed, the materials and structures of the tanks must maintain a confinement function by providing a leak-tight barrier to the environment and by maintaining acceptable structural stability during design basis event which include loading from both normal service and abnormal conditions

  6. ROBOTIC TANK INSPECTION END EFFECTOR

    International Nuclear Information System (INIS)

    Rachel Landry

    1999-01-01

    The objective of this contract between Oceaneering Space Systems (OSS) and the Department of Energy (DOE) was to provide a tool for the DOE to inspect the inside tank walls of underground radioactive waste storage tanks in their tank farms. Some of these tanks are suspected to have leaks, but the harsh nature of the environment within the tanks precludes human inspection of tank walls. As a result of these conditions only a few inspection methods can fulfill this task. Of the methods available, OSS chose to pursue Alternating Current Field Measurement (ACFM), because it does not require clean surfaces for inspection, nor any contact with the Surface being inspected, and introduces no extra by-products in the inspection process (no coupling fluids or residues are left behind). The tool produced by OSS is the Robotic Tank Inspection End Effector (RTIEE), which is initially deployed on the tip of the Light Duty Utility Arm (LDUA). The RTEE combines ACFM with a color video camera for both electromagnetic and visual inspection The complete package consists of an end effector, its corresponding electronics and software, and a user's manual to guide the operator through an inspection. The system has both coarse and fine inspection modes and allows the user to catalog defects and suspected areas of leakage in a database for further examination, which may lead to emptying the tank for repair, decommissioning, etc.. The following is an updated report to OSS document OSS-21100-7002, which was submitted in 1995. During the course of the contract, two related sub-tasks arose, the Wall and Coating Thickness Sensor and the Vacuum Scarifying and Sampling Tool Assembly. The first of these sub-tasks was intended to evaluate the corrosion and wall thinning of 55-gallon steel drums. The second was retrieved and characterized the waste material trapped inside the annulus region of the underground tanks on the DOE's tank farms. While these sub-tasks were derived from the original intent

  7. 1999 Leak Detection, Monitoring, and Mitigation Strategy Update

    International Nuclear Information System (INIS)

    OHL, P.C.

    1999-01-01

    This document is a complete revision of WHC-SD-WM-ES-378, Rev 1. This update includes recent developments in Leak Detection, Leak Monitoring, and Leak Mitigation technologies, as well as, recent developments in single-shell tank retrieval technologies. In addition, a single-shell tank retrieval release protection strategy is presented

  8. Using virtual objects to aid underground storage tank teleoperation

    International Nuclear Information System (INIS)

    Anderson, R.J.; Davies, B.

    1994-01-01

    In this paper we describe an algorithm by which obstructions and surface features in an underground storage tank can be modeled and used to generate virtual barrier function for a real-time telerobotic system, which provides an aid to the operator for both real-time obstacle avoidance and for surface tracking. The algorithm requires that the slave's tool and every object in the waste storage tank be decomposed into convex polyhedral primitives, with the waste surface modeled by triangular prisms. Intrusion distance and extraction vectors are then derived at every time step by applying Gilbert's polyhedra distance algorithm, which has been adapted for the task. This information is then used to determine the compression and location of nonlinear virtual spring-dampers whose total force is summed and applied to the manipulator/teleoperator system. Experimental results using a PUMA 560 and a simulated waste surface validate the approach, showing that it is possible to compute the algorithm and generate smooth, realistic pseudo forces for the teleoperator system using standard VME bus hardware

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

    International Nuclear Information System (INIS)

    Cox, D. H.

    2000-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    D. H. Cox

    2000-07-01

    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.

  11. High water level installation of monitoring wells for underground storage tanks

    International Nuclear Information System (INIS)

    Treadway, C.

    1990-01-01

    This paper briefly describes a common monitoring well installation design for shallow ground water contamination resulting from leaky underground storage tanks. The paper describes drilling techniques used in unconsolidated Florida aquifers using hollow-stem augers. It describes methods for the prevention of heaving sands and sand-locking problems. It then goes on to describe the proper well casing placement and sealing techniques using neat cements. The proper sell screen level is also discussed to maximize the detection of floating hydrocarbons

  12. LEAK: A source term generator for evaluating release rates from leaking vessels

    International Nuclear Information System (INIS)

    Clinton, J.H.

    1994-01-01

    An interactive computer code for estimating the rate of release of any one of several materials from a leaking tank or broken pipe leading from a tank is presented. It is generally assumed that the material in the tank is liquid. Materials included in the data base are acetonitrile, ammonia, carbon tetrachloride, chlorine, chlorine trifluoride, fluorine, hydrogen fluoride, nitric acid, nitrogen tetroxide, sodium hydroxide, sulfur hexafluoride, sulfuric acid, and uranium hexafluoride. Materials that exist only as liquid and/or vapor over expected ranges of temperature and pressure can easily be added to the data base file. The Fortran source code for LEAK and the data file are included with this report

  13. 40 CFR Appendix A to Part 282 - State Requirements Incorporated by Reference in Part 282 of the Code of Federal Regulations

    Science.gov (United States)

    2010-07-01

    ... 2195Underground Storage Tank Trust Fund Section 2195.1Underground Motor Fuel Storage Tank Remediation Agreements... Vessels Section 9.07(F)—Response to Leaks Section 9.07(G)—Tank Repair and Relining Section 9.07(H)—Tanks... ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) APPROVED UNDERGROUND STORAGE TANK PROGRAMS...

  14. Safety issue resolution strategy plan for inactive miscellaneous underground storage tanks

    International Nuclear Information System (INIS)

    Wang, O.S.; Powers, T.B.

    1994-09-01

    The purpose of this strategy plan is to identify, confirm, and resolve safely issues associated with inactive miscellaneous underground storage tanks (MUSTs) using a risk-based priority approach. 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 including risk ranking and cost effectiveness. This plan specifies work scope and recommends schedules for activities related to resolving safety issues, such as collecting historical data, searching for authorization documents, performing Unreviewed Safety Question (USQ) screening and evaluation, identifying safety issues, imposing operational controls and monitoring, characterizing waste contents, mitigating and resolving safety issues, and fulfilling other remediation requirements consistent with the overall Tank Waste Remediation System strategy. Recommendations for characterization and remediation are also recommended according to the order of importance and practical programmatic consideration

  15. DOE underground storage tank waste remediation chemical processing hazards. Part I: Technology dictionary

    International Nuclear Information System (INIS)

    DeMuth, S.F.

    1996-10-01

    This document has been prepared to aid in the development of Regulating guidelines for the Privatization of Hanford underground storage tank waste remediation. The document has been prepared it two parts to facilitate their preparation. Part II is the primary focus of this effort in that it describes the technical basis for established and potential chemical processing hazards associated with Underground Storage Tank (UST) nuclear waste remediation across the DOE complex. The established hazards involve those at Sites for which Safety Analysis Reviews (SARs) have already been prepared. Potential hazards are those involving technologies currently being developed for future applications. Part I of this document outlines the scope of Part II by briefly describing the established and potential technologies. In addition to providing the scope, Part I can be used as a technical introduction and bibliography for Regulatory personnel new to the UST waste remediation, and in particular Privatization effort. Part II of this document is not intended to provide examples of a SAR Hazards Analysis, but rather provide an intelligence gathering source for Regulatory personnel who must eventually evaluate the Privatization SAR Hazards Analysis

  16. Structural analysis of an underground reinforced concrete waste storage tank due to over-pressurization

    International Nuclear Information System (INIS)

    Xu, J.; Bandyopadhyay, K.; Shteyngart, S.

    1993-01-01

    This paper presents the results of a structural analysis performed by use of the finite element method in determining the pressure-carrying capacity of an underground tank which contains nuclear wastes. The tank and surrounding soil were modeled and analyzed using the ABAQUS program. Special emphasis as given to determining the effects of soil-containment interaction by employing a Coulomb friction model. The effect of material properties was investigated by considering two sets of stress-strain data for the steel plates. In addition, a refined mesh was used to evaluate the strain concentration effects at steel liner thickness discontinuities

  17. Structural analysis of underground gunite storage tanks. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This report documents the structural analysis of the 50-ft diameter underground gunite storage tanks constructed in 1943 and located in the Oak Ridge National Laboratory (ORNL) South Tank Farm, known as Facility 3507 in the 3500-3999 area. The six gunite tanks (W-5 through W-10) are spaced in a 2 {times} 3 matrix at 60 ft on centers with 6 ft of soil cover. Each tank (Figures 1, 2, and 3) has an inside diameter of 50 ft, a 12-ft vertical sidewall having a thickness of 6 in. (there is an additional 1.5-in. inner liner for much of the height), and a spherical domed roof (nominal thickness is 10 in.) rising another 6 ft, 3 in. at the center of the tank. The thickness of both the sidewall and the domed roof increases to 30 in. near their juncture. The tank floor is nominally 3-in. thick, except at the juncture with the wall where the thickness increases to 9 in. The tanks are constructed of gunite (a mixture of Portland cement, sand, and water in the form of a mortar) sprayed from the nozzle of a cement gun against a form or a solid surface. The floor and the dome are reinforced with one layer of welded wire mesh and reinforcing rods placed in the radial direction. The sidewall is reinforced with three layers of welded wire mesh, vertical {1/2}-in. rods, and 21 horizontal rebar hoops (attached to the vertical rods) post-tensioned to 35,000 psi stress. The haunch at the sidewall/roof junction is reinforced with 17 horizontal rebar hoops post-tensioned with 35,000 to 40,000 psi stress. The yield strength of the post-tensioning steel rods is specified to be 60,000 psi, and all other steel is 40,000 psi steel. The specified 28-day design strength of the gunite is 5,000 psi.

  18. Structural analysis of underground gunite storage tanks. Environmental Restoration Program

    International Nuclear Information System (INIS)

    1995-08-01

    This report documents the structural analysis of the 50-ft diameter underground gunite storage tanks constructed in 1943 and located in the Oak Ridge National Laboratory (ORNL) South Tank Farm, known as Facility 3507 in the 3500-3999 area. The six gunite tanks (W-5 through W-10) are spaced in a 2 x 3 matrix at 60 ft on centers with 6 ft of soil cover. Each tank (Figures 1, 2, and 3) has an inside diameter of 50 ft, a 12-ft vertical sidewall having a thickness of 6 in. (there is an additional 1.5-in. inner liner for much of the height), and a spherical domed roof (nominal thickness is 10 in.) rising another 6 ft, 3 in. at the center of the tank. The thickness of both the sidewall and the domed roof increases to 30 in. near their juncture. The tank floor is nominally 3-in. thick, except at the juncture with the wall where the thickness increases to 9 in. The tanks are constructed of gunite (a mixture of Portland cement, sand, and water in the form of a mortar) sprayed from the nozzle of a cement gun against a form or a solid surface. The floor and the dome are reinforced with one layer of welded wire mesh and reinforcing rods placed in the radial direction. The sidewall is reinforced with three layers of welded wire mesh, vertical 1/2-in. rods, and 21 horizontal rebar hoops (attached to the vertical rods) post-tensioned to 35,000 psi stress. The haunch at the sidewall/roof junction is reinforced with 17 horizontal rebar hoops post-tensioned with 35,000 to 40,000 psi stress. The yield strength of the post-tensioning steel rods is specified to be 60,000 psi, and all other steel is 40,000 psi steel. The specified 28-day design strength of the gunite is 5,000 psi

  19. South Tank Farm underground storage tank inspection using the topographical mapping system for radiological and hazardous environments

    International Nuclear Information System (INIS)

    Armstrong, G.A.; Burks, B.L.; Hoesen, S.D. van

    1997-07-01

    During the winter of 1997 the Topographical Mapping System (TMS) for hazardous and radiological environments and the Interactive Computer-Enhanced Remote-Viewing System (ICERVS) were used to perform wall inspections on underground storage tanks (USTs) W5 and W6 of the South Tank Farm (STF) at Oak Ridge National Laboratory (ORNL). The TMS was designed for deployment in the USTs at the Hanford Site. Because of its modular design, the TMS was also deployable in the USTs at ORNL. The USTs at ORNL were built in the 1940s and have been used to store radioactive waste during the past 50 years. The tanks are constructed with an inner layer of Gunite trademark that has been spalling, leaving sections of the inner wall exposed. Attempts to quantify the depths of the spalling with video inspection have proven unsuccessful. The TMS surface-mapping campaign in the STF was initiated to determine the depths of cracks, crevices, and/or holes in the tank walls and to identify possible structural instabilities in the tanks. The development of the TMS and the ICERVS was initiated by DOE for the purpose of characterization and remediation of USTs at DOE sites across the country. DOE required a three-dimensional, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is mapping the interiors of USTs as part of DOE's waste characterization and remediation efforts, to obtain both baseline data on the content of the storage tank interiors and changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Site, the TMS has been designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention

  20. Environmental Monitoring Of Leaks Using Time Lapsed Long Electrode Electrical Resistivity

    International Nuclear Information System (INIS)

    Rucker, D.F.; Fink, J.B.; Loke, M.H.; Myers, D.A.

    2009-01-01

    Highly industrialized areas pose significant challenges for surface based electrical resistivity characterization and monitoring due to the high degree of metallic infrastructure. The infrastructure is typically several orders of magnitude more conductive than the desired targets, preventing the geophysicist from obtaining a clear picture of the subsurface. These challenges may be minimized if steel-cased wells are used as long electrodes. We demonstrate a method of using long electrodes in a complex nuclear waste facility to monitor a simulated leak from an underground storage tank. The leak was simulated by injecting high conductivity fluid in a perforated well and the resistivity measurements were made before and after the leak test. The data were processed in four dimensions, where a regularization procedure was applied in both the time and space domains. The results showed a lowered resistivity feature develop south of the injection site. The time lapsed regularization parameter had a strong influence on the differences in inverted resistivity between the pre and post datasets, potentially making calibration of the results to specific hydrogeologic parameters difficult.

  1. Review of sensors for the in situ chemical characterization of the Hanford underground storage tanks

    International Nuclear Information System (INIS)

    Kyle, K.R.; Mayes, E.L.

    1994-01-01

    Lawrence Livermore National Laboratory (LLNL), in the Technical Task Plan (TTP) SF-2112-03 subtask 2, is responsible for the conceptual design of a Raman probe for inclusion in the in-tank cone penetrometer. As part of this task, LLNL is assigned the further responsibility of generating a report describing a review of sensor technologies other than Raman that can be incorporated in the in-tank cone penetrometer for the chemical analysis of the tank environment. These sensors would complement the capabilities of the Raman probe, and would give information on gaseous, liquid, and solid state species that are insensitive to Raman interrogation. This work is part of a joint effort involving several DOE laboratories for the design and development of in-tank cone penetrometer deployable systems for direct UST waste characterization at Westinghouse Hanford Company (WHC) under the auspices of the U.S. Department of Energy (DOE) Underground Storage Tank Integrated Demonstration (UST-ID)

  2. Review of sensors for the in situ chemical characterization of the Hanford underground storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Kyle, K.R.; Mayes, E.L.

    1994-07-29

    Lawrence Livermore National Laboratory (LLNL), in the Technical Task Plan (TTP) SF-2112-03 subtask 2, is responsible for the conceptual design of a Raman probe for inclusion in the in-tank cone penetrometer. As part of this task, LLNL is assigned the further responsibility of generating a report describing a review of sensor technologies other than Raman that can be incorporated in the in-tank cone penetrometer for the chemical analysis of the tank environment. These sensors would complement the capabilities of the Raman probe, and would give information on gaseous, liquid, and solid state species that are insensitive to Raman interrogation. This work is part of a joint effort involving several DOE laboratories for the design and development of in-tank cone penetrometer deployable systems for direct UST waste characterization at Westinghouse Hanford Company (WHC) under the auspices of the U.S. Department of Energy (DOE) Underground Storage Tank Integrated Demonstration (UST-ID).

  3. Means for preventing radioactive fluid leaking

    International Nuclear Information System (INIS)

    Akatsu, Jun-ichi.

    1975-01-01

    Object: To permit prevention of leakage of radioactive fluid from line and valve leak sections while also recovering the liquid by producing a vacuum state in a leak-off line by means of a water ejector. Structure: A portion of the water from a condenser is forced by a condensed water pump through a water ejector tank to a recovery tank while controlling an orifice and valve, whereby a vacuum state is produced in the leak-off line to withdraw the leakage fluid. (Kamimura, M.)

  4. Control system design for robotic underground storage tank inspection systems

    International Nuclear Information System (INIS)

    Kiebel, G.R.

    1994-09-01

    Control and data acquisition systems for robotic inspection and surveillance systems used in nuclear waste applications must be capable, versatile, and adaptable to changing conditions. The nuclear waste remediation application is dynamic -- requirements change as public policy is constantly re-examined and refocused, and as technology in this area advances. Control and data acquisition systems must adapt to these changing conditions and be able to accommodate future missions, both predictable and unexpected. This paper describes the control and data acquisition system for the Light Duty Utility Arm (LDUA) System that is being developed for remote surveillance and inspection of underground storage tanks at the Hanford Site and other US Department of Energy (DOE) sites. It is a high-performance system which has been designed for future growth. The priority mission at the Hanford site is to retrieve the waste generated by 50 years of production from its present storage and process it for final disposal. The LDUA will help to gather information about the waste and the tanks it is stored in to better plan and execute the cleanup mission

  5. TANK FARM RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE

    International Nuclear Information System (INIS)

    DODD RA

    2008-01-01

    One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the U. S. Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60 percent of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste to the surrounding soil. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring this waste to the DST system. Retrieval of SST saltcake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. Regulatory requirements for SST waste retrieval and tank farm closure are established in the Hanford Federal Facility Agreement and Consent Order (HFFACO), better known as the TriParty Agreement, or TPA. The HFFACO was signed by the DOE, the State of Washington Department of Ecology (Ecology), and U. S. Environmental Protection Agency (EPA) and requires retrieval of as much waste as technically possible, with waste residues not to exceed 360 fe in 530,000 gallon or larger tanks; 30 fe in 55,000 gallon or smaller tanks; or the limit of waste retrieval technology, whichever is less. If residual waste volume requirements cannot be achieved, then HFFACO Appendix H provisions can be invoked to request Ecology and EPA approval of an

  6. An assessment study of septic tank based sewage disposal system on quality of underground water

    International Nuclear Information System (INIS)

    Khawaja, A.A.; Lisa, M.; Boustani, M.; Jaffar, M.; Masud, K.

    1999-01-01

    An assessment of septic tank based sewage disposal system made on the basis of quality of underground water is presented. Machrala village is selected as the case study area where an ever-increasing number of septic tanks are posing great health threat to the inhabitants. Both hand pump and tube well water samples are analyzed for toxic trace metals (Mn, Fe, Cd and Co), physico-chemical parameters (pH, turbidity, conductance, total dissolved salts, Ca, Mg, Cl/sup-/ and SO/sub 4//sup -2/) and micro-organism population in terms of total viable count, coliform count, MPN coliform. The metals were analyzed by the flame atomic absorption method using standard procedure. The study shows that the local underground water of the village is being adversely affected by toxic metals and coliform bacteria. In most cases, the latter parameter exceeds 240 counts/ml. Besides, tube well water were found to have higher Pb concentration (0.200 mg/ml) and the overall assessment renders more than 50% of the water samples as unsatisfactory for human consumption. (author)

  7. Reactivity of Primary Soil Minerals and Secondary Precipitates Beneath Leaking Hanford Waste Tanks

    International Nuclear Information System (INIS)

    Nagy, Kathryn L.; Sturchio, Neil C.

    2003-01-01

    This project, renewal of a previous EMSP project of the same title, is in its first year of funding at the University of Illinois at Chicago. The purpose is to continue investigating rates and mechanisms of reactions between primary sediment minerals found in the Hanford subsurface and leaked waste tank solutions. The goals are to understand processes that result in (1) changes in porosity and permeability of the sediment and resultant changes in flow paths of the contaminant plumes, (2) formation of secondary precipitates that can take up contaminants in their structures, and (3) release of mineral components that can drive redox reactions affecting dissolved contaminant mobility. A post-doctoral scientist, Dr. Sherry Samson, has been hired and two masters of science students are beginning to conduct experimental research. One research project that is underway is focused on measurement of the dissolution rates of plagioclase feldspar in high pH, high nitrate, high Al-bearing solutions characteristic of the BX tank farms. The first set of experiments is being conduced at room temperature. Subsequent experiments will examine the role of temperature because tank solutions in many cases were near boiling when leakage is thought to have occurred and temperature gradients have been observed beneath the SX and BX tank farms. The dissolution experiments are being conducted in stirred-flow kinetic reactors using powdered labradorite feldspar from Pueblo Park, New Mexico

  8. Detection and delineation of underground septic tanks in sandy terrain using ground penetrating radar

    Science.gov (United States)

    Omolaiye, Gabriel Efomeh; Ayolabi, Elijah A.

    2010-09-01

    A ground penetrating radar (GPR) survey was conducted on the Lekki Peninsula, Lagos State, Nigeria. The primary target of the survey was the delineation of underground septic tanks (ST). A total of four GPR profiles were acquired on the survey site using Ramac X3M GPR equipment with a 250MHz antenna, chosen based on the depth of interest and resolution. An interpretable depth of penetration of 4.5m below the surface was achieved after processing. The method accurately delineated five underground ST. The tops of the ST were easily identified on the radargram based on the strong-amplitude anomalies, the length and the depths to the base of the ST were estimated with 99 and 73 percent confidence respectively. The continuous vertical profiles provide uninterrupted subsurface data along the lines of traverse, while the non-intrusive nature makes it an ideal tool for the accurate mapping and delineation of underground utilities.

  9. Development of a computer code to predict a ventilation requirement for an underground radioactive waste storage tank

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y.J.; Dalpiaz, E.L. [ICF Kaiser Hanford Co., Richland, WA (United States)

    1997-08-01

    Computer code, WTVFE (Waste Tank Ventilation Flow Evaluation), has been developed to evaluate the ventilation requirement for an underground storage tank for radioactive waste. Heat generated by the radioactive waste and mixing pumps in the tank is removed mainly through the ventilation system. The heat removal process by the ventilation system includes the evaporation of water from the waste and the heat transfer by natural convection from the waste surface. Also, a portion of the heat will be removed through the soil and the air circulating through the gap between the primary and secondary tanks. The heat loss caused by evaporation is modeled based on recent evaporation test results by the Westinghouse Hanford Company using a simulated small scale waste tank. Other heat transfer phenomena are evaluated based on well established conduction and convection heat transfer relationships. 10 refs., 3 tabs.

  10. Tanks focus area. Annual report 1997

    International Nuclear Information System (INIS)

    Frey, J.

    1997-01-01

    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

  11. 75 FR 76742 - Detecting Oil Leaks From Vessels Into the Water

    Science.gov (United States)

    2010-12-09

    ... to detect leaks from oil tanks into the water? (E) What is the threshold for detection, accuracy... than leak detection from oil cargo tanks into the water? (H) Are methods or equipment being applied for... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2010-1085] Detecting Oil Leaks From...

  12. Low Level Leaks

    Science.gov (United States)

    1998-01-01

    NASA has transferred the improved portable leak detector technology to UE Systems, Inc.. This instrument was developed to detect leaks in fluid systems of critical launch and ground support equipment. This system incorporates innovative electronic circuitry, improved transducers, collecting horns, and contact sensors that provide a much higher degree of reliability, sensitivity and versatility over previously used systems. Potential commercial uses are pipelines, underground utilities, air-conditioning systems, petrochemical systems, aerospace, power transmission lines and medical devices.

  13. Contingency plan for the Old Hydrofracture Facility tanks sluicing project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-10-01

    Lockheed Martin Energy Systems, Inc. (Energy Systems), plans to begin a sluicing (flushing) and pumping project to remove the contents from five inactive, underground storage tanks at the Old Hydrofracture Facility (OHF) at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The tank contents will be transferred to the Melton Valley Storage Tanks, which are part of the active waste treatment system at ORNL. The purpose of the project is to minimize the risk of leaking the highly radioactive material to the environment. The five OHF tanks each contain a layer of sludge and a layer of supernatant. Based on a sampling project undertaken in 1995, the sludge in the tanks has been characterized as transuranic and mixed waste and the supernatants have been characterized as mixed waste. The combined radioactivity of the contents of the five tanks is approximately 29,500 Ci. This contingency plan is based on the preliminary design for the project and describes a series of potential accident/release scenarios for the project. It outlines Energy Systems' preliminary plans for prevention, detection, and mitigation. Prevention/detection methods range from using doubly contained pipelines to alarmed sensors and automatic pump cutoff systems. Plans for mitigation range from pumping leaked fluids from the built-in tank drainage systems and cleaning up spilled liquids to personnel evacuation

  14. Engineering study of 50 miscellaneous inactive underground radioactive waste tanks located at the Hanford Site, Washington

    International Nuclear Information System (INIS)

    Freeman-Pollard, J.R.

    1994-01-01

    This engineering study addresses 50 inactive underground radioactive waste tanks. The tanks were formerly used for the following functions associated with plutonium and uranium separations and waste management activities in the 200 East and 200 West Areas of the Hanford Site: settling solids prior to disposal of supernatant in cribs and a reverse well; neutralizing acidic process wastes prior to crib disposal; receipt and processing of single-shell tank (SST) waste for uranium recovery operations; catch tanks to collect water that intruded into diversion boxes and transfer pipeline encasements and any leakage that occurred during waste transfer operations; and waste handling and process experimentation. Most of these tanks have not been in use for many years. Several projects have, been planned and implemented since the 1970's and through 1985 to remove waste and interim isolate or interim stabilize many of the tanks. Some tanks have been filled with grout within the past several years. Responsibility for final closure and/or remediation of these tanks is currently assigned to several programs including Tank Waste Remediation Systems (TWRS), Environmental Restoration and Remedial Action (ERRA), and Decommissioning and Resource Conservation and Recovery Act (RCRA) Closure (D ampersand RCP). Some are under facility landlord responsibility for maintenance and surveillance (i.e. Plutonium Uranium Extraction [PUREX]). However, most of the tanks are not currently included in any active monitoring or surveillance program

  15. 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

    International Nuclear Information System (INIS)

    1998-04-01

    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

  16. Single-Shell Tank Leak Integrity Summary

    Energy Technology Data Exchange (ETDEWEB)

    Harlow, D. G. [Washington River Protection Solutions LLC, Richland, WA (United States); Girardot, C. L. [Washington River Protection Solutions LLC, Richland, WA (United States); Venetz, T. J. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2015-03-26

    This document summarizes and evaluates the information in the Hanford Tri-Party Agreement Interim Milestone M-045-91F Targets completed between 2010 and 2015. 1) Common factors of SST liner failures (M-045-91F-T02), 2) the feasibility of testing for ionic conductivity between the inside and outside of SSTs (M-045-91F-T03, and 3) the causes, locations, and rates of leaks from leaking SSTs (M-045-91F-T04).

  17. Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site

    International Nuclear Information System (INIS)

    Bohrman, D.E.; Ingram, E.M.

    1993-09-01

    This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7)

  18. Leak Detection in Heat Exchangers and Underground Pipelines Using Radiotracers. Material for Education and On-The-Job Training for Practitioners of Radiotracer Technology

    International Nuclear Information System (INIS)

    2009-01-01

    The International Atomic Energy Agency plays a major role in facilitating the transfer of radiotracer technology to developing Member States. The use of radiotracer techniques is well established in many Member States; some hundred radiotracer and end user specialists have been trained in radiotracer techniques and their applications; nearly 50 radiotracer laboratories have been working in this field. The training of radiotracer practitioners is vital for the provision of quality services to industry. Leak detection using radiotracer techniques is probably one of the most widespread applications of radiotracers in industrial troubleshooting. Radiotracer techniques are the most competitive for online leak inspection of heat exchangers and buried pipelines. Radiotracers help in early detection of leaks in heat exchangers and underground transporting pipelines, thus saving money, reducing shutdown time, ensuring safe operation and protecting the environment from pollution. The training course series on leak detection in heat exchangers and underground pipelines using radiotracers addresses the needs of the radiotracer groups and their end users. Besides training purposes, this material will assist radiotracer groups in establishing their quality control and accreditation systems. This training course material is based on lecture notes and practical work delivered by many experts in IAEA-supported activities. In particular, the Technical Cooperation Projects implemented under the Regional Cooperative Agreement (RCA) of the IAEA Member States in the Asia and the Pacific Region have been successful in transferring and implementing radiotracer techniques for leak detection to many end users from oil and gas production, oil refineries and the petrochemical industry. The experience obtained in the RCA Region is presented in the training material illustrated with many case studies carried out in several RCA Member States. Lectures and case studies were reviewed by a number

  19. Recent progress of the waste processing and disposal projects within the Underground Storage Tank-Integrated Demonstration

    International Nuclear Information System (INIS)

    Hunt, R.D.; McGinnis, C.P.; Cruse, J.M.

    1994-01-01

    The US Department of Energy (DOE) Office of Environmental Restoration and Waste Remediation has created the Office of Technology Development (OTD) to provide new and improved remediation technologies for the 1 x 10 8 gal of radioactive waste in the underground storage tanks (USTs) at five DOE sites. The OTD established and the Underground Storage Tank-Integrated Demonstration (UST-ID) to perform demonstrations, tests, and evaluations on these new technologies before these processes are transferred to the tank sites for use in full-scale remediation of the USTs. The UST-ID projects are performed by the Characterization and Waste Retrieval Program or the Waste Processing and Disposal Program (WPDP). During FY 1994, the WPDP is funding 12 projects in the areas of supernate processing, sludge processing, nitrate destruction, and final waste forms. The supernate projects are primarily concerned with cesium removal. A mobile evaporator and concentrator for cesium-free supernate is also being demonstrated. The sludge projects are emphasizing sludge dissolution and the evaluation of the TRUEX and diamide solvent extraction processes for transuranic waste streams. One WPDP project is examining both supernate and sludge processes in an effort to develop a system-level plan for handling all UST waste. The other WPDP studies are concerned with nitrate and organic destruction as well as subsequent waste forms. The current status of these WPDP projects is presented

  20. Dropping of mixing pump in Tank 102-AP

    International Nuclear Information System (INIS)

    Jimenez, R.F.

    1995-01-01

    The purpose of this study is to examine dropping of the mixing pump in Tank 102-AP during its removal poses the risk of causing a leak in the tank bottom with attendant potential for public exposure from the leak. The purpose of this investigation is to examine the potential for causing such a leak (i.e., estimated frequency of leak occurrence); to qualitatively estimate leak magnitude if its is a credible event; and, finally to compare the worker hazard, in the installation of an impact limiter (should it be required), to that which the public might incur if a leak is manifest in the tank bottom. The ultimate goal of the study is, of course, to assess the need for installation of an impact limiter

  1. CHEMICAL SLUDGE HEEL REMOVAL AT THE SAVANNAH RIVER SITE F TANK FARM CLOSURE PROJECT 8183

    International Nuclear Information System (INIS)

    Thaxton, D; Timothy Baughman, T

    2008-01-01

    Chemical Sludge Removal (CSR) is the final waste removal activity planned for some of the oldest nuclear waste tanks located at the Savannah River Site (SRS) in Aiken, SC. In 2008, CSR will be used to empty two of these waste tanks in preparation for final closure. The two waste tanks chosen to undergo this process have previously leaked small amounts of nuclear waste from the primary tank into an underground secondary containment pan. CSR involves adding aqueous oxalic acid to the waste tank in order to dissolve the remaining sludge heel. The resultant acidic waste solution is then pumped to another waste tank where it will be neutralized and then stored awaiting further processing. The waste tanks to be cleaned have a storage capacity of 2.84E+06 liters (750,000 gallons) and a target sludge heel volume of 1.89E+04 liters (5,000 gallons) or less for the initiation of CSR. The purpose of this paper is to describe the CSR process and to discuss the most significant technical issues associated with the development of CSR

  2. TANK WASTE RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE

    International Nuclear Information System (INIS)

    DODD, R.A.

    2006-01-01

    One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the US Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60% of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring the waste to the DST system since 1997 as part of the interim stabilization program. Retrieval of SST saltcake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. This paper presents lessons learned from retrieval of tank waste at the Hanford Site and discusses how this information is used to optimize retrieval system efficiency, improve overall cost effectiveness of retrieval operations, and ensure that HFFACO requirements are met

  3. Draining device in an emergency holding floor for leaked liquid metals

    International Nuclear Information System (INIS)

    Kawakami, Hiroto.

    1980-01-01

    Purpose: To automatically discharge leaked liquid metals rapidly to a damping tank in LMFBR type reactors, by the provision of freeze-seal mechanisms having materials capable of being fused due to the heat of the leaked liquid metals to a catching pan for leaked liquid metals. Constitution: A freeze seal pot having a double seal against other liquid by the provision of a freeze seal material fusible by the heat of the leaked metallic sodium and a downwardly opening cup-like inner cylinder closed by a rupturing plate to be ruptured by heat or pressure is provided to the catching pot of a catching tank. A drain pipe connecting by way of a pot to the damping tank is connected to the pan. Accordingly, if the seal member is fused due to the heat of the leaked liquid sodium, the rupturing plate is ruptured due to the decrease in the strength by the heat of the leaked liquid sodium and by the pressure, whereby leaked liquid sodium is automatically discharged into the damping tank rapidly and safely, and the temperature increase in the concrete materials is reduced as compared with the case of cooling the concrete by covering with liners. (Seki, T.)

  4. Environmental Assessment: Waste Tank Safety Program, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1994-02-01

    The US Department of Energy (DOE) needs to take action in the near-term, to accelerate resolution of waste tank safety issues at the Hanford Site near the City of Richland, Washington, and reduce the risks associated with operations and management of the waste tanks. The DOE has conducted nuclear waste management operations at the Hanford Site for nearly 50 years. Operations have included storage of high-level nuclear waste in 177 underground storage tanks (UST), both in single-shell tank (SST) and double-shell tank configurations. Many of the tanks, and the equipment needed to operate them, are deteriorated. Sixty-seven SSTs are presumed to have leaked a total approximately 3,800,000 liters (1 million gallons) of radioactive waste to the soil. Safety issues associated with the waste have been identified, and include (1) flammable gas generation and episodic release; (2) ferrocyanide-containing wastes; (3) a floating organic solvent layer in Tank 241-C-103; (4) nuclear criticality; (5) toxic vapors; (6) infrastructure upgrades; and (7) interim stabilization of SSTs. Initial actions have been taken in all of these areas; however, much work remains before a full understanding of the tank waste behavior is achieved. The DOE needs to accelerate the resolution of tank safety concerns to reduce the risk of an unanticipated radioactive or chemical release to the environment, while continuing to manage the wastes safely

  5. Advanced remediation, technology development in the underground storage tank

    International Nuclear Information System (INIS)

    Gates, T.E.; Gilchrist, R.L.

    1992-01-01

    Production of nuclear materials has been a major mission of the U. S. Department of Energy (DOE) over the last 50 years. These activities have contributed to a substantial accumulation of hazardous, radioactive, and mixed wastes. In 1989, the DOE established the Office of Environmental Restoration and Waste Management. This office coordinates and manages the DOE's remediation, waste minimization, and environmental compliance activities. It also has responsibility for waste generated by current operations. Within this office is the Office of Technology Development, which is responsible for providing technology improvements. This paper reports on integrated demonstrations which have been established to efficiently bring the best technologies to bear on the common needs of multiple DOE sites. One such need is resolution of the actions required for final closure and waste disposal of liquid (including sludge and salt cake) radioactive and chemical wastes that have been transferred to underground storage tanks

  6. 241-CX-70, 241-CX-71, and 241-CX-72 underground storage tanks at the strontium semiworks facility supplemental information to the Hanford Facility Contingency Plan

    International Nuclear Information System (INIS)

    Ingle, S.J.

    1996-03-01

    This document is a unit-specific contingency plan for the underground storage tanks at the Strontium Semiworks Facility and is intended to be used as a supplement to the Hanford Facility Contingency Plan. This unit-specific plan is to be used to demonstrate compliance with the contingency plan requirements of WAC 173-303 for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units. Radioactive material is contained in three underground storage tanks: 241-CX-70, 241-CX-71, and 241-CX-72. Tank 241-CX-70 has been emptied, except for residual quantities of waste, and has been classified as an elementary neutralization tank under the RCRA. Tanks 241-CX-71 and 241-CX-72 contain radioactive and Washington State-only dangerous waste material, but do not present a significant hazard to adjacent facilities, personnel, or the environment. Currently, dangerous waste management activities are not being applied at the tanks. It is unlikely that any incidents presenting hazards to public health or the environment would occur at the Strontium Semiworks Facility

  7. Detailed Leak Detection Test Plan and schedule for the Oak Ridge National Laboratory liquid low-level waste active pipelines

    International Nuclear Information System (INIS)

    1994-08-01

    This document provides a detailed leak detection test plan and schedule for the pipelines that comprise the active, singly contained, portion of the liquid low-level waste (LLLW) system at the Oak Ridge National Laboratory (ORNL). This plan was prepared in response to the requirements of the Federal Facility Agreement for the Oak Ridge Reservation (FFA) between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC). The LLLW system is an interconnected complex of tanks and pipelines. The FFA distinguishes four categories of tank and pipeline systems within this complex: new or replacement tank systems with secondary containment (Category A), existing tank systems with secondary containment (Category B), existing tank systems without secondary containment (Category C), and tank systems that have been removed from service (Category D). The FFA specifically requires that DOE demonstrate that the Category C systems are not leaking. This plan and schedule addresses testing of the Category C pipelines and the pipelines which are part of Category B tank systems that do not fully meet the requirements for secondary containment as listed in the FFA. A key feature of the plan is that it is based on the use of performance standards for the conduct of release detection testing, and on the use of methods whose performance has been evaluated and shown to meet those standards. Another feature of the plan is that it is based in part on relevant portions of current federal EPA regulations applicable to underground storage tanks and pipelines (UST systems) that store and transfer petroleum products and other hazardous substances. While the FFA does not require that the testing at ORNL follow these regulations, the regulations do provide industry- and regulator-accepted performance standards, as well as a schedule for repeated testing of UST components

  8. Failure analysis of buried tanks

    International Nuclear Information System (INIS)

    Watkins, R.K.

    1994-01-01

    Failure of a buried tank can be hazardous. Failure may be a leak through which product is lost from the tank; but also through which contamination can occur. Failures are epidemic -- because buried tanks are out of sight, but also because designers of buried tanks have adopted analyses developed for pressure tanks. So why do pressure tanks fail when they are buried? Most failures of buried tanks are really soil failures. Soil compresses, or slips, or liquefies. Soil is not only a load, it is a support without which the tank deforms. A high water table adds to the load on the tank. It also reduces the strength of the soil. Based on tests, structural analyses are proposed for empty tanks buried in soils of various quality, with the water table at various levels, and with internal vacuum. Failure may be collapse tank. Such collapse is a sudden, audible inversion of the cylinder when the sidefill soil slips. Failure may be flotation. Failure may be a leak. Most leaks are fractures in the welds in overlap seams at flat spots. Flat spots are caused by a hard bedding or a heavy surface wheel load. Because the tank wall is double thick at the overlap, shearing stress in the weld is increased. Other weld failures occur when an end plate shears down past a cylinder; or when the tank is supported only at its ends like a beam. These, and other, failures can be analyzed with justifiable accuracy using basic principles of mechanics of materials. 10 figs

  9. Accuracy improvement in the TDR-based localization of water leaks

    Directory of Open Access Journals (Sweden)

    Andrea Cataldo

    Full Text Available A time domain reflectometry (TDR-based system for the localization of water leaks has been recently developed by the authors. This system, which employs wire-like sensing elements to be installed along the underground pipes, has proven immune to the limitations that affect the traditional, acoustic leak-detection systems.Starting from the positive results obtained thus far, in this work, an improvement of this TDR-based system is proposed. More specifically, the possibility of employing a low-cost, water-absorbing sponge to be placed around the sensing element for enhancing the accuracy in the localization of the leak is addressed.To this purpose, laboratory experiments were carried out mimicking a water leakage condition, and two sensing elements (one embedded in a sponge and one without sponge were comparatively used to identify the position of the leak through TDR measurements. Results showed that, thanks to the water retention capability of the sponge (which maintains the leaked water more localized, the sensing element embedded in the sponge leads to a higher accuracy in the evaluation of the position of the leak. Keywords: Leak localization, TDR, Time domain reflectometry, Water leaks, Underground water pipes

  10. Aboveground storage tanks

    International Nuclear Information System (INIS)

    Rizzo, J.A.

    1992-01-01

    With the 1988 promulgation of the comprehensive Resource Conservation and Recovery Act (RCRA) regulations for underground storage of petroleum and hazardous substances, many existing underground storage tank (UST) owners have been considering making the move to aboveground storage. While on the surface, this may appear to be the cure-all to avoiding the underground leakage dilemma, there are many other new and different issues to consider with aboveground storage. The greatest misconception is that by storing materials above ground, there is no risk of subsurface environmental problems. it should be noted that with the aboveground storage tank (AGST) systems, there is still considerable risk of environmental contamination, either by the failure of onground tank bottoms or the spillage of product onto the ground surface where it subsequently finds its way to the ground water. In addition, there are added safety concerns that must be addressed. So what are the other specific areas of concern besides environmental to be addressed when making the decision between underground and aboveground tanks? The primary issues that will be addressed in this paper are: Safety, Product Losses, Cost Comparison of USTs vs AGSTs, Space Availability/Accessibility, Precipitation Handling, Aesthetics and Security, Pending and Existing Regulations

  11. Leak testing plan for the Oak Ridge National Laboratory liquid low-level waste systems (active tanks): Revision 2. Volume 1: Regulatory background and plan approach; Volume 2: Methods, protocols, and schedules; Volume 3: Evaluation of the ORNL/LT-823DP differential pressure leak detection method; Appendix to Revision 2: DOE/EPA/TDEC correspondence

    Energy Technology Data Exchange (ETDEWEB)

    Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr. [Vista Research, Inc., Mountain View, CA (United States)

    1994-11-01

    This document, the Leak Testing Plan for the Oak Ridge National Laboratory Liquid Low-Level Waste System (Active Tanks), comprises three volumes. The first two volumes address the component-based leak testing plan for the liquid low-level waste system at Oak Ridge, while the third volume describes the performance evaluation of the leak detection method that will be used to test this system. Volume 1, describes that portion of the liquid low-level waste system at that will be tested; it provides the regulatory background, especially in terms of the requirements stipulated in the Federal Facilities Agreement, upon which the leak testing plan is based. Volume 1 also describes the foundation of the plan, portions of which were abstracted from existing federal documents that regulate the petroleum and hazardous chemicals industries. Finally, Volume 1 gives an overview the plan, describing the methods that will be used to test the four classes of components in the liquid low-level waste system. Volume 2 takes the general information on component classes and leak detection methods presented in Volume 1 and shows how it applies particularly to each of the individual components. A complete test plan for each of the components is presented, with emphasis placed on the methods designated for testing tanks. The protocol for testing tank systems is described, and general leak testing schedules are presented. Volume 3 describes the results of a performance evaluation completed for the leak testing method that will be used to test the small tanks at the facility (those less than 3,000 gal in capacity). Some of the details described in Volumes 1 and 2 are expected to change as additional information is obtained, as the viability of candidate release detection methods is proven in the Oak Ridge environment, and as the testing program evolves.

  12. Leak testing plan for the Oak Ridge National Laboratory liquid low-level waste systems (active tanks): Revision 2. Volume 1: Regulatory background and plan approach; Volume 2: Methods, protocols, and schedules; Volume 3: Evaluation of the ORNL/LT-823DP differential pressure leak detection method; Appendix to Revision 2: DOE/EPA/TDEC correspondence

    International Nuclear Information System (INIS)

    Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.

    1994-11-01

    This document, the Leak Testing Plan for the Oak Ridge National Laboratory Liquid Low-Level Waste System (Active Tanks), comprises three volumes. The first two volumes address the component-based leak testing plan for the liquid low-level waste system at Oak Ridge, while the third volume describes the performance evaluation of the leak detection method that will be used to test this system. Volume 1, describes that portion of the liquid low-level waste system at that will be tested; it provides the regulatory background, especially in terms of the requirements stipulated in the Federal Facilities Agreement, upon which the leak testing plan is based. Volume 1 also describes the foundation of the plan, portions of which were abstracted from existing federal documents that regulate the petroleum and hazardous chemicals industries. Finally, Volume 1 gives an overview the plan, describing the methods that will be used to test the four classes of components in the liquid low-level waste system. Volume 2 takes the general information on component classes and leak detection methods presented in Volume 1 and shows how it applies particularly to each of the individual components. A complete test plan for each of the components is presented, with emphasis placed on the methods designated for testing tanks. The protocol for testing tank systems is described, and general leak testing schedules are presented. Volume 3 describes the results of a performance evaluation completed for the leak testing method that will be used to test the small tanks at the facility (those less than 3,000 gal in capacity). Some of the details described in Volumes 1 and 2 are expected to change as additional information is obtained, as the viability of candidate release detection methods is proven in the Oak Ridge environment, and as the testing program evolves

  13. Locating leaks in water mains using noise loggers

    OpenAIRE

    El-Abbasy, Mohammed S.; Mosleh, Fadi; Senouci, Ahmed; Zayed, Tarek; Al-Derham, Hassan

    2016-01-01

    Because of their potential danger to public health, economic loss, environmental damage, and energy waste, underground water pipelines leaks have received more attention globally. Researchers have proposed active leakage control approaches to localize, locate, and pinpoint leaks. Noise loggers have usually been used only for localizing leaks while other tools were used for locating and pinpointing. These approaches have resulted in additional cost and time. Thus, regression and artificial neu...

  14. Fuel leak detection on large transport airplanes

    OpenAIRE

    Behbahani-Pour, M.J.; Radice, G.

    2016-01-01

    Fuel leakage has the risk of being ignited by external ignition sources, and therefore it is important to detect\\ud any fuel leakage before the departure of the aircraft. Currently, there are no fuel leak detection systems installed\\ud on commercial aircrafts, to detect fuel tank leakage, while only a small number of more recent aircraft, have a fuel\\ud monitoring system, that generates a fuel leak-warning message in cockpit in the case of fuel imbalance between the\\ud tanks. The approach pro...

  15. AX Tank Farm tank removal study

    International Nuclear Information System (INIS)

    SKELLY, W.A.

    1998-01-01

    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 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

  16. Capacitive system detects and locates fluid leaks

    Science.gov (United States)

    1966-01-01

    Electronic monitoring system automatically detects and locates minute leaks in seams of large fluid storage tanks and pipelines covered with thermal insulation. The system uses a capacitive tape-sensing element that is adhesively bonded over seams where fluid leaks are likely to occur.

  17. Japan Reports New Water Leak at Fukushima Daiichi; IAEA Sees No Danger to Public

    International Nuclear Information System (INIS)

    2014-01-01

    Full text: Japanese authorities have informed the IAEA that a leak from an overflowing water storage tank at TEPCO's Fukushima Daiichi Nuclear Power Station was detected in the late evening of 19 February 2014. About 100 cubic metres of radioactive water leaked to the ground adjacent to the tank storage area before the leak was stopped about six hours later. Based on the information provided, IAEA experts consider that the leak poses no danger to the public. IAEA experts also consider actions taken by Japan's Nuclear Regulatory Authority (NRA) following the leak to be appropriate. These include an NRA recommendation that TEPCO remove soil contaminated by the leaked water, which will reduce the risk that contaminated water will be spread further through rain and groundwater. Japan has not asked the IAEA for any assistance in connection with the leak from the tank. The IAEA will continue monitoring developments. (IAEA)

  18. Design and construction work of underground pit for existing light oil tank foundation at Onagawa Nuclear Power Station

    International Nuclear Information System (INIS)

    Kikuchi, Keita; Date, Masanao; Horimi, Shingo

    2017-01-01

    Based on the new regulatory standards for commercial power plant reactors enforced in July 2013, Onagawa Nuclear Power Station of Tohoku Electric Power Co., Inc. implemented various safety measure works. One of them was a measure for the existing light oil tank foundation for emergency diesel generators for Unit 2 reactor. In consideration of tornado, external fire, and earthquake resistance, the company implemented the underground pit construction for a light oil tank basement by utilizing the existing oil retaining wall and foundation. This paper reported the outline of the planning, design, and implementation of construction works, which were carried out while securing quality and safety. Upon installation of the underground pit, the company utilized the existing oil retaining wall from the viewpoint of reducing construction costs, shortening time schedule, and reducing environmental burden. As a result of checking bending and axial force, part of these values exceeded the design reference values. So, 3-dimensional shell model was applied, and the simulation results showed sufficient seismic margin. As a measure to secure seismic margin against shear force, Ceramic-Cap-bar construction method was adopted. Upon construction, the company adopted the water jet method, and devised the sequential order of construction. In parallel with the day and night work and tank installation, it constructed the top slab, which secured the time schedule and quality. (A.O.)

  19. Functions and requirements for subsurface barriers used in support of single-shell tank waste retrieval

    International Nuclear Information System (INIS)

    Lowe, S.S.

    1993-01-01

    The mission of the Tank Waste Remediation System (TWRS) Program is to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The scope of the TWRS Program includes project and program activities for receiving, storing, maintaining, treating, and disposing onsite, or packaging for offsite disposal, all Hanford tank waste. Hanford tank waste includes the contents of 149 single-shell tanks (SSTs) and 28 double-shell tanks (DSTs), plus any new waste added to these facilities, and all encapsulated cesium and strontium stored onsite and returned from offsite users. A key element of the TWRS Program is retrieval of the waste in the SSTs. The waste stored in these underground tanks must be removed in order to minimize environmental, safety, and health risks associated with continuing waste storage. Subsurface barriers are being considered as a means to mitigate the effects of tank leaks including those occurring during SST waste retrieval. The functions to be performed by subsurface barriers based on their role in retrieving waste from the SSTs are described, and the requirements which constrain their application are identified. These functions and requirements together define the functional baseline for subsurface barriers

  20. Detection of elastic waves for the leakage locating of underground water supply pipes

    International Nuclear Information System (INIS)

    Lee, Young Sup; Yoon, Dong Jin; Jeong, Jung Chae; Lee, Seung Seok

    2003-01-01

    Leaks in underground pipelines can cause social, environmental and economical problems. One of a good countermeasures of leaks is to find and repair of leak points of pipes. Leak noise is a good source to identify the location of leak points of pipelines. Although there have been several methods to detect the leak location with leak noise, such as listening rods, hydrophones or ground microphones, they were not so efficient tools. In this paper, two accelerometers are used to detect leak locations which could provide an easier and efficient method. The filtering, signal processing and algorithm is described for the detection of leak location. A 120 m-long pipeline system for experiment is installed and the results with the system show that the algorithm with the two accelerometers gives very accurate pinpointing of leaks. Theoretical analysis of sound wave propagation speed in underground pipes is also described.

  1. Detection of elastic waves for the leakage locating of underground water supply pipes

    International Nuclear Information System (INIS)

    Lee, Young Sup; Yoon, Dong Jin; Jeong, Jung Chae; Lee, Seung Seok

    2003-01-01

    Leaks in underground pipelines can cause social, environmental and economical problems. One of a good countermeasures of leaks is to find and repair of leak points of pipes. Leak noise is good source to identify the location of leak points of pipelines. Although there have been several methods to detect the leak location with leak noise, such as listening rods, hydrophones or ground microphones, they were not so efficient tools. In this paper, two accelerometers are used to detect leak locations which could provide an easier and efficient method. The filtering signal processing and algorithm is described for the detection of leak location. A 120 m-long pipeline system for experiment is installed and the results with the system show that the algorithm with the two accelerometers gives very accurate pinpointing of leaks. Theoretical analysis of sound wave propagation speed in underground pipes is also described.

  2. Screening the Hanford tanks for trapped gas

    International Nuclear Information System (INIS)

    Whitney, P.

    1995-10-01

    The Hanford Site is home to 177 large, underground nuclear waste storage tanks. Hydrogen gas is generated within the waste in these tanks. This document presents the results of a screening of Hanford's nuclear waste storage tanks for the presence of gas trapped in the waste. The method used for the screening is to look for an inverse correlation between waste level measurements and ambient atmospheric pressure. If the waste level in a tank decreases with an increase in ambient atmospheric pressure, then the compressibility may be attributed to gas trapped within the waste. In this report, this methodology is not used to estimate the volume of gas trapped in the waste. The waste level measurements used in this study were made primarily to monitor the tanks for leaks and intrusions. Four measurement devices are widely used in these tanks. Three of these measure the level of the waste surface. The remaining device measures from within a well embedded in the waste, thereby monitoring the liquid level even if the liquid level is below a dry waste crust. In the past, a steady rise in waste level has been taken as an indicator of trapped gas. This indicator is not part of the screening calculation described in this report; however, a possible explanation for the rise is given by the mathematical relation between atmospheric pressure and waste level used to support the screening calculation. The screening was applied to data from each measurement device in each tank. If any of these data for a single tank indicated trapped gas, that tank was flagged by this screening process. A total of 58 of the 177 Hanford tanks were flagged as containing trapped gas, including 21 of the 25 tanks currently on the flammable gas watch list

  3. Oil/gas collector/separator for underwater oil leaks

    International Nuclear Information System (INIS)

    Henning, C.D.

    1993-01-01

    An oil/gas collector/separator for underwater oil leaks is described comprising: a cylindrical tank; a hollow float member for supporting said tank in a substantially upright position; a skirt assembly secured to said hollow float member and extending in a direction away from said float member opposite said tank; means for removing oil from said tank; and means for removing gas from said tank

  4. An algorithm for leak locating using coupled vibration of pipe-water

    International Nuclear Information System (INIS)

    Lee, Young Sup; Yoon, Dong Jin

    2004-01-01

    Leak noise is a good source to identify the exact location of a leak point of underground water pipelines. Water leak generates broadband sound from a leak location and this sound propagation due to leak in water pipelines is not a non-dispersive wave any more because of the surrounding pipes and soil. However, the necessity of long-range detection of this leak location makes to identify low-frequency acoustic waves rather than high frequency ones. Acoustic wave propagation coupled with surrounding boundaries including cast iron pipes is theoretically analyzed and the wave velocity was confirmed with experiment. The leak locations were identified both by the Acoustic Emission (AE) method and the cross-correlation method. In a short-range distance, both the AE method and cross-correlation method are effective to detect leak position. However, the detection for a long-range distance required a lower frequency range accelerometers only because higher frequency waves were attenuated very quickly with the increase of propagation paths. Two algorithms for the cross-correlation function were suggested, and a long-range detection has been achieved at real underground water pipelines longer than 300m

  5. Hanford Double-Shell Tank Extent-of-Condition Construction Review

    International Nuclear Information System (INIS)

    Venetz, Theodore J.; Johnson, Jeremy M.; Gunter, Jason R.; Barnes, Travis J.; Washenfelder, Dennis J.; Boomer, Kayle D.

    2013-01-01

    During routine visual inspections of Hanford double-shell waste tank 241-AY-102 (AY-102), anomalies were identified on the annulus floor which resulted in further evaluations. Following a formal leak assessment in October 2012, Washington River Protection Solutions, LLC (WRPS) determined that the primary tank of AY-102 was leaking. The formal leak assessment, documented in RPP-ASMT-53793,Tank 241-AY-102 Leak Assessment Report, identified first-of-a-kind construction difficulties and trial-and-error repairs as major contributing factors to tank failure. To determine if improvements in double-shell tank (DST) construction occurred after construction of tank AY-102, a detailed review and evaluation of historical construction records were performed for the first three DST tank farms constructed, which included tanks 241-AY-101, 241-AZ-101, 241-AZ-102, 241-SY-101, 241-SY-102, and 241-SY-103. The review for these six tanks involved research and review of dozens of boxes of historical project documentation. These reviews form a basis to better understand the current condition of the three oldest Hanford DST farms. They provide a basis for changes to the current tank inspection program and also provide valuable insight into future tank use decisions. If new tanks are constructed in the future, these reviews provide valuable 'lessons-learned' information about expected difficulties as well as construction practices and techniques that are likely to be successful

  6. Tsuruga: 1 ton, some 10 mCi of rad-liquid leaks out to the sea, no environmental and human costs

    International Nuclear Information System (INIS)

    1981-01-01

    In the Tsuruga Nuclear Power Station of Japan Atomic Power Co., the leakage of radioactivity from the site into the sea occurred, as follows. Due to a valve being left open on March 8, 1981, the overflow of liquid waste from the filter sludge storage tank into the laundry waste filtering room took place. A part of it leaked through the floor into the general underground waterway. The amount was estimated to be one ton with some 10 mCi. The incident is reviewed with the following topics: nobody expected rad-material in the waterway with the leakage from a filter sludge tank; construction, human and management mistakes were revealed in the survey; no environmental impact, with the defect peculiar to Tsuruga; JAPCO executives assume the responsibility; JAPCO and regulatory authorities need review. (Mori, K.)

  7. WASTE TANK SUMMARY REPORT FOR MONTH ENDING 01/2004

    International Nuclear Information System (INIS)

    HANLON, B.M.

    2004-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 60 smaller miscellaneous underground storage tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of U.S. Department of Energy Order 435.1 (DOE-HQ, August 28,2001, Radioactive Waste Management, U.S. Department of Energy-Washington, D.C.) requiring the reporting of waste inventories and space utilization for the Hanford Site Tank Farm tanks

  8. Characterization of underground storage tank sludge using fourier transform infrared photoacoustic spectroscopy

    International Nuclear Information System (INIS)

    Luo, S.; Bajic, S.J.; Jones, R.W.

    1994-01-01

    Analysis of underground storage tank (UST) contents is critical for the determination of proper disposal protocols and storage procedures of nuclear waste materials. Tank volume reduction processes during the 1940's and 50's have produced a waste form that compositionally varies widely and has a consistency that ranges from paste like sludge to saltcake. The heterogeneity and chemical reactivity of the waste form makes analysis difficult by most conventional methods which require extensive sample preparation. In this paper, a method is presented to characterize nuclear waste from UST's at the Westinghouse Hanford Site in Washington State, using Fourier transform infrared-photoacoustic spectroscopy (FTIR-PAS). FTIR-PAS measurements on milligram amounts of surrogate sludge samples have been used to accurately identify phosphate, sulfate, nitrite, nitrate and ferrocyanide components. A simple sample preparation method was followed to provide a reproducible homogeneous sample for quantitative analysis. The sample preparation method involved freeze drying the sludge sample prior to analysis to prevent the migration of soluble species. Conventional drying (e.g., air or, oven) leads to the formation of crystals near the surface where evaporation occurs. Sample preparation as well as the analytical utility of this method will be discussed

  9. Vandose Zone Characterization Project at the Hanford Tank Farms: SX Tank Farm Report

    International Nuclear Information System (INIS)

    Brodeur, J.R.; Koizumi, C.J.; Bertsch, J.F.

    1996-09-01

    The SX Tank Farm is located in the southwest portion of the 200 West Area of the Hanford Site. This tank farm consists of 15 single-shell tanks (SSTs), each with an individual capacity of 1 million gallons (gal). These tanks currently store high-level nuclear waste that was primarily generated from what was called the oxidation-reduction or open-quotes REDOXclose quotes process at the S-Plant facility. Ten of the 15 tanks are listed in Hanlon as open-quotes assumed leakersclose quotes and are known to have leaked various amounts of high-level radioactive liquid to the vadose zone sediment. The current liquid content of each tank varies, but the liquid from known leaking tanks has been removed to the extent possible. In 1994, the U.S. Department of Energy Richland Office (DOE-RL) requested the DOE Grand Junction Projects Office (GJPO), Grand Junction, Colorado, to perform a baseline characterization of contamination in the vadose zone at all the SST farms with spectral gamma-ray logging of boreholes surrounding the tanks. The SX Tank Farm geophysical logging was completed, and the results of this baseline characterization are presented in this report

  10. Tank 241-BY-111 tank characterization plan

    International Nuclear Information System (INIS)

    Homi, C.S.

    1994-01-01

    The sampling and analytical needs associated with the 51 Hanford Site underground storage tanks classified on one or more of the four Watch Lists (ferrocyanide, organic, flammable gas, and high heat), and the safety screening of all 177 tanks have been identified through the Data Quality Objective (DQO) process. DQO's identify information needed by a program group in the Tank Waste Remediation System concerned with safety issues, regulatory requirements, or the transporting and processing of tank waste. This Tank Characterization Plan will identify characterization objectives for Tank BY-111 pertaining to sample collection, sample preparation and analysis, and laboratory analytical evaluation and reporting requirements. In addition, an estimate of the current contents and status of the tank is given

  11. History of waste tank 15, 1959 through 1974

    International Nuclear Information System (INIS)

    Davis, T.L.; Tharin, D.W.; Lohr, D.R.

    1978-06-01

    Tank 15 was put into service as a receiver of high heat waste (HW) supernate from leaking tank 16 on October 15, 1960, after which it also became the active receiver for fresh HW. Between June 1964 and November 1972, the supernate was decanted (leaving the sludge) five times to allow the tank to be refilled with HW. Inspections and photographs have been made in the annular space using an optical periscope. In April 1972, periscopic inspection revealed salt accumulation at two arrested leak sites on the primary tank wall. Through December 1974, fifteen leak sites had been discovered. Analytical samples of supernate and vapor have been taken. Wall thicknesses and profiles of tank temperature differences have been obtained. Several tests, primarily concerning general corrosion, have been run. Equipment modifications and various equipment repairs were made. 14 figures

  12. Water Pipeline Monitoring and Leak Detection using Flow Liquid Meter Sensor

    Science.gov (United States)

    Rahmat, R. F.; Satria, I. S.; Siregar, B.; Budiarto, R.

    2017-04-01

    Water distribution is generally installed through underground pipes. Monitoring the underground water pipelines is more difficult than monitoring the water pipelines located on the ground in open space. This situation will cause a permanent loss if there is a disturbance in the pipeline such as leakage. Leaks in pipes can be caused by several factors, such as the pipe’s age, improper installation, and natural disasters. Therefore, a solution is required to detect and to determine the location of the damage when there is a leak. The detection of the leak location will use fluid mechanics and kinematics physics based on harness water flow rate data obtained using flow liquid meter sensor and Arduino UNO as a microcontroller. The results show that the proposed method is able to work stably to determine the location of the leak which has a maximum distance of 2 metres, and it’s able to determine the leak location as close as possible with flow rate about 10 litters per minute.

  13. Fully automatic AI-based leak detection system

    Energy Technology Data Exchange (ETDEWEB)

    Tylman, Wojciech; Kolczynski, Jakub [Dept. of Microelectronics and Computer Science, Technical University of Lodz in Poland, ul. Wolczanska 221/223, Lodz (Poland); Anders, George J. [Kinectrics Inc., 800 Kipling Ave., Toronto, Ontario M8Z 6C4 (Canada)

    2010-09-15

    This paper presents a fully automatic system intended to detect leaks of dielectric fluid in underground high-pressure, fluid-filled (HPFF) cables. The system combines a number of artificial intelligence (AI) and data processing techniques to achieve high detection capabilities for various rates of leaks, including leaks as small as 15 l per hour. The system achieves this level of precision mainly thanks to a novel auto-tuning procedure, enabling learning of the Bayesian network - the decision-making component of the system - using simulated leaks of various rates. Significant new developments extending the capabilities of the original leak detection system described in and form the basis of this paper. Tests conducted on the real-life HPFF cable system in New York City are also discussed. (author)

  14. Closure report for Building 875 sump encased in concrete

    International Nuclear Information System (INIS)

    Montemayor, W.

    1991-08-01

    This report will document the post-closure activities for the 875-R1U1 Waste-Solvent Underground Storage Tank located at Lawrence Livermore National Laboratory (LLNL), Site 300. The aforementioned tank waspreviously identified and registered with the California Water Resources Control Board as 875-31R. The underground tank system consists of a 55-gallon steel drum encased in concrete. The underground tank was used to collect dripping and spillage from the above-concrete drum rack storage area. The closure of this underground tank was permitted as Tank Identification No. 39-1945-21 by W.R. Snavely of SJCPHS-EHS. The last tank test, performed on February 1988, showed that the underground tank was leak tight. On May 1988, the sludge at the bottom of the tank was removed and disposed of as hazardous waste. The residual 1.5 inches of oily water in the tank was removed and the tank was washed with soap and water on December 11, 1989. The rinsate and residual sludge was disposed of as hazardous waste. The empty tank and the encasing concrete were extracted from the ground on November 5, 1990. No underground piping was associated with the removal of this underground tank since the tank was used to collect the dripping and spillage from the above-concrete drum rack. Three soil samples were collected in split tubes from approximately 1 foot below the bottom of the tank. The soil samples were collected and analyzed for Total Petroleum Hydrocarbon (TPH)-Gasoline, TPH-Diesel, Total Extractable Petroleum, Benzene, Toluene, Xylene, Ethyl Benzene, Tetraethyl Lead, Metals, Polychlorinated Biphenyls (PCB), and Ethylene Dibromide. Results indicated that the underground tank was leak tight. The concrete encasing was removed from the 55-gallon tank and disposed of as a municipal waste. The 55-gallon tank is currently stored at the Hazardous Waste Storage Area located in Lawrence Livermore National Laboratory, Livermore, California and is waiting as a hazardous waste

  15. Quench tank in-leakage diagnosis at St. Lucie

    Energy Technology Data Exchange (ETDEWEB)

    Price, J.E.; Au-Yang, M.K.; Beckner, D.A.; Vickery, A.N.

    1996-12-01

    In February 1995, leakage into the quench tank of the St. Lucie Nuclear Station Unit 1 was becoming an operational concern. This internal leak resulted in measurable increases in both the temperature and level of the quench tank water, and was so severe that, if the trend continued, plant shut down would be necessary. Preliminary diagnosis based on in-plant instrumentation indicated that any one of 11 valves might be leaking into the quench tank. This paper describes the joint effort by two teams of engineers--one from Florida Power & Light, the other from Framatome Technologies--to identify the sources of the leak, using the latest technology developed for valve diagnosis.

  16. Waste Tank Summary Report for Month Ending February 28 2001

    International Nuclear Information System (INIS)

    HANLON, B.M.

    2001-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 63 smaller miscellaneous underground storage tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of U.S. Department of Energy-Richland Operations Office Order 435.I (DOE-RL, July 1999, Radioactive Waste Management, U.S. Department of Energy-Richland Operations Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm tanks

  17. Waste Tank Summary Report for Month Ending 04/30/2002

    International Nuclear Information System (INIS)

    HANLON, B.M.

    2002-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 60 smaller miscellaneous underground storage tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US. Department of Energy Order 435.1 (DOE-HQ, August 28, 2001, Radioactive Waste Management, US. Department of Energy-Washington, D.C.) requiring the reporting of waste inventories and space utilization for the Hanford Site Tank Farm tanks

  18. History of waste tank 1, 1954 through 1974

    International Nuclear Information System (INIS)

    McNatt, F.G.; Stevens, W.E.

    1978-10-01

    Tank 1 was placed in service as a receiver of high heat waste (HW) in October 1954. The supernate was removed from the tank in October 1961 and the tank began receiving low heat waste (LW) in January 1962. The LW supernate was decanted in October 1962 and prior to beginning a second HW filling in April 1963. The supernate from this HW filling was decanted twice in 1969. Sludge removal operations were conducted in May and August 1969 in order to use tank 1 for salt storage. The first evaporator concentrate receipt was in September 1969 and tank 1 has only been used as a salt storage tank since. Leakage from the tank into the annulus was discovered in February 1969. Deposits less than 1/4 inch deep of leaked waste were found on the pan floor. However, no leak sites have been found. Inspections of the tank interior and annulus were made by direct observation and by using a 40-ft optical periscope. Samples of sludge, supernate, tank vapors, and leaked material into the annulus were analyzed and tank temperature profiles were taken. Deflection measurements were made of the primary tank bottom knuckle plate while filling the tank with salt. Two vertical cooling coils have failed. Several equipment modifications and various equipment repairs were made. 18 figures, 2 tables

  19. Hanford Site Waste Storage Tank Information Notebook

    International Nuclear Information System (INIS)

    Husa, E.I.; Raymond, R.E.; Welty, R.K.; Griffith, S.M.; Hanlon, B.M.; Rios, R.R.; Vermeulen, N.J.

    1993-07-01

    This report provides summary data on the radioactive waste stored in underground tanks in the 200 East and West Areas at the Hanford Site. The summary data covers each of the existing 161 Series 100 underground waste storage tanks (500,000 gallons and larger). It also contains information on the design and construction of these tanks. The information in this report is derived from existing reports that document the status of the tanks and their materials. This report also contains interior, surface photographs of each of the 54 Watch List tanks, which are those tanks identified as Priority I Hanford Site Tank Farm Safety Issues in accordance with Public Law 101-510, Section 3137*

  20. Measures against concrete cracking in underground type light oil tank pit construction work

    International Nuclear Information System (INIS)

    Koike, Takeo; Kadowaki, Kazuhiko; Date, Masanao

    2017-01-01

    The underground type light oil tank pit set at Onagawa Nuclear Power Station is a tripartite underground pit structure made of reinforced concrete. This is a mass concrete made of deck slab / outer wall of 1.5 m in thickness and inner wall / top slab of 1.0 m in thickness. Since concrete placement season was July for the deck slab and October for the walls, the occurrence of thermal cracking was highly conceivable. As a result of investigating crack suppression measures based on the crack width of 0.2 mm or less as a guide, the application of fly ash cement and the addition of expansion material to the walls were judged effective and adopted. Thanks to these preliminary studies and careful construction control, it was possible to minimize the occurrence of cracks, but several through cracks of 0.2 mm or less were confirmed on part of the outer walls. As a countermeasure, repair by means of surface impregnation method was adopted, and quality and schedule could be secured. This paper outlines crack suppression measures and repair of the cracks that occurred after the implementation. (A.O.)

  1. Double-shell tank emergency pumping guide

    International Nuclear Information System (INIS)

    BROWN, M.H.

    1999-01-01

    This Double-Shell Tank Emergency Pumping Guide provides the preplanning necessary to expeditiously remove any waste that may leak from the primary tank to the secondary tank for Hanfords 28 DSTs. The strategy is described, applicable emergency procedures are referenced, and transfer routes and pumping equipment for each tank are identified

  2. Double-shell tank emergency pumping guide

    International Nuclear Information System (INIS)

    BROWN, M.H.

    1999-01-01

    This Double-Shell Tank Emergency Pumping Guide provides the preplanning necessary to expeditiously remove any waste that may leak from the primary tank to the secondary tank for Hanford's 28 DSTS. The strategy is described, applicable emergency procedures are referenced, and transfer routes and pumping equipment for each tank are identified

  3. Safe jack-up method permits repairs of tank bottoms and foundations

    International Nuclear Information System (INIS)

    de Wit, J.

    1991-01-01

    The oil and chemical industries use many thousands of steel tanks to store crude oil, oil products, and chemical liquids. The majority of these tanks are 30-40 years old. Tank bottoms are likely to begin leaking in the coming years, as these tanks get older. The European technique of jacking up a tank and repairing its foundation allows the thorough inspection of the underside of the tank bottom and the removal of saturated foundation material. And the possibility of soil and groundwater pollution is reduced to a minimum. With good, regular maintenance, the lifetime of a storage tank is very long. But experience has shown that special attention should be paid to the tank's bottom. Tank bottoms are only 5 or 6 mm thick, and in the last 10 years, an increasing number of leaks in tank bottoms have been reported. Tank foundations are affected by these leaks. This article describes the resulting procedure, which is used successfully in many European countries, but is not yet common in the U.S

  4. History of waste tank 13, 1956 through 1974

    International Nuclear Information System (INIS)

    Davis, T.L.; Tharin, D.W.; Lohr, D.R.

    1978-06-01

    Tank 13 was placed in service as a receiver of LW from the Building 221-H Purex process in December 1956. Five years later, the supernate was decanted to evaporator feed tank 21. It has since served as a transfer tank for HW supernate being sent to tank 21 and has received sludge removed from other tanks four times. The tank annulus has been inspected with an optical periscope and a lead-shielded camera. No indication of tank leakage had been seen through December 1974. However, subsequent to this report (on April 14, 1977), an arrested leak was discovered, making tank 13 the last of the four type II tanks to leak. Analytical samples of supernate and sludge have been taken. Tank 13 has had no cooling coil failures. Primary tank wall thicknesses, sludge level determinations, and temperature profiles have been obtained. Tank 13 has been included in various tests. Equipment modifications and various equipment repairs were made. 11 figures, 2 tables

  5. Quench tank in-leakage diagnosis at St. Lucie

    International Nuclear Information System (INIS)

    Price, J.E.; Au-Yang, M.K.; Beckner, D.A.; Vickery, A.N.

    1996-01-01

    In February 1995, leakage into the quench tank of the St. Lucie Nuclear Station Unit 1 was becoming an operational concern. This internal leak resulted in measurable increases in both the temperature and level of the quench tank water, and was so severe that, if the trend continued, plant shut down would be necessary. Preliminary diagnosis based on in-plant instrumentation indicated that any one of 11 valves might be leaking into the quench tank. This paper describes the joint effort by two teams of engineers--one from Florida Power ampersand Light, the other from Framatome Technologies--to identify the sources of the leak, using the latest technology developed for valve diagnosis

  6. Feedback regarding leaks in pipe work

    International Nuclear Information System (INIS)

    Guerville, C.; Boudouin, E.

    2011-01-01

    Contaminated effluent from nuclear medicine departments is stored in decay tanks before being discharged via the sewage system. Generally speaking, these tanks are located outside hospital wards, within the hospital's maintenance rooms. Pipes leading from the evacuation points (e.g. toilets in isolation wards) to the tanks may nonetheless pass through various other parts of the hospital premises (wards, corridors, offices, etc.). Should a leak occur in any of these pipes, this may impact on the public, workers or the environment. (author)

  7. Measurement of Submerged Oil/Gas Leaks using ROV Video

    Science.gov (United States)

    Shaffer, Franklin; de Vera, Giorgio; Lee, Kenneth; Savas, Ömer

    2013-11-01

    Drilling for oil or gas in the Gulf of Mexico is increasing rapidly at depths up to three miles. The National Commission on the Deepwater Horizon Oil Leak concluded that inaccurate estimates of the leak rate from the Deepwater Horizon caused an inadequate response and attempts to cap the leak to fail. The first response to a submerged oil/gas leak will be to send a Remotely Operated Vehicle (ROV) down to view the leak. During the response to the Deepwater Horizon crisis, the authors Savas and Shaffer were members of the Flow Rate Technical Group's Plume Team who used ROV video to develop the FRTG's first official estimates of the oil leak rate. Savas and Shaffer developed an approach using the larger, faster jet features (e.g., turbulent eddies, vortices, entrained particles) in the near-field developing zone to measure discharge rates. The authors have since used the Berkeley Tow Tank to test this approach on submerged dye-colored water jets and compressed air jets. Image Correlation Velocimetry has been applied to measure the velocity of visible features. Results from tests in the Berkeley Tow Tank and submerged oil jets in the OHMSETT facility will be presented.

  8. DOUBLE SHELL TANK EMERGENCY PUMPING GUIDE

    International Nuclear Information System (INIS)

    REBERGER, D.W.

    2006-01-01

    This document provides preplanning necessary to expeditiously remove any waste that may leak from the primary tank to the secondary tank for Hanford's 28 DSTs. The strategy is described, applicable emergency procedures are referenced, and transfer routes and pumping equipment for each tank are identified

  9. History of waste tank 24, 1962--1974

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1979-04-01

    Tank 24 was placed in service in April 1963 receiving HW concentrate from the Building 242-H evaporator. The tank was filled by October 1965. In October 1966 the cooled concentrate supernate was decanted. The tank was again filled with concentrate by March 1967, then decanted in June 1967 and refilled by July 1967. Since that time the tank has remained in service storing LW and HW salt and receiving spent zeolite from the cesium removal column (CRC). In April 1973 an influx of slightly contaminated water in the bottom leak detection sump was observed. The tank was inspected with an optical periscope and numerous tests and investigations were conducted but the source of the contaminated water was not determined. However, subsequent to this report period a D 2 O tracer test in tank 21 which also experienced an influx of contaminated water into its bottom sump provided conclusive evidence of communication between the tank vapor space and the bottom leak detection sump. The D 2 O tracer test was documented in DPSPU 76-11-19. Inspections of the tank interior were performed by direct observation and photography using an optical periscope inserted through access risers in the roof. Samples of the vapor condensate and supernate in the tank, and liquid collected in the bottom leak detection sump were analyzed. Numerous temperature profiles were taken and several equipment modifications and repairs were made

  10. Corrosion analysis of decommissioned carbon steel waste water tanks at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Soo, P.; Roberts, T.C.

    1995-07-01

    A corrosion analysis was carried out on available sections of carbon steels taken from two decommissioned radioactive waste water tanks at Brookhaven National Laboratory. One of the 100,000 gallon tanks suffered from a pinhole failure in the wall which was subsequently patched. From the analysis it was shown that this leak, and two adjacent leaks were initiated by a discarded copper heating coil that had been dropped into the tank during service. The failure mechanism is postulated to have been galvanic attack at points of contact between the tank structure and the coil. Other leaks in the two tanks are also described in this report

  11. 30 CFR 57.4401 - Storage tank foundations.

    Science.gov (United States)

    2010-07-01

    ... leaks caused by tanks settling. ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Storage tank foundations. 57.4401 Section 57... and Control Flammable and Combustible Liquids and Gases § 57.4401 Storage tank foundations. Fixed...

  12. Corrective action baseline report for underground storage tank 2331-U Building 9201-1

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tank (UST) 2331-U at the Building 9201-1 Site. Progress in support of the Building 9201-1 Site has included monitoring well installation and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the Building 9201-1 site and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes the summary of additional monitoring well installation activities and the results of baseline groundwater sampling. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

  13. 40 CFR 267.200 - What must I do in case of a leak or a spill?

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false What must I do in case of a leak or a... UNDER A STANDARDIZED PERMIT Tank Systems § 267.200 What must I do in case of a leak or a spill? If there has been a leak or a spill from a tank system or secondary containment system, or if either system is...

  14. Double shell tanks emergency pumping plan

    International Nuclear Information System (INIS)

    Tangen, M.J.

    1994-01-01

    At the request of the Department of Energy (DOE), a formal plan for the emergency transfer of waste from a leaking double shell tank to a designated receiver tank has been developed. This plan is in response to the priority 2 safety issue ''Response to a leaking double-shell tank'' in the DOE Report to Congress, 1991. The plan includes the tanks in four of the east tank farms and one of the west farms. The background information and supporting calculations used for the creation of the emergency plan are discussed in this document. The scope of this document is all of the double shell tanks in the AN, AP, AW, AY, and SY farms. The transfer lines, flush pits, and valve pits involved in the transfer of waste between these farms are also included in the scope. Due to the storage of high heat waste, AZ farm is excluded at this time

  15. Development of an in situ method to define the rheological properties of slurries and sludges stored in underground tanks

    International Nuclear Information System (INIS)

    Heath, W.O.

    1987-04-01

    A method for measuring the in situ flow properties of high-level radioactive waste (HLW) sludges has been developed at Pacific Northwest Laboratory, along with a preconceptual design for a shear vane device that can be installed in underground HLW storage tanks and used to make those measurements remotely. The data obtained with this device will assist in the design of mixing equipment used to resuspend and remove HLW sludges from their storage tanks for downstream processing. This method is also suitable for remotely characterizing other types of waste sludges and slurries. Commonly available viscometric methods were adapted to allow characterization of sludge samples in the laboratory such that the laboratory and in-tank data can be directly compared (scaled up). Procedures for conducting measurements and analyzing the results in terms of useful mathematical models describing both start-up and steady-state flow behavior are presented, as is a brief tutorial on the types of flow behavior that can be exhibited by tank sludges. 30 refs., 36 figs., 14 tabs

  16. Tank farm potential ignition sources

    International Nuclear Information System (INIS)

    Scaief, C.C. III.

    1996-01-01

    This document identifies equipment, instrumentation, and sensors that are located in-tank as well as ex-tank in areas that may have communication paths with the tank vapor space. For each item, and attempt is made to identify the potential for ignition of flammable vapors using a graded approach. The scope includes all 177 underground storage tanks

  17. Waste Transfer Leaks Control Decision Record

    International Nuclear Information System (INIS)

    RYAN, G.W.

    2000-01-01

    Control decision meetings for Waste Transfer Leaks were held on April 24,25,26, and 27, 2000. The agenda for the control decision meetings is included in Appendix A, and attendee lists are included in Appendix B. The purpose of the control decision meetings was to review and revise previously selected controls for the prevention or mitigation of waste transfer leak accidents. Re-evaluation of the controls is warranted due to revisions in the hazard and accident analysis for these Tank Farm events. In particular, calculated radiological consequences are significantly reduced from those currently reported in the Final Safety Analysis Report (FSAR). Revised hazard and accident analysis and a revised control recommendation will be reflected in an Authorization Basis Amendment to be submitted at the Department of Energy, Office of River Protection's (ORP's) request by June 30, 2000 to satisfy ORP Performance Incentive (PI) 2.1.1, Revision 1, ''Authorization Basis Management Process Efficiency Improvement''. The scope of the control decision meetings was to address all waste transfer leak-related hazardous conditions identified in the Tank Farm hazard analysis database, excluding those associated with the use of the Replacement Cross-Site Transfer System (RCSTS) slurry line and sluicing of Tank 241-C-106, which is addressed in FSAR Addendum 1. The scope of this control decision process does include future waste feed delivery waste transfer operations

  18. 49 CFR 230.115 - Feed water tanks.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Feed water tanks. 230.115 Section 230.115... Tenders Steam Locomotive Tanks § 230.115 Feed water tanks. (a) General provisions. Tanks shall be maintained free from leaks, and in safe and suitable condition for service. Suitable screens must be provided...

  19. Design of second generation Hanford tank corrosion monitoring system

    International Nuclear Information System (INIS)

    Edgemon, G.L.

    1998-01-01

    The Hanford Site has 177 underground waste tanks that store approximately 253 million liters of radioactive waste from 50 years of plutonium production. Twenty-eight tanks have a double shell and are constructed of welded ASTM A537-Class 1 (UNS K02400), ASTM A515-Grade 60 (UNS K02401), or ASTM A516-Grade 60 (UNS K02100) material. The inner tanks of the double-shell tanks (DSTS) were stress relieved following fabrication. One hundred and forty-nine tanks have a single shell, also constructed of welded mild steel, but not stress relieved following fabrication. Tank waste is in liquid, solid, and sludge forms. Tanks also contain a vapor space above the solid and liquid waste regions. The composition of the waste varies from tank to tank but generally has a high pH (>12) and contains sodium nitrate, sodium hydroxide, sodium nitrite, and other minor radioactive constituents resulting from plutonium separation processes. Leaks began to appear in the single-shell tanks shortly after the introduction of nitrate-based wastes in the 1950s. Leaks are now confirmed or suspected to be present in a significant number of single-shell tanks. The probable modes of corrosion failures are reported as nitrate stress corrosion cracking (SCC) and pitting. Previous efforts to monitor internal corrosion of waste tank systems have included linear polarization resistance (LPR) and electrical resistance techniques. These techniques are most effective for monitoring uniform corrosion, but are not well suited for detection of localized corrosion (pitting and SCC). The Savannah River Site (SRS) investigated the characterization of electrochemical noise (EN) for monitoring waste tank corrosion in 1993, but the tests were not conclusive. The SRS effort has recently been revived and additional testing is underway. For many years, EN has been observed during corrosion and other electrochemical reactions, and the phenomenon is well established. Typically, EN consists of low frequency (< 1 Hz) and

  20. Tank Farm surveillance and waste status summary report for April 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-07-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations

  1. 46 CFR 35.05-15 - Tank vessel security-TB/ALL.

    Science.gov (United States)

    2010-10-01

    ... scuppers, if any, unobstructed; meets any loadline or freeboard requirements; and neither leaks cargo into the water, voids, or cofferdams nor leaks water into the tanks, voids, or cofferdams; (ii) Ensuring... checks are made of every tank barge in the tow for leakage of cargo into the water, voids, or cofferdams...

  2. 33 CFR 183.510 - Fuel tanks.

    Science.gov (United States)

    2010-07-01

    ... SAFETY BOATS AND ASSOCIATED EQUIPMENT Fuel Systems Equipment Standards § 183.510 Fuel tanks. (a) Each fuel tank in a boat must have been tested by its manufacturer under § 183.580 and not leak when...

  3. Tank farm surveillance and waste status report for June 1991

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1991-09-01

    This report is Westinghouse Hanford Company's official inventory for radioactive stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. The intent of the report is to provide data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and to provide supplemental information regarding tank surveillance anomalies and ongoing investigations. 2 figs., 8 tabs

  4. Tank farm surveillance and waste status report for July 1991

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1991-09-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. The intent of the report is to provide data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and to provide supplemental information regarding tank surveillance anomalies and ongoing investigations. 1 fig., 8 tabs

  5. Steam reforming as a method to treat Hanford underground storage tank (UST) wastes

    International Nuclear Information System (INIS)

    Miller, J.E.; Kuehne, P.B.

    1995-07-01

    This report summarizes a Sandia program that included partnerships with Lawrence Livermore National Laboratory and Synthetica Technologies, Inc. to design and test a steam reforming system for treating Hanford underground storage tank (UST) wastes. The benefits of steam reforming the wastes include the resolution of tank safety issues and improved radionuclide separations. Steam reforming destroys organic materials by first gasifying, then reacting them with high temperature steam. Tests indicate that up to 99% of the organics could be removed from the UST wastes by steam exposure. In addition, it was shown that nitrates in the wastes could be destroyed by steam exposure if they were first distributed as a thin layer on a surface. High purity alumina and nickel alloys were shown to be good candidates for materials to be used in the severe environment associated with steam reforming the highly alkaline, high nitrate content wastes. Work was performed on designing, building, and demonstrating components of a 0.5 gallon per minute (gpm) system suitable for radioactive waste treatment. Scale-up of the unit to 20 gpm was also considered and is feasible. Finally, process demonstrations conducted on non-radioactive waste surrogates were carried out, including a successful demonstration of the technology at the 0.1 gpm scale

  6. Tank farm surveillance and waste status summary report for May 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-08-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations

  7. Cryograb: A Novel Approach to the Retrieval of Waste from Underground Storage Tanks - 13501

    Energy Technology Data Exchange (ETDEWEB)

    O' Brien, Luke; Baker, Stephen; Bowen, Bob [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom); Mallick, Pramod; Smith, Gary [US Department of Energy (United States); King, Bill [Savannah River National Laboratory (United States); Judd, Laurie [NuVision Engineering (United States)

    2013-07-01

    The UK's National Nuclear Laboratory (NNL) is investigating the use of cryogenic technology for the recovery of nuclear waste. Cryograb, freezing the waste on a 'cryo-head' and then retrieves it as a single mass which can then be treated or stabilized as necessary. The technology has a number of benefits over other retrieval approaches in that it minimizes sludge disturbance thereby reducing effluent arising and it can be used to de-water, and thereby reduce the volume of waste. The technology has been successfully deployed for a variety of nuclear and non-nuclear waste recovery operations. The application of Cryograb for the recovery of waste from US underground storage tanks is being explored through a US DOE International Technology Transfer and Demonstration programme. A sample deployment being considered involves the recovery of residual mounds of sludge material from waste storage tanks at Savannah River. Operational constraints and success criteria were agreed prior to the completion of a process down selection exercise which specified the preferred configuration of the cryo-head and supporting plant. Subsequent process modeling identified retrieval rates and temperature gradients through the waste and tank infrastructure. The work, which has been delivered in partnership with US DOE, SRNL, NuVision Engineering and Frigeo AB has demonstrated the technical feasibility of the approach (to TRL 2) and has resulted in the allocation of additional funding from DOE to take the programme to bench and cold pilot-scale trials. (authors)

  8. Detection of underground water distribution piping system and leakages using ground penetrating radar (GPR)

    Science.gov (United States)

    Amran, Tengku Sarah Tengku; Ismail, Mohamad Pauzi; Ahmad, Mohamad Ridzuan; Amin, Mohamad Syafiq Mohd; Sani, Suhairy; Masenwat, Noor Azreen; Ismail, Mohd Azmi; Hamid, Shu-Hazri Abdul

    2017-01-01

    A water pipe is any pipe or tubes designed to transport and deliver water or treated drinking with appropriate quality, quantity and pressure to consumers. The varieties include large diameter main pipes, which supply entire towns, smaller branch lines that supply a street or group of buildings or small diameter pipes located within individual buildings. This distribution system (underground) is used to describe collectively the facilities used to supply water from its source to the point of usage. Therefore, a leaking in the underground water distribution piping system increases the likelihood of safe water leaving the source or treatment facility becoming contaminated before reaching the consumer. Most importantly, leaking can result in wastage of water which is precious natural resources. Furthermore, they create substantial damage to the transportation system and structure within urban and suburban environments. This paper presents a study on the possibility of using ground penetrating radar (GPR) with frequency of 1GHz to detect pipes and leakages in underground water distribution piping system. Series of laboratory experiment was designed to investigate the capability and efficiency of GPR in detecting underground pipes (metal and PVC) and water leakages. The data was divided into two parts: 1. detecting/locating underground water pipe, 2. detecting leakage of underground water pipe. Despite its simplicity, the attained data is proved to generate a satisfactory result indicating GPR is capable and efficient, in which it is able to detect the underground pipe and presence of leak of the underground pipe.

  9. EMSP Project 70070: Reactivity of Primary Soil Minerals and Secondary Precipitates Beneath Leaking Hanford Waste Tanks - Final Report

    International Nuclear Information System (INIS)

    Nagy, Kathryn L.

    2004-01-01

    Since the late 1950s, leaks from 67 single-shell tanks at the Hanford Site have released about 1 million curies to the underlying sediments. The radioactive material was contained in water-based solutions generally characterized as having high pH values (basic solutions), high nitrate and nitrite concentrations, and high aluminum concentrations. The solutions were also hot, in some cases at or near boiling, as well as complex and highly variable in composition reflecting solutions obtained from multiple methods of reprocessing spent nuclear fuel. In order to understand the observed and probable distribution of radionuclides in the ground at Hanford, major reactions that likely occurred between the leaked fluids and the sediment minerals were investigated in laboratory experiments simulating environmental conditions. Reactions involving the dissolution of quartz and biotite and the simultaneous formation of new minerals were quantified at controlled pH values and temperature. Result s show that the dissolution of quartz and formation of new zeolite-like minerals could have altered the flow path of ground water and contaminant plumes and provided an uptake mechanism for positively-charged soluble radionuclides, such as cesium. The dissolution of biotite, a layered-iron-aluminum-silicate mineral, provided iron in a reduced form that could have reacted with negatively-charged soluble chromium, a toxic component of the wastes, to cause its reduction and precipitation as a new reduced-chromium mineral. The quantity of iron released in the experiments is sufficient to explain observations of reductions in dissolved chromium concentration in a plume beneath one Hanford tank. Fundamental data obtained in the project are the rates of the reactions at variable temperatures and pHs. Fundamental data were also obtained on aspects of the surface reactivity of clay or layered-silicate minerals, a small proportion of the total mass of the sediment minerals, but a large proportion

  10. Tank 241-BY-108 tank characterization plan

    International Nuclear Information System (INIS)

    Carpenter, B.C.

    1994-01-01

    The sampling and analytical needs associated with the 51 Hanford Site underground storage tanks classified on one or more of the four Watch Lists (ferrocyanide, organic, flammable gas, and high heat), and the safety screening of all 177 tanks have been identified through the Data Quality Objective (DQO) process. DQOs identity information needed by a program group in the Tank Waste Remediation System concerned with safety issues, regulatory requirements, or the transporting and processing of tank waste. This Tank Characterization Plan will identify characterization objectives for tank BY-108 pertaining to sample collection, sample preparation and analysis, and laboratory analytical evaluation and reporting requirements. In addition, an estimate of the current contents and status of the tank is given. Single-shell tank BY-108 is classified as a Ferrocyanide Watch List tank. The tank was declared an assumed leaker and removed from service in 1972; interim stabilized was completed in February 1985. Although not officially an Organic Watch List tank, restrictions have been placed on intrusive operations by Standing Order number-sign 94-16 (dated 09/08/94) since the tank is suspected to contain or to have contained a floating organic layer

  11. Overview Of Enhanced Hanford Single-Shell Tank (SST) Integrity Project - 12128

    International Nuclear Information System (INIS)

    Venetz, T.J.; Boomer, K.D.; Washenfelder, D.J.; Johnson, J.B.

    2012-01-01

    To improve the understanding of the single-shell tanks integrity, Washington River Protection Solutions, LLC, the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank (SST) Integrity Project in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The change package identified two phases of work for SST integrity. The initial phase has been focused on efforts to envelope the integrity of the tanks. The initial phase was divided into two primary areas of investigation: structural integrity and leak integrity. If necessary based on the outcome from the initial work, a second phase would be focused on further definition of the integrity of the concrete and liners. Combined these two phases are designed to support the formal integrity assessment of the Hanford SSTs in 2018 by Independent Qualified Registered Engineer. The work to further define the DOE's understanding of the structural integrity SSTs involves preparing a modern Analysis of Record using a finite element analysis program. Structural analyses of the SSTs have been conducted since 1957, but these analyses used analog calculation, less rigorous models, or focused on individual structures. As such, an integrated understanding of all of the SSTs has not been developed to modern expectations. In support of this effort, other milestones will address the visual inspection of the tank concrete and the collection of concrete core samples from the tanks for analysis of

  12. Nuclear waste

    International Nuclear Information System (INIS)

    1989-01-01

    This paper reviews the Department of Energy's management of underground single-shell waste storage tanks at its Hanford, Washington, site. The tanks contain highly radioactive and nonradioactive hazardous liquid and solid wastes from nuclear materials production. Hundreds of thousands of gallons of these wastes have leaked, contaminating the soil, and a small amount of leaked waste has reached the groundwater. DOE does not collect sufficient data to adequately trace the migration of the leaks through the soil, and studies predicting the eventual environmental impact of tank leaks do not provide convincing support for DOE's conclusion that the impact will be low or nonexistent. DOE can do more to minimize the environmental risks associated with leaks. To reduce the environmental impact of past leaks, DOE may be able to install better ground covering over the tanks to reduce the volume of precipitation that drains through the soil and carries contaminants toward groundwater

  13. Recycling of underground storage tanks: a way-out to the risks; Reciclagem de tanques de combustiveis: solucoes para os riscos envolvidos

    Energy Technology Data Exchange (ETDEWEB)

    Duarte, Cristiano J.P.; Santos, Joao David [Companhia Brasileira de Petroleo Ipiranga, Porto Alegre, RS (Brazil)

    2004-07-01

    In petrol stations, the removal of an underground storage tank happens when it becomes unnecessary or inappropriate. Among the several reasons which motivate this removal, we can mention the environmental license process. According to the Resolution CONAMA 273/00, all the petrol stations are subjected to the previous, installation and operation licenses (including the ones in operation). This will cause the substitution of a large number of tanks all over Brazil along the following years. However, so that the license process can be successful, it is necessary that the environmental impacts caused by its implementation are properly managed, avoiding safety problems and providing that there won't be any damage to the environment. This work shows alternatives for the recycling of the tank, the destination of residue and the maintenance of safety all over the process. (author)

  14. Localization of leaks in underground pipes with the application of radioactive isotopes

    International Nuclear Information System (INIS)

    Klupa, A.; Morawiec, J.

    1983-01-01

    A method of leaks localization on gas pipe-lines during resistance and tightness tests was elaborated. The leaks were localized using tracer technique. Sodium 24 was used as a tracer for short sections of the pipe-line (up to 30 km). Only 1 m 3 of water with a tracer was introduced into the pipe-line. A measuring probe was also put into pipe-line. All leaks were detected and the method appeared useful. For the longer sections of the pipe-line iodine 131 ought to be used. (A.S.)

  15. Radioactive tank waste remediation focus area

    International Nuclear Information System (INIS)

    1996-08-01

    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

  16. Radioactive tank waste remediation focus area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    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.

  17. History of waste tank 12, 1956 through 1974

    International Nuclear Information System (INIS)

    Davis, T.L.; Tharin, D.W.; Lohr, D.R.

    1978-09-01

    Tank 12 was placed in service as a receiver for high heat waste (HW) in September 1956 and continued in this service through 1974. From August 1963 through December 1974, the supernate was decanted (leaving the sludge) five times to allow the tank to be refilled with HW. Inspections have been made and photographs taken in the annular space with an optical periscope and a lead-shielded camera. A salt-encrusted leak site was discovered in May 1974. No other leak sites have been found. Analytical samples have been taken of sludge, supernate, and vapor. Primary tank wall thickness, heat transfer coefficient measurements, and profiles of tank temperature differences have been obtained. Several modifications to equipment and various equipment repairs were made

  18. Natural convection and vapor loss during underground waste storage

    International Nuclear Information System (INIS)

    Plys, M.G.; Epstein, M.; Turner, D.

    1996-01-01

    Natural convection and vapor loss from underground waste storage tanks is examined here. Stability criteria are provided for the onset of natural convection flow within the headspace of a tank, and between tanks and the environment. The flowrate is quantified and used to predict vapor losses during storage

  19. Monitoring underground water leakage pattern by ground penetrating radar (GPR) using 800 MHz antenna frequency

    Science.gov (United States)

    Amran, T. S. T.; Ismail, M. P.; Ahmad, M. R.; Amin, M. S. M.; Ismail, M. A.; Sani, S.; Masenwat, N. A.; Basri, N. S. M.

    2018-01-01

    Water is the most treasure natural resources, however, a huge amount of water are lost during its distribution that leads to water leakage problem. The leaks meant the waste of money and created more economic loss to treat and fix the damaged pipe. Researchers and engineers have put tremendous attempts and effort, to solve the water leakage problem especially in water leakage of buried pipeline. An advanced technology of ground penetrating radar (GPR) has been established as one of the non-destructive testing (NDT) method to detect the underground water pipe leaking. This paper focuses on the ability of GPR in water utility field especially on detection of water leaks in the underground pipeline distribution. A series of laboratory experiments were carried out using 800-MHz antenna, where the performance of GPR on detecting underground pipeline and locating water leakage was investigated and validated. A prototype to recreate water-leaking system was constructed using a 4-inch PVC pipe. Different diameter of holes, i.e. ¼ inch, ½ inch, and ¾ inch, were drilled into the pipe to simulate the water leaking. The PVC pipe was buried at the depth of 60 cm into the test bed that was filled with dry sand. 15 litres of water was injected into the PVC pipe. The water leakage patterns in term of radargram data were gathered. The effectiveness of the GPR in locating the underground water leakage was ascertained, after the results were collected and verified.

  20. 1990 waste tank inspection program

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1990-01-01

    Aqueous radioactive wastes from Savannah River Site separations processes are contained in large underground carbon steel tanks. Tank conditions are evaluated by inspection using periscopes, still photography, and video systems for visual imagery. Inspections made in 1990 are the subject of this report

  1. OVERVIEW OF ENHANCED HANFORD SINGLE-SHELL TANK (SST) INTEGRITY PROJECT - 12128

    Energy Technology Data Exchange (ETDEWEB)

    VENETZ TJ; BOOMER KD; WASHENFELDER DJ; JOHNSON JB

    2012-01-25

    To improve the understanding of the single-shell tanks integrity, Washington River Protection Solutions, LLC, the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank (SST) Integrity Project in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The change package identified two phases of work for SST integrity. The initial phase has been focused on efforts to envelope the integrity of the tanks. The initial phase was divided into two primary areas of investigation: structural integrity and leak integrity. If necessary based on the outcome from the initial work, a second phase would be focused on further definition of the integrity of the concrete and liners. Combined these two phases are designed to support the formal integrity assessment of the Hanford SSTs in 2018 by Independent Qualified Registered Engineer. The work to further define the DOE's understanding of the structural integrity SSTs involves preparing a modern Analysis of Record using a finite element analysis program. Structural analyses of the SSTs have been conducted since 1957, but these analyses used analog calculation, less rigorous models, or focused on individual structures. As such, an integrated understanding of all of the SSTs has not been developed to modern expectations. In support of this effort, other milestones will address the visual inspection of the tank concrete and the collection of concrete core samples from the tanks for analysis

  2. Tank Closure Progress at the Department of Energy's Idaho National Engineering Laboratory Tank Farm Facility

    International Nuclear Information System (INIS)

    Butterworth, St.W.; Shaw, M.R.

    2009-01-01

    Significant progress continued at the U.S. Department of Energy (DOE) Idaho National Laboratory (INL) with the completion of the closure process to empty, clean and close radioactive liquid waste storage tanks at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF). The TFF includes eleven 1,135.6-kL (300,000-gal) underground stainless steel storage tanks and four smaller, 113.5-kL (30,000-gal) stainless steel tanks, along with tank vaults, interconnecting piping, and ancillary equipment. The TFF tanks had historically been used to store a variety of radioactive liquid waste, including wastes associated with past spent nuclear fuel reprocessing. Four of the large storage tanks remain in use for waste storage while the other seven 1,135.6-kL (300,000-gal) tanks and the four 113.5-kL (30,000-gal) tanks have been emptied of waste, cleaned and filled with grout. Recent issuance of an Amended Record of Decision (ROD) in accordance with the National Environmental Policy Act, and a Waste Determination complying with Section 3116 of the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, allowed commencement of grouting activities on the cleaned tanks. The first three 113.5-kL (30,000-gal) tanks were grouted in the Fall of 2006 and the fourth tank and the seven 1,135.6-kL (300,000-gal) tanks were filled with grout in 2007 to provide long-term stability. During 2008 over seven miles of underground process piping along with associated tank valve boxes and secondary containment systems was stabilized with grout. Lessons learned were compiled and implemented during the closure process and will be utilized on the remaining four 1,135.6-kL (300,000-gal) underground stainless steel storage tanks. Significant progress has been made to clean and close emptied tanks at the INTEC TFF. Between 2002 and 2005, seven of the eleven 1,135.6-kL (300,000-gal) tanks and all four 113.5-kL (30,000-gal) tanks were cleaned and prepared

  3. Initial laboratory studies into the chemical and radiological aging of organic materials in underground storage tanks at the Hanford Complex

    International Nuclear Information System (INIS)

    Samuels, W.D.; Camaioni, D.M.; Babad, H.

    1994-01-01

    The underground storage tanks at the Hanford Complex contain wastes generated over many years from plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct bearing on several specific safety issues, including potential energy releases from these tanks. The major portion of organic materials that have been added to the tanks consists of tributyl phosphate, dibutyl phosphate, butyl alcohol, hexone (methyl isobutyl ketone), normal paraffin hydrocarbons (NPH), ethylenediaminetetraacetic acid (EDTA), hydroxyethylethylenediaminetriadetic acid (HEDTA), other complexants, and lesser quantities of ion exchange polymers and minor organic compounds. A study of how thermal and radiological processes that may have changed the composition of organic tanks constituents has been initiated after a review of the open literature revealed little information was available about the rates and products of these processes under basic pH conditions. This paper will detail the initial findings as they relate to gas generation, e.g. H 2 , CO, NH 3 , CH 4 , and to changes in the composition of the organic and inorganic components brought about by ''Aging'' processes

  4. Tank 244A tank characterization plan

    International Nuclear Information System (INIS)

    Schreiber, R.D.

    1994-01-01

    The Double-Shell Tank (DST) System currently receives waste from the Single-Shell Tank (SST) System in support of SST stabilization efforts or from other on-site facilities which generate or store waste. Waste is also transferred between individual DSTs. The mixing or commingling of potentially incompatible waste types at the Hanford Site must be addressed prior to any waste transfers into the DSTs. The primary goal of the Waste Compatibility Program is to prevent the formation of an Unreviewed Safety Question (USQ) as a result of improper waste management. Tank 244A is a Double Contained Receiver Tank (DCRT) which serves as any overflow tank for the East Area Farms. Waste material is able to flow freely between the underground storage tanks and tank 244A. Therefore, it is necessary to test the waste in tank 244A for compatibility purposes. Two issues related to the overall problem of waste compatibility must be evaluated: Assurance of continued operability during waste transfer and waste concentration and Assurance that safety problems are not created as a result of commingling wastes under interim storage. The results of the grab sampling activity prescribed by this Tank Characterization Plan shall help determine the potential for four kinds of safety problems: criticality, flammable gas accumulation, energetics, and corrosion and leakage

  5. 241-AY-102 Leak Detection Pit Drain Line Inspection Report

    International Nuclear Information System (INIS)

    Boomer, Kayle D.; Engeman, Jason K.; Gunter, Jason R.; Joslyn, Cameron C.; Vazquez, Brandon J.; Venetz, Theodore J.; Garfield, John S.

    2014-01-01

    This document provides a description of the design components, operational approach, and results from the Tank AY-102 leak detection pit drain piping visual inspection. To perform this inspection a custom robotic crawler with a deployment device was designed, built, and operated by IHI Southwest Technologies, Inc. for WRPS to inspect the 6-inch leak detection pit drain line

  6. Underground storage tank - Integrated Demonstration Technical Task Plan master schedule

    International Nuclear Information System (INIS)

    Johnson, C.M.

    1994-08-01

    This document provides an integrated programmatic schedule (i.e., Master Schedule) for the U.S. Department of Energy (DOE) Underground Storage Tank-Integrated Demonstration (UST-ID) Program. It includes top-level schedule and related information for the DOE Office of Technology Development (EM-50) UST-ID activities. The information is based upon the fiscal year (FY) 1994 technical task plans (TTPS) and has been prepared as a baseline information resource for program participants. The Master Schedule contains Level 0 and Level 1 program schedules for the UST-ID Program. This document is one of a number of programmatic documents developed to support and manage the UST-ID activities. It is composed of the following sections: Program Overview - provides a summary background of the UST-ID Program. This summary addresses the mission, scope, and organizational structure of the program; Activity Description - provides a programmatic description of UST-ID technology development activities and lists the key milestones for the UST-ID systems. Master Schedules - contains the Level 0 and Level 1 programmatic schedules for the UST-ID systems. References - lists the UST-ID programmatic documents used as a basis for preparing the Master Schedule. The appendixes contain additional details related to site-specific technology applications

  7. Nondestructive examination of DOE high-level waste storage tanks

    International Nuclear Information System (INIS)

    Bush, S.; Bandyopadhyay, K.; Kassir, M.; Mather, B.; Shewmon, P.; Streicher, M.; Thompson, B.; van Rooyen, D.; Weeks, J.

    1995-01-01

    A number of DOE sites have buried tanks containing high-level waste. Tanks of particular interest am double-shell inside concrete cylinders. A program has been developed for the inservice inspection of the primary tank containing high-level waste (HLW), for testing of transfer lines and for the inspection of the concrete containment where possible. Emphasis is placed on the ultrasonic examination of selected areas of the primary tank, coupled with a leak-detection system capable of detecting small leaks through the wall of the primary tank. The NDE program is modelled after ASME Section XI in many respects, particularly with respects to the sampling protocol. Selected testing of concrete is planned to determine if there has been any significant degradation. The most probable failure mechanisms are corrosion-related so that the examination program gives major emphasis to possible locations for corrosion attack

  8. Light duty utility arm deployment in Hanford tank T-106

    International Nuclear Information System (INIS)

    Kiebel, G.R.

    1997-07-01

    An existing gap in the technology for the remediation of underground waste storage tanks filled by the Light Duty Utility Arm (LDUA) System. On September 27 and 30, 1996, the LDUA System was deployed in underground storage tank T-106 at Hanford. The system performed successfully, satisfying all objectives of the in-tank operational test (hot test); performing close-up video inspection of features of tank dome, risers, and wall; and grasping and repositioning in-tank debris. The successful completion of hot testing at Hanford means that areas of tank structure and waste surface that were previously inaccessible are now within reach of remote tools for inspection, waste analysis, and small-scale retrieval. The LDUA System has become a new addition to the arsenal of technologies being applied to solve tank waste remediation challenges

  9. Light duty utility arm deployment in Hanford tank T-106

    Energy Technology Data Exchange (ETDEWEB)

    Kiebel, G.R.

    1997-07-01

    An existing gap in the technology for the remediation of underground waste storage tanks filled by the Light Duty Utility Arm (LDUA) System. On September 27 and 30, 1996, the LDUA System was deployed in underground storage tank T-106 at Hanford. The system performed successfully, satisfying all objectives of the in-tank operational test (hot test); performing close-up video inspection of features of tank dome, risers, and wall; and grasping and repositioning in-tank debris. The successful completion of hot testing at Hanford means that areas of tank structure and waste surface that were previously inaccessible are now within reach of remote tools for inspection, waste analysis, and small-scale retrieval. The LDUA System has become a new addition to the arsenal of technologies being applied to solve tank waste remediation challenges.

  10. Supporting document for the Southeast Quadrant historical tank content estimate report for SY-tank farm

    International Nuclear Information System (INIS)

    Brevick, C.H.; Gaddis, L.A.; Consort, S.D.

    1995-01-01

    Historical Tank Content Estimate of the Southeast Quadrant provides historical evaluations on a tank by tank basis of the radioactive mixed wastes stored in the underground double-shell tanks of the Hanford 200 East and West Areas. This report summarizes historical information such as waste history, temperature profiles, psychrometric data, tank integrity, inventory estimates and tank level history on a tank by tank basis. Tank Farm aerial photos and in-tank photos of each tank are provided. A brief description of instrumentation methods used for waste tank surveillance are included. Components of the data management effort, such as Waste Status and Transaction Record Summary, Tank Layer Model, Supernatant Mixing Model, Defined Waste Types, and Inventory Estimates which generate these tank content estimates, are also given in this report

  11. Radiation leaking protection device

    International Nuclear Information System (INIS)

    Sunami, Yoshio; Mitsumori, Kojiro

    1980-01-01

    Purpose: To prevent radioactivity from leaking outside of a reactor container by way of pipeways passing therethrough, by supplying pressurized fluid between each of a plurality of valves for separating the pipeways. Constitution: Pressurized fluid is supplied between each of a plurality of valves for separating pipeways. For instance, water in a purified water tank is pressurized by a pressure pump and the pressure of the pressurized water is controlled by a differential pressure detector, a pressure controller and a pressure control valve. In the case if a main steam pipe is ruptured outside of the reactor container or to be repaired, the separation valves are wholly closed and then the pressurizing device is actuated to supply pressurized water containing no radioactivity from the purified water tank to the position between the valves. The pressure in the pressurized water is controlled such that it is always higher by a predetermined level than the pressure in the reactor. This prevents the radioacitivity in the reactor core from leaking outside of the container passing through the valves, whereby radiation exposure in the working can be reduced and the circumferential contamination upon accident of pipeway rupture can be decreased. (Kawakami, Y.)

  12. Revised cost savings estimate with uncertainty for enhanced sludge washing of underground storage tank waste

    International Nuclear Information System (INIS)

    DeMuth, S.

    1998-01-01

    Enhanced Sludge Washing (ESW) has been selected to reduce the amount of sludge-based underground storage tank (UST) high-level waste at the Hanford site. During the past several years, studies have been conducted to determine the cost savings derived from the implementation of ESW. The tank waste inventory and ESW performance continues to be revised as characterization and development efforts advance. This study provides a new cost savings estimate based upon the most recent inventory and ESW performance revisions, and includes an estimate of the associated cost uncertainty. Whereas the author's previous cost savings estimates for ESW were compared against no sludge washing, this study assumes the baseline to be simple water washing which more accurately reflects the retrieval activity along. The revised ESW cost savings estimate for all UST waste at Hanford is $6.1 B ± $1.3 B within 95% confidence. This is based upon capital and operating cost savings, but does not include development costs. The development costs are assumed negligible since they should be at least an order of magnitude less than the savings. The overall cost savings uncertainty was derived from process performance uncertainties and baseline remediation cost uncertainties, as determined by the author's engineering judgment

  13. Tank waste remediation system vadose zone program plan

    International Nuclear Information System (INIS)

    Fredenburg, E.A.

    1998-01-01

    The objective of the vadose zone characterization under this program is to develop a better conceptual geohydrologic model of identified tank farms which will be characterized so that threats to human health and the environment from past leaks and spills, intentional liquid discharges, potential future leaks during retrieval, and from residual contaminants that may remain in tank farms at closure can be explicitly addressed in decision processes. This model will include geologic, hydrologic, and hydrochemical parameters as defined by the requirements of each of the TWRS programs identified here. The intent of this TWRS Vadose Zone Program Plan is to provide justification and an implementation plan for the following activities: Develop a sufficient understanding of subsurface conditions and transport processes to support decisions on management, cleanup, and containment of past leaks, spills, and intentional liquid discharges; Develop a sufficient understanding of transport processes to support decisions on controlling potential retrieval leaks; Develop a sufficient understanding of transport processes to support decisions on tank farm closure, including allowable residual waste that may remain at closure; and Provide new information on geotechnical properties in the 200 Area to supplement data used for design and performance assessment for immobilized low-activity waste disposal facilities

  14. Tank waste remediation system vadose zone program plan

    Energy Technology Data Exchange (ETDEWEB)

    Fredenburg, E.A.

    1998-07-27

    The objective of the vadose zone characterization under this program is to develop a better conceptual geohydrologic model of identified tank farms which will be characterized so that threats to human health and the environment from past leaks and spills, intentional liquid discharges, potential future leaks during retrieval, and from residual contaminants that may remain in tank farms at closure can be explicitly addressed in decision processes. This model will include geologic, hydrologic, and hydrochemical parameters as defined by the requirements of each of the TWRS programs identified here. The intent of this TWRS Vadose Zone Program Plan is to provide justification and an implementation plan for the following activities: Develop a sufficient understanding of subsurface conditions and transport processes to support decisions on management, cleanup, and containment of past leaks, spills, and intentional liquid discharges; Develop a sufficient understanding of transport processes to support decisions on controlling potential retrieval leaks; Develop a sufficient understanding of transport processes to support decisions on tank farm closure, including allowable residual waste that may remain at closure; and Provide new information on geotechnical properties in the 200 Area to supplement data used for design and performance assessment for immobilized low-activity waste disposal facilities.

  15. Tank farm surveillance and waste status summary report for October 1992

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  16. Tank farm surveillance and waste status summary report for January 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-03-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  17. Tank farm surveillance and waste status summary report for November 1992

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-02-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  18. Tank Farm surveillance and waste status summary report for September 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1994-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  19. Tank farm surveillance and waste status summary report for October 1992

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1993-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

  20. Tank farm surveillance and waste status summary report for May 1994

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1994-08-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

  1. Tank farm surveillance and waste status summary report for June 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-10-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  2. Tank farm surveillance and waste status summary report for May 1994

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1994-08-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  3. Tank farm surveillance and waste status summary report for December 1992

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-02-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  4. Tank farm surveillance and waste status summary report for December 1993

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1994-05-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special 9 surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of U.S. Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, U.S. Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

  5. Tank farm surveillance and waste status summary report for December 1992

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1993-02-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

  6. Tank 241-C-103 tank characterization plan

    International Nuclear Information System (INIS)

    Schreiber, R.D.

    1994-01-01

    The data quality objective (DQO) process was chosen as a tool to be used to identify the sampling analytical needs for the resolution of safety issues. A Tank Characterization Plant (TCP) will be developed for each double shell tank (DST) and single-shell tank (SST) using the DQO process. There are four Watch list tank classifications (ferrocyanide, organic salts, hydrogen/flammable gas, and high heat load). These classifications cover the six safety issues related to public and worker health that have been associated with the Hanford Site underground storage tanks. These safety issues are as follows: ferrocyanide, flammable gas, organic, criticality, high heat, and vapor safety issues. Tank C-103 is one of the twenty tanks currently on the Organic Salts Watch List. This TCP will identify characterization objectives pertaining to sample collection, hot cell sample isolation, and laboratory analytical evaluation and reporting requirements in accordance with the appropriate DQO documents. In addition, the current contents and status of the tank are projected from historical information. The relevant safety issues that are of concern for tanks on the Organic Salts Watch List are: the potential for an exothermic reaction occurring from the flammable mixture of organic materials and nitrate/nitrite salts that could result in a release of radioactive material and the possibility that other safety issues may exist for the tank

  7. UST/LUST Program Information

    Data.gov (United States)

    U.S. Environmental Protection Agency — This asset includes an inventory of programmatic information, including policies and guidance, training course materials and Leaking Underground Storage Tanks (LUST)...

  8. Double-shell tank ultrasonic inspection plan. Revision 1

    International Nuclear Information System (INIS)

    Pfluger, D.C.

    1994-01-01

    The waste tank systems managed by the Tank Waste Remediation System Division of Westinghouse Hanford Company includes 28 large underground double-shell tanks (DST) used for storing hazardous radioactive waste. The ultrasonic (UT) inspection of these tanks is part of their required integrity assessment (WAC 1993) as described in the tank systems integrity assessment program plan (IAPP) (Pfluger 1994a) submitted to the Ecology Department of the State of Washington. Because these tanks hold radioactive waste and are located underground examinations and inspections must be done remotely from the tank annuli with specially designed equipment. This document describes the UT inspection system (DSTI system), the qualification of the equipment and procedures, field inspection readiness, DST inspections, and post-inspection activities. Although some of the equipment required development, the UT inspection technology itself is the commercially proven and available projection image scanning technique (P-scan). The final design verification of the DSTI system will be a performance test in the Hanford DST annulus mockup that includes the demonstration of detecting and sizing corrosion-induced flaws

  9. Remaining Sites Verification Package for the 100-B-20, 1716-B Maintenance Garage Underground Tank, Waste Site Reclassification Form 2006-019

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-09-27

    The 100-B-20 waste site, located in the 100-BC-1 Operable Unit of the Hanford Site, consisted of an underground oil tank that once serviced the 1716-B Maintenance Garage. The selected action for the 100-B-20 waste site involved removal of the oil tanks and their contents and demonstrating through confirmatory sampling that all cleanup goals have been met. In accordance with this evaluation, a reclassification status of interim closed out has been determined. The results demonstrate that the site will support future unrestricted land uses that can be represented by a rural-residential scenario. These results also show that residual concentrations support unrestricted future use of shallow zone soil and that contaminant levels remaining in the soil are protective of groundwater and the Columbia River.

  10. History of waste tank 14, 1957 through 1974

    International Nuclear Information System (INIS)

    Davis, T.L.; Tharin, D.W.; Jones, D.W.; Lohr, D.R.

    1977-08-01

    Tank 14 was placed in service as a receiver of fresh high heat waste (HW) in September 1957. Annulus leakage was discovered in April 1959 and continued until annulus ventilation was increased in January 1965. Practically all of the approximately 40 leak sites that have been identified on the tank wall are located at or below the bottom horizontal weld. Tank supernate was removed from the tank in preparation for a sludge removal operation which was performed in December 1968. The tank was then filled to its present level with blended supernate from tanks 10 and 13. In December 1972, supernate was inadvertently siphoned into the annulus through a dewatering jet, filling the annulus pan to a level of 33 in. The waste was promptly returned to the tank. Inspections of the tank interior and annulus were performed by direct observation, with a 40-ft optical periscope, and with photography and closed circuit television. Radioactive waste was first found in the annulus during visual inspection in May 1959. Samples of sludge, supernate, tank vapors, and leaked material in the annulus were analyzed, and numerous tank temperature profiles were taken. Soil and tank wall temperatures were measured in a study of tank nil ductility transition temperature. Six cooling coils failed, five of which occurred within 7 months after sludge removal. Several modifications to equipment and various equipment repairs were made. 14 figures, 3 tables

  11. 2003 Initial Assessments of Closure for the C Tank Farm Field Investigation Report (FIR):Numerical Simulations

    International Nuclear Information System (INIS)

    Zhang, Z F.; Freedman, Vicky L.; White, Mark D.

    2003-01-01

    In support of CH2M HILL Hanford Group, Inc.'s (CHG) preparation of a Field Investigative Report (FIR) for the closure of the Hanford Site Single-Shell Tank (SST) Waste Management Area (WMA) tank farms, a set of numerical simulations of flow and solute transport was executed to predict the performance of surface barriers for reducing long-term risks from potential groundwater contamination at the C Farm WMA. This report documents the simulation of 14 cases (and two verification cases) involving two-dimensional cross sections through the C Farm WMA tanks C-103 - C-112. Utilizing a unit release scenario at Tank C-112, four different types of leaks were simulated. These simulations assessed the impact of leakage during retrieval, past leaks, and tank residual wastes and tank ancillary equipment following closure activities. . Two transported solutes were considered: uranium-238 (U-238) and technetium-99 (Tc-99). To evaluate the impact of sorption to the subsurface materials, six different retardation coefficients were simulated for U-238. Overall, simulations results for the C Farm WMA showed that only a small fraction of the U-238 with retardation factors greater than 0.6 migrated from the vadose zone in all of the cases. For the conservative solute, Tc-99, results showed that the simulations investigating leakages during retrieval demonstrated the highest WMA peak concentrations and the earliest arrival times due to the high infiltration rate before the use of surface barriers and the addition of water into the system. Simulations investigating past leaks showed similar peaks and arrival times as the retrieval leak cases. Several different release rates were used to investigate contaminant transport from residual tank wastes. All showed similar peak concentrations and arrival times, except for the lowest initial release rate, which was 1,000 times slower than the highest release rate. Past leaks were also investigated with different release rate models, including

  12. Underground storage tank 291-D1U1: Closure plan

    Energy Technology Data Exchange (ETDEWEB)

    Mancieri, S.; Giuntoli, N.

    1993-09-01

    The 291-D1U1 tank system was installed in 1983 on the north side of Building 291. It supplies diesel fuel to the Building 291 emergency generator and air compressor. The emergency generator and air compressor are located southwest and southeast, respectively, of the tank (see Appendix B, Figure 2). The tank system consists of a single-walled, 2,000- gallon, fiberglass tank and a fuel pump system, fill pipe, vent pipe, electrical conduit, and fuel supply and return piping. The area to be excavated is paved with asphalt and concrete. It is not known whether a concrete anchor pad is associated with this tank. Additionally, this closure plan assumes that the diesel tank is below the fill pad. The emergency generator and air compressor for Building 291 and its associated UST, 291-D1U1, are currently in use. The generator and air compressor will be supplied by a temporary above-ground fuel tank prior to the removal of 291-D1U1. An above-ground fuel tank will be installed as a permanent replacement for 291-D1U1. The system was registered with the State Water Resources Control Board on June 27, 1984, as 291-41D and has subsequently been renamed 291-D1U1. Figure 1 (see Appendix B) shows the location of the 291-D1U1 tank system in relation to the Lawrence Livermore National Laboratory (LLNL). Figure 2 (see Appendix B) shows the 291-D1U1 tank system in relation to Building 291. Figure 3 (see Appendix B) shows a plan view of the 291-D1U1 tank system.

  13. Analysis on signal properties due to concurrent leaks at two points in water supply pipelines

    International Nuclear Information System (INIS)

    Lee, Young Sup

    2015-01-01

    Intelligent leak detection is an essential component of a underground water supply pipeline network such as a smart water grid system. In this network, numerous leak detection sensors are needed to cover all of the pipelines in a specific area installed at specific regular distances. It is also necessary to determine the existence of any leaks and estimate its location within a short time after it occurs. In this study, the leak signal properties and feasibility of leak location detection were investigated when concurrent leaks occurred at two points in a pipeline. The straight distance between the two leak sensors in the 100A sized cast-iron pipeline was 315.6 m, and their signals were measured with one leak and two concurrent leaks. Each leak location was described after analyzing the frequency properties and cross-correlation of the measured signals.

  14. Analysis on signal properties due to concurrent leaks at two points in water supply pipelines

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Sup [Dept. of Embedded Systems Engineering, Incheon National University, Incheon (Korea, Republic of)

    2015-02-15

    Intelligent leak detection is an essential component of a underground water supply pipeline network such as a smart water grid system. In this network, numerous leak detection sensors are needed to cover all of the pipelines in a specific area installed at specific regular distances. It is also necessary to determine the existence of any leaks and estimate its location within a short time after it occurs. In this study, the leak signal properties and feasibility of leak location detection were investigated when concurrent leaks occurred at two points in a pipeline. The straight distance between the two leak sensors in the 100A sized cast-iron pipeline was 315.6 m, and their signals were measured with one leak and two concurrent leaks. Each leak location was described after analyzing the frequency properties and cross-correlation of the measured signals.

  15. Melton Valley liquid low-level radioactive waste storage tanks evaluation

    International Nuclear Information System (INIS)

    1995-06-01

    The Melton Valley Liquid Low-Level Radioactive Waste Storage Tanks (MVSTs) store the evaporator concentrates from the Liquid Low-Level Radioactive Waste (LLLW) System at the Oak Ridge National Laboratory (ORNL). The eight stainless steel tanks contain approximately 375,000 gallons of liquid and sludge waste. These are some of the newer, better-designed tanks in the LLLW System. They have been evaluated and found by the US Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation to comply with all Federal Facility Agreement requirements for double containment. The operations and maintenance aspects of the tanks were also reviewed by the Defense Nuclear Facilities Safety Board (DNFSB) in September 1994. This document also contains an assessment of the risk to the public and ORNL workers from a leak in one of the MVSTs. Two primary scenarios were investigated: (1) exposure of the public to radiation from drinking Clinch River water contaminated by leaked LLLW, and (2) exposure of on-site workers to radiation by inhaling air contaminated by leaked LLLW. The estimated frequency of a leak from one of the MVSTs is about 8 x 10 -4 events per year, or about once in 1200 years (with a 95% confidence level). If a leak were to occur, the dose to a worker from inhalation would be about 2.3 x 10 -1 mrem (with a 95% confidence level). The dose to a member of the public through the drinking water pathway is estimated to be about 7 x 10 -1 mrem (with a 95% confidence level). By comparison with EPA Safe Drinking Water regulations, the allowable lifetime radiation dose is about 300 mrem. Thus, a postulated LLLW leak from the MVSTs would not add appreciably to an individual's lifetime radiation dose

  16. In situ bioremediation of an underground diesel fuel spill: A case history

    Science.gov (United States)

    Frankenberger, W. T.; Emerson, K. D.; Turner, D. W.

    1989-05-01

    In the winter months of 1983, approximately 1000 gallons of diesel fuel had flowed along an asphalt parking lot of a commercial establishment towards a surface drain near an open creek. Investigations led to the discovery of an underground storage tank leaking diesel fuel. Exploratory borings showed that contamination was near the surface horizon and the capillary zone of the water table. Hydrocarbon quantities ranged up to 1500 mg/kg of soil. The plume continued to move in an eastward direction toward the surface water of the creek. A laboratory study indicated relatively high numbers of hydrocarbon-oxidizing organisms relative to glucose-utilizing microorganisms in the unsaturated vadose zone. Bioreclamation was initiated in April 1984 by injecting nutrients (nitrogen and phosphorus) and hydrogen peroxide and terminated in October 1984 upon no detection (<1 mg/kg) of hydrocarbons. A verification boring within the vicinity of the contaminated plume confirmed that residual contamination had attained background levels. The monitoring program was terminated in January 1987.

  17. Criteria: waste tank isolation and stabilization

    Energy Technology Data Exchange (ETDEWEB)

    Metz, W.P.; Ogren, W.E.

    1976-09-01

    The crystallized Hanford high-level wastes stored in single-shell underground tanks consist of sludges and salt cakes covered with supernatural liquor. Purpose of stabilization and isolation is to reduce the releases and losses as a result of a loss of tank integrity. The tanks will be modified so that no inadvertent liquid additions can be made. Criteria for the isolation and stabilization are given and discussed briefly. (DLC)

  18. Criteria: waste tank isolation and stabilization

    International Nuclear Information System (INIS)

    Metz, W.P.; Ogren, W.E.

    1976-09-01

    The crystallized Hanford high-level wastes stored in single-shell underground tanks consist of sludges and salt cakes covered with supernatural liquor. Purpose of stabilization and isolation is to reduce the releases and losses as a result of a loss of tank integrity. The tanks will be modified so that no inadvertent liquid additions can be made. Criteria for the isolation and stabilization are given and discussed briefly

  19. Tank Farm surveillance and waste status summary report for March 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-05-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are Contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding flank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  20. Fundamental study on leak detection of underground gas pipeline using passive acoustic method; Judogata onkyo keisoku ni yoru maisetsu gas dokan hason kasho no kenshutsu ni kansuru kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    Jinguji, M; Imaizumi, H; Kunimatsu, S; Isei, T [National Institute for Resources and Environment, Tsukuba (Japan)

    1997-05-27

    With an objective to detect gas leaking from an underground gas pipeline, discussions have been given on a method which utilizes acoustic characteristics of leakage. On leaking sound generated from damaged portions, the form of damaging was hypothesized as pinholes, and spectra of leaking sounds from holes with different diameters were measured. The dominant frequency decreases as the hole diameter increases, while it is in a region of relatively high frequency of 1 kHz or higher. However, detection from the ground surface was impossible when cover soil has thickness from 0.5 to 1.5 m. In an experiment to measure leaking sound inside the pipe, pressure in the pipe was adjusted to 0.02 atm which is a standard pressure for a low-pressure pipe, and the sound was measured when the hole diameters were varied. In any of the results obtained by varying the hole diameter, spectra having the dominant frequency in the region of 1 kHz or higher were measured. In addition, it was found that sound pressure difference of as much as 50 dB at maximum is generated as compared with a case of no sound leakage. The above results verified that monitoring the high frequency of 1 kHz or higher is effective in detecting leakage from small damages. 2 refs., 4 figs.

  1. Underground storage tank 431-D1U1, Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mancieri, S.

    1993-09-01

    This document contains information about the decommissioning of Tank 431-D1U1. This tank was installed in 1965 for diesel fuel storage. This tank will remain in active usage until closure procedures begin. Soils and ground water around the tank will be sampled to check for leakage. Appendices include; proof of proper training for workers, health and safety briefing record, task hazard analysis summary, and emergency plans.

  2. Heat pipe cooling system for underground, radioactive waste storage tanks

    International Nuclear Information System (INIS)

    Cooper, K.C.; Prenger, F.C.

    1980-02-01

    An array of 37 heat pipes inserted through the central hole at the top of a radioactive waste storage tank will remove 100,000 Btu/h with a heat sink of 70 0 F atmospheric air. Heat transfer inside the tank to the heat pipe is by natural convection. Heat rejection to outside air utilizes a blower to force air past the heat pipe condenser. The heat pipe evaporator section is axially finned, and is constructed of stainless steel. The working fluid is ammonia. The finned pipes are individually shrouded and extend 35 ft down into the tank air space. The hot tank air enters the shroud at the top of the tank and flows downward as it is cooled, with the resulting increased density furnishing the pressure difference for circulation. The cooled air discharges at the center of the tank above the sludge surface, flows radially outward, and picks up heat from the radioactive sludge. At the tank wall the heated air rises and then flows inward to comple the cycle

  3. HIGH RESOLUTION RESISTIVITY LEAK DETECTION DATA PROCESSING and EVALUATION MEHTODS and REQUIREMENTS

    International Nuclear Information System (INIS)

    SCHOFIELD JS

    2007-01-01

    This document has two purposes: (sm b ullet) Describe how data generated by High Resolution REsistivity (HRR) leak detection (LD) systems deployed during single-shell tank (SST) waste retrieval operations are processed and evaluated. (sm b ullet) Provide the basic review requirements for HRR data when Hrr is deployed as a leak detection method during SST waste retrievals

  4. Use of the Modified Light Duty Utility Arm to Perform Nuclear Waste Cleanup of Underground Waste Storage Tanks at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Blank, J.A.; Burks, B.L.; DePew, R.E.; Falter, D.D.; Glassell, R.L.; Glover, W.H.; Killough, S.M.; Lloyd, P.D.; Love, L.J.; Randolph, J.D.; Van Hoesen, S.D.; Vesco, D.P.

    1999-01-01

    The Modified Light Duty Utility Arm (MLDUA) is a selectable seven or eight degree-of-freedom robot arm with a 16.5 ft (5.03 m) reach and a payload capacity of 200 lb. (90.72 kg). The utility arm is controlled in either joystick-based telerobotic mode or auto sequence robotics mode. The MLDUA deployment system deploys the utility arm vertically into underground radioactive waste storage tanks located at Oak Ridge National Laboratory. These tanks are constructed of gunite material and consist of two 25 ft (7.62 m) diameter tanks in the North Tank Farm and six 50 ft (15.24 m) diameter tanks in the South Tank Farm. After deployment inside a tank, the utility arm reaches and grasps the confined sluicing end effecter (CSEE) which is attached to the hose management arm (HMA). The utility arm positions the CSEE within the tank to allow the HMA to sluice the tank's liquid and solid waste from the tank. The MLDUA is used to deploy the characterization end effecter (CEE) and gunite scarifying end effecter (GSEE) into the tank. The CEE is used to survey the tank wall's radiation levels and the physical condition of the walls. The GSEE is used to scarify the tank walls with high-pressure water to remove the wall scale buildup and a thin layer of gunite which reduces the radioactive contamination that is embedded into the gunite walls. The MLDUA is also used to support waste sampling and wall core-sampling operations. Other tools that have been developed for use by the MLDUA include a pipe-plugging end effecter, pipe-cutting end effecter, and pipe-cleaning end effecter. Washington University developed advance robotics path control algorithms for use in the tanks. The MLDUA was first deployed in June 1997 and has operated continuously since then. Operational experience in the first four tanks remediated is presented in this paper

  5. Operational Plan for Underground Storage Tank 322 R2U2

    Energy Technology Data Exchange (ETDEWEB)

    Griffin, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-06-07

    This Operational Plan provides the operator of the tank system with guidelines relating to the safe and compliant operation and maintenance of the tank system. The tank system schematic and list of emergency contacts shall be posted near the tank so they are visible to tank personnel. This Operational Plan shall be kept on file by the Facility Supervisor. It should be understood when managing this tank system that it is used to store hazardous waste temporarily for 90 calendar days or less. The rinsewater handled in the tank system is considered hazardous and may exhibit the characteristic of toxicity.

  6. 340 Facility secondary containment and leak detection

    International Nuclear Information System (INIS)

    Bendixsen, R.B.

    1995-01-01

    This document presents a preliminary safety evaluation for the 340 Facility Secondary Containment and Leak Containment system, Project W-302. Project W-302 will construct Building 340-C which has been designed to replace the current 340 Building and vault tank system for collection of liquid wastes from the Pacific Northwest Laboratory buildings in the 300 Area. This new nuclear facility is Hazard Category 3. The vault tank and related monitoring and control equipment are Safety Class 2 with the remainder of the structure, systems and components as Safety Class 3 or 4

  7. Annual radioactive waste tank inspection program: 1995

    International Nuclear Information System (INIS)

    McNatt, F.G. Sr.

    1996-01-01

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1995 to evaluate these vessels and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

  8. Annual radioactive waste tank inspection program - 1992

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1992-01-01

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1992 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report

  9. Annual radioactive waste tank inspection program - 1991

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1992-01-01

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1991 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report

  10. Analysis of Bracket Assembly for Portable Leak Detector Station

    International Nuclear Information System (INIS)

    ZIADA, H.H.

    1999-01-01

    This Supporting Document Presents Structural and Stress Analysis of a Portable Leak Detector Station for Tank Farms. The results show that the bracket assembly meets the requirements for dead load and natural phenomena hazards loads (seismic and wind)

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

    International Nuclear Information System (INIS)

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

    1994-06-01

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

  12. Supporting document for the historical tank content estimate for A Tank Farm

    International Nuclear Information System (INIS)

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

    1994-06-01

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

  13. Supporting document for the historical tank content estimate for A Tank Farm

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-06-01

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

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

    International Nuclear Information System (INIS)

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

    1994-06-01

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

  16. Geology of the 241-TY Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the ERDA Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  17. Annual Progress Report on the Development of Waste Tank Leak Monitoring and Detection and Mitigation Activities in Support of M-45-08

    International Nuclear Information System (INIS)

    DEFIGH PRICE, C.

    2000-01-01

    Milestone M-45-09E of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) [TPA 1996] requires submittal of an annual progress report on the development of waste tank leak detection, monitoring, and mitigation (LDMM) activities associated with the retrieval of waste from single-shell tanks (SSTs). This report details progress for fiscal year 2000, building on the current LDMM strategy and including discussion of technologies, applications, cost, schedule, and technical data. The report also includes discussion of demonstrations conducted and recommendations for additional testing. Tri-Party Agreement Milestones M-45-08A and M-45-08B required design and demonstration of LDMM systems for initial retrieval of SST waste. These specific milestones have recently been deleted as part of the M-45-00A change package. Future LDMM development work has been incorporated into specific technology demonstration milestones and SST waste retrieval milestones in the M-45-03 and M-45-05 milestone series

  18. Savannah River Plant waste tank inspection manual

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1979-01-01

    This manual is to aid in making visual and photographic inspections and steel thickness measurements of Building 241-F and -H underground waste storage tanks. It describes the inspection program, the storage tanks, the equipment and techniques used and the results of their application, and the inspection recordkeeping methods

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

    International Nuclear Information System (INIS)

    Wiersma, B

    2008-01-01

    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

  20. METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    WEBER RA

    2009-01-16

    The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank 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 gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as

  1. METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    FOWLER KD

    2007-12-27

    This 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 7 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs. The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank 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 gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient

  2. A review of technology for verification of waste removal from Hanford Underground Storage Tanks (WHC Issue 30)

    International Nuclear Information System (INIS)

    Thunborg, S.

    1994-09-01

    Remediation of waste from Underground Storage Tanks (UST) at the Hanford Waste storage sites will require removal of all waste to a nearly clean condition. Current requirements are 99% clean. In order to meet remediation legal requirements, a means to remotely verify that the waste has been removed to sufficient level is needed. This report discusses the requirements for verification and reviews major technologies available for inclusion in a verification system. The report presents two operational scenarios for verification of residual waste volume. Thickness verification technologies reviewed are Ultrasonic Sensors, Capacitance Type Sensors, Inductive Sensors, Ground Penetrating Radar, and Magnetometers. Of these technologies Inductive (Metal Detectors) and Ground Penetrating Radar appear to be the most suitable for use as waste thickness sensors

  3. GIS Analysis of Available Data to Identify regions in the U.S. Where Shallow Ground Water Supplies are Particularly Vulnerable to Contamination by Releases to Biofuels from Underground Storage Tanks

    Science.gov (United States)

    GIS analysis of available data to identify regions in the U.S. where shallow ground water supplies are particularly vulnerable to contamination by releases of biofuels from underground storage tanks. In this slide presentation, GIS was used to perform a simple numerical and ...

  4. Hanford tank initiative test facility site selection study

    International Nuclear Information System (INIS)

    Staehr, T.W.

    1997-01-01

    The Hanford Tanks Initiative (HTI) project is developing equipment for the removal of hard heel waste from the Hanford Site underground single-shell waste storage tanks. The HTI equipment will initially be installed in the 241-C-106 tank where its operation will be demonstrated. This study evaluates existing Hanford Site facilities and other sites for functional testing of the HTI equipment before it is installed into the 241-C-106 tank

  5. Potential for criticality in Hanford tanks resulting from retrieval of tank waste

    International Nuclear Information System (INIS)

    Whyatt, G.A.; Sterne, R.J.; Mattigod, S.V.

    1996-09-01

    This report assesses the potential during retrieval operations for segregation and concentration of fissile material to result in a criticality. The sluicing retrieval of C-106 sludge to AY-102 and the operation of mixer pumps in SY-102 are examined in some detail. These two tanks (C-106, SY-102) were selected because of the near term plans for retrieval of these tanks and their high plutonium inventories relative to other tanks. Although all underground storage tanks are subcritical by a wide margin if assumed to be uniform in composition, the possibility retrieval operations could preferentially segregate the plutonium and locally concentrate it sufficiently to result in criticality was a concern. This report examines the potential for this segregation to occur

  6. Treatment of radioactive wastes from DOE underground storage tanks

    International Nuclear Information System (INIS)

    Collins, J.L.; Egan, B.Z.; Spencer, B.B.; Chase, C.W.; Anderson, K.K.; Bell, J.T.

    1994-01-01

    Bench-scale batch tests have been conducted with sludge and supernate tank waste from the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to evaluate separation technology process for use in a comprehensive sludge processing flow sheet as a means of concentrating the radionuclides and reducing the volumes of storage tank waste at national sites for final disposal. This paper discusses the separation of the sludge solids and supernate, the basic washing of the sludge solids, the acidic dissolution of the sludge solids, and the removal of the radionuclides from the supernate

  7. CHEMICALS STORED IN USTS: CHARACTERISTICS AND LEAK DETECTION

    Science.gov (United States)

    The regulations Issued by the U.S. Environmental Protection Agency (EPA) In 1988 require, with several exceptions, that the Integrity of underground storage tank (UST) systems containing petroleum fuels and hazardous chemicals be routinely tested. The regulatory standards for ...

  8. Annual radioactive waste tank inspection program - 1999

    International Nuclear Information System (INIS)

    Moore, C.J.

    2000-01-01

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1999 to evaluate these vessels and auxiliary appurtenances along with evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

  9. Data quality objectives lessons learned for tank waste characterization

    International Nuclear Information System (INIS)

    Eberlein, S.J.

    1996-01-01

    The tank waste characterization process is an integral part of the overall effort to control the hazards associated with radioactive wastes stored in underground tanks at the Hanford Reservation. The programs involved in the characterization of the wastes are employing Data Quality Objective (DQO) process in all information and data collection activities. The DQO process is used by the programs to address an issue or problem rather than a specific sampling event. Practical limits do not always allow for precise characterization of a tank or the implementation of the DQO process. Because of the flexibility of the DQO process, it can be used as a tool for sampling and analysis of the underground waste storage tanks. The iterative nature of the DQO process allows it to be used as additional information is claimed or lessons are learned concerning an issue or problem requiring sampling and analysis of tank waste. In addition, the application of DQO process forces alternative actions to be considered when precise characterization of a tank or the full implementation of the DQO process is not practical

  10. Portable Rapid Test Fuel Tank Leak Detection System

    Science.gov (United States)

    2010-04-01

    polished. Lid is tig welded . Media: Water Result: Bubbles (encircled in red) only at threaded port and at top of the center as shown in Picture 2...conditioned electrical signal is processed by leak detector software on a common laptop computer. Figure 1-1. RT...connect the DP-103 gauge. This cable was connected and sealed to the DP-103 gauge through a polyurethane mold process performed at the manufacturer

  11. Detection of Leaks in Water Distribution System using Non-Destructive Techniques

    Science.gov (United States)

    Aslam, H.; Kaur, M.; Sasi, S.; Mortula, Md M.; Yehia, S.; Ali, T.

    2018-05-01

    Water is scarce and needs to be conserved. A considerable amount of water which flows in the water distribution systems was found to be lost due to pipe leaks. Consequently, innovations in methods of pipe leakage detections for early recognition and repair of these leaks is vital to ensure minimum wastage of water in distribution systems. A major component of detection of pipe leaks is the ability to accurately locate the leak location in pipes through minimum invasion. Therefore, this paper studies the leak detection abilities of the three NDT’s: Ground Penetration Radar (GPR) and spectrometer and aims at determining whether these instruments are effective in identifying the leak. An experimental setup was constructed to simulate the underground conditions of water distribution systems. After analysing the experimental data, it was concluded that both the GPR and the spectrometer were effective in detecting leaks in the pipes. However, the results obtained from the spectrometer were not very differentiating in terms of observing the leaks in comparison to the results obtained from the GPR. In addition to this, it was concluded that both instruments could not be used if the water from the leaks had reached on the surface, resulting in surface ponding.

  12. Improved estimation of leak location of pipelines using frequency band variation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Sup [Embedded System Engineering Department, Incheon National University, Incheon (Korea, Republic of); Yoon, Dong Jin [Safety Measurement Center, Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of)

    2014-02-15

    Leakage is an important factor to be considered for the management of underground water supply pipelines in a smart water grid system, especially if the pipelines are aged and buried under the pavement or various structures of a highly populated city. Because the exact detection of the location of such leaks in pipelines is essential for their efficient operation, a new methodology for leak location detection based on frequency band variation, windowing filters, and probability is proposed in this paper. Because the exact detection of the leak location depends on the precision of estimation of time delay between sensor signals due to leak noise, some window functions that offer weightings at significant frequencies are applied for calculating the improved cross-correlation function. Experimental results obtained by applying this methodology to an actual buried water supply pipeline, ∼ 253.9 m long and made of cast iron, revealed that the approach of frequency band variation with those windows and probability offers better performance for leak location detection.

  13. Improved estimation of leak location of pipelines using frequency band variation

    International Nuclear Information System (INIS)

    Lee, Young Sup; Yoon, Dong Jin

    2014-01-01

    Leakage is an important factor to be considered for the management of underground water supply pipelines in a smart water grid system, especially if the pipelines are aged and buried under the pavement or various structures of a highly populated city. Because the exact detection of the location of such leaks in pipelines is essential for their efficient operation, a new methodology for leak location detection based on frequency band variation, windowing filters, and probability is proposed in this paper. Because the exact detection of the leak location depends on the precision of estimation of time delay between sensor signals due to leak noise, some window functions that offer weightings at significant frequencies are applied for calculating the improved cross-correlation function. Experimental results obtained by applying this methodology to an actual buried water supply pipeline, ∼ 253.9 m long and made of cast iron, revealed that the approach of frequency band variation with those windows and probability offers better performance for leak location detection.

  14. Ultrasonic Detectors Safely Identify Dangerous, Costly Leaks

    Science.gov (United States)

    2013-01-01

    In 1990, NASA grounded its space shuttle fleet. The reason: leaks detected in the hydrogen fuel systems of the Space Shuttles Atlantis and Columbia. Unless the sources of the leaks could be identified and fixed, the shuttles would not be safe to fly. To help locate the existing leaks and check for others, Kennedy Space Center engineers used portable ultrasonic detectors to scan the fuel systems. As a gas or liquid escapes from a leak, the resulting turbulence creates ultrasonic noise, explains Gary Mohr, president of Elmsford, New York-based UE Systems Inc., a long-time leader in ultrasonic detector technologies. "In lay terms, the leak is like a dog whistle, and the detector is like the dog ear." Because the ultrasound emissions from a leak are highly localized, they can be used not only to identify the presence of a leak but also to help pinpoint a leak s location. The NASA engineers employed UE s detectors to examine the shuttle fuel tanks and solid rocket boosters, but encountered difficulty with the devices limited range-certain areas of the shuttle proved difficult or unsafe to scan up close. To remedy the problem, the engineers created a long-range attachment for the detectors, similar to "a zoom lens on a camera," Mohr says. "If you are on the ground, and the leak is 50 feet away, the detector would now give you the same impression as if you were only 25 feet away." The enhancement also had the effect of reducing background noise, allowing for a clearer, more precise detection of a leak s location.

  15. Geology of the 241-C Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  16. Geology of the 241-SX Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  17. Geology of the 241-S Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  18. Geology of the 241-T Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  19. Geology of the 241-TX Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps have been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  20. Geology of the 241-U Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps has been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  1. Replacement inhibitors for tank farm cooling coil systems

    International Nuclear Information System (INIS)

    Hsu, T.C.

    1995-01-01

    Sodium chromate has been an effective corrosion inhibitor for the cooling coil systems in Savannah River Site (SRS) waste tanks for over 40 years. Due to their age and operating history, cooling coils occasionally fail allowing chromate water to leak into the environment. When the leaks spill 10 lbs. or more of sodium chromate over a 24-hr period, the leak incidents are classified as Unusual Occurrences (UO) per CERCLA (Comprehensive Environmental Response, Compensation and Liability Act). The cost of reporting and cleaning up chromate spills prompted High Level Waste Engineering (HLWE) to initiate a study to investigate alternative tank cooling water inhibitor systems and the associated cost of replacement. Several inhibitor systems were investigated as potential alternatives to sodium chromate. All would have a lesser regulatory impact, if a spill occurred. However, the conversion cost is estimated to be $8.5 million over a period of 8 to 12 months to convert all 5 cooling systems. Although each of the alternative inhibitors examined is effective in preventing corrosion, there is no inhibitor identified that is as effective as chromate. Assuming 3 major leaks a year (the average over the past several years), the cost of maintaining the existing inhibitor was estimated at $0.5 million per year. Since there is no economic or regulatory incentive to replace the sodium chromate with an alternate inhibitor, HLWE recommends that sodium chromate continue to be used as the inhibitor for the waste tank cooling systems

  2. A basic study on underground storage of LNG

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min-Kyu; Lee, Kyung-Han; Kang, Sun-Duck [Korea Institute of Geology Mining and Materials, Taejon (KR)] (and others)

    1999-12-01

    In 1997, import of LNG was 11,378 thousand of about 2.3 billion US dollars. The demand of LNG(Liquefied Natural Gas) in Korea has been increased since 1987 with the rate of 20% annually. It is also estimated that this trend will be continued until 2010. Long-term estimation says that demand will increase with 9.1% and total demand of 2010 will be 23 million ton that is four times larger than that of 1994. Bases of unloading and store of LNG is necessary to complete the network of LNG distribution system to cover all of the country from import to final supply terminal at home. The construction plan of LNG bases with 49 tanks was published and is going on now at three bases, Pyungtaek, Incheon and Tongyoung. The total cost for this construction will be over 5,400 billion Won. All the LNG tanks are planned to build on the surface. The construction of LNG tanks on the surfaces is conventional but it damage the surface green area and is very vulnerable on safety, especially in Korea Peninsula with potentially unstable of military confrontation. And Korea is so small and limited in available land that it is not easy to find proper places for construction of more LNG tanks on surface. Underground LNG stores in rock will be a good alternative for tanks on surface in the view points of environmental and safety. It is also reported that it can be cheaper than that of on surfaces. It is well known that bed rocks in Korea is good to build underground structure like LNG stores. This report is basic research to seek for the possibility of LNG store construction in underground rocks. The important two questions on it is that whether it is possible technically and economically or not. The technical focus in this report is the stability of underground cavern for storage of LNG, energy conservation in operation, tightness against leakage of stored gas to surface and safety. Some statistic on LNG in Korea is given for this study with its future. (author). 25 refs., 36 tabs., 88 figs.

  3. Remaining Sites Verification Package for the 100-B-20, 1716-B Maintenance Garage Underground Tank. Attachment to Waste Site Reclassification Form 2006-019

    International Nuclear Information System (INIS)

    Dittmer, L.M.

    2006-01-01

    The 100-B-20 waste site, located in the 100-BC-1 Operable Unit of the Hanford Site, consisted of an underground oil tank that once serviced the 1716-B Maintenance Garage. The selected action for the 100-B-20 waste site involved removal of the oil tanks and their contents and demonstrating through confirmatory sampling that all cleanup goals have been met. In accordance with this evaluation, a reclassification status of interim closed out has been determined. The results demonstrate that the site will support future unrestricted land uses that can be represented by a rural-residential scenario. These results also show that residual concentrations support unrestricted future use of shallow zone soil and that contaminant levels remaining in the soil are protective of groundwater and the Columbia River

  4. Single shell tank sluicing history and failure frequency

    International Nuclear Information System (INIS)

    HERTZEL, J.S.

    1998-01-01

    This document assesses the potential for failure of the single-shell tanks (SSTs) that are presumably sound and helps to establish the retrieval priorities for these and the assumed leakers. Furthermore, this report examines probabilities of SST failure as a function of age and operational history, and provides a simple statistical summary of historical leak volumes, leak rates, and corrosion factor

  5. Seismic design and evaluation guidelines for the Department of Energy high-level waste storage tanks and appurtenances

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.; Cornell, A.; Costantino, C.; Kennedy, R.; Miller, C.; Veletsos, A.

    1993-01-01

    This document provides guidelines for the design and evaluation of underground high-level waste storage tanks due to seismic loads. Attempts were made to reflect the knowledge acquired in the last two decades in the areas of defining the ground motion and calculating hydrodynamic loads and dynamic soil pressures for underground tank structures. The application of the analysis approach is illustrated with an example. The guidelines are developed for specific design of underground storage tanks, namely double-shell structures. However, the methodology discussed is applicable for other types of tank structures as well. The application of these and of suitably adjusted versions of these concepts to other structural types will be addressed in a future version of this document

  6. Releases from the cooling water system in the Waste Tank Farm

    International Nuclear Information System (INIS)

    Perkins, W.C.; Lux, C.R.

    1991-01-01

    On September 12, 1991, a cooling-water header broke in the H-Area Waste Tank farm, at the Savannah River Site, releasing contaminated water down a storm sewer that drains to the creek. A copy of the Occurrence Report is attached. As part of the follow-up on this incident, the NPSR Section was asked by Waste Management Technology to perform a probabilistic analysis of the following cases: (1) A large break in the header combined with a large break in a cooling coil inside a waste tank. (2) A large break in the header combined with a leak in a cooling coil inside a waste tank. (3) A large break in the header combined with a very small leak in a cooling coil inside a waste tank. This report documents the results of the analysis of these cases

  7. Inspection and repair of storage tank bottoms and foundations using airbag lifting

    International Nuclear Information System (INIS)

    Wildin, I.P.; Adams, N.J.

    1992-01-01

    This paper reports that within the past five years the environmental impact on the operation of petro-chemical product storage tanks, constructed to standards such as API 650, has taken on critical implications for refineries and distribution centers. Pollution of the supporting foundation and possible widespread effects on ground water has resulted in moves to require the installation of double integrity bottoms. That is not to say, necessarily, a tank with two steel bottoms, but alternative means of reducing the failure probability to an acceptable public or statutory level. Clearly increased inspection of the tank bottom has merit and visual examination of the bottom from inside the tank can be supplemented by ultrasonic methods, acoustic leak detection and magnetic flux scanning. Tank lifting now offers a very cost effective method for underfloor inspection, combined with the opportunity to undertake repairs to the bottom and underside painting, together with improvements and repairs to the Bitsand surface of the tank pad. if necessary, an impervious membrane can also be installed with a leak detection trough formed around the tank edge

  8. An Approach for Developing Site-Specific Lateral and Vertical Inclusion Zones within which Structures Should be Evaluated for Petroleum Vapor Intrusion due to Releases of Motor Fuel from Underground Storage Tanks

    Science.gov (United States)

    Buildings may be at risk from Petroleum Vapor Intrusion (PVI) when they overlie petroleum hydrocarbon contamination in the unsaturated zone or dissolved in groundwater. The U.S. EPA Office of Underground Storage Tanks (OUST) is preparing Guidance for Addressing Petroleum Vapor I...

  9. [Leak on underground pipings. Corrosion in containment spray systems at Bugey NPP (Preliminary Information)

    International Nuclear Information System (INIS)

    1996-01-01

    During last refuelling shutdown at BUGEY 3, this year on the fourteenth of February, the plant operator discovered a wide corrosion on the reactor vessel head and its equipments. The reactor head vessel had recently been replaced by a new one since last reactor shutdown in order to treat the vessel head adaptor safety problem. The cause of this corrosion is a small primary leak on this pipe flange. The leak had been found fortuitously during a field inspection of valves while there was not reactor charge, seven months before the reactor was shutdown for refuelling. At this time the primary leak had been leaktighted by closure of a manual valve and the reactor was restarted up

  10. Leak detector for a steam generator in FBR type reactors

    International Nuclear Information System (INIS)

    Miyaji, Nobuyoshi.

    1979-01-01

    Purpose: To facilitate maintenance for liquid leak detectors such as exchange of nickel membrane sensors during operation in a sodium-cooled fbr type reactor. Constitution: A pipeway capable of supplying a cover gas such as argon into the cylinder of a hydrogen detector containing a nickel membrane sensor is provided in a liquid leak detector constituting a part of a by-pass loop. The pipeway is also adapted to be evacuated. A pipeway and a small sodium tank for drain use are provided on the side of the by-pass loop near valves. Then, after closing the inlet and outlet valves to disconnect the by-pass loop from the sodium main pipeway, the cover gas is supplied to drive liquid sodium to the drain tank. After the drain of the liquid sodium, the sensor can be replaced. (Ikeda, J.)

  11. A Monte Carlo simulation method for assessing biotransformation effects on groundwater fuel hydrocarbon plume lengths

    International Nuclear Information System (INIS)

    McNab, W.W. Jr.

    2000-01-01

    Biotransformation of dissolved groundwater hydrocarbon plumes emanating from leaking underground fuel tanks should, in principle, result in plume length stabilization over relatively short distances, thus diminishing the environmental risk. However, because the behavior of hydrocarbon plumes is usually poorly constrained at most leaking underground fuel tank sites in terms of release history, groundwater velocity, dispersion, as well as the biotransformation rate, demonstrating such a limitation in plume length is problematic. Biotransformation signatures in the aquifer geochemistry, most notably elevated bicarbonate, may offer a means of constraining the relationship between plume length and the mean biotransformation rate. In this study, modeled plume lengths and spatial bicarbonate differences among a population of synthetic hydrocarbon plumes, generated through Monte Carlo simulation of an analytical solute transport model, are compared to field observations from six underground storage tank (UST) sites at military bases in California. Simulation results indicate that the relationship between plume length and the distribution of bicarbonate is best explained by biotransformation rates that are consistent with ranges commonly reported in the literature. This finding suggests that bicarbonate can indeed provide an independent means for evaluating limitations in hydrocarbon plume length resulting from biotransformation. (Author)

  12. Development of Pipe Inspection Gauge (PIG) for leak detection in buried pipelines using radiotracer technique

    International Nuclear Information System (INIS)

    Pendharkar, A.S.; Sharma, V.K.; Pant, H.J.; Singh, Gursharan

    2004-01-01

    This paper discusses the development of a portable battery operated radioisotope based pipeline inspection gauge( PIG) for detection and location of leaks as well as to examine the condition of the underground pipelines. The system consists of a scintillation detector, power supply for detector and other electronic circuits. Pulse processing amplifier data acquisition system, readout unit and software to transfer data to computer for further processing. The microcontroller based pig is very useful in a field in an underground pipeline of 6 inch diameter and above. The battery operated pig system developed indigenously is rugged and portable with data storage capacity up to 20 hours. The system was tested under simulated leak conditions and field trials are being planned. (author)

  13. Detailed leak detection test plan and schedule for the Oak Ridge National Laboratory LLLW active pipelines

    International Nuclear Information System (INIS)

    Douglas, D.G.; Starr, J.W.; Juliano, T.M.; Maresca, J.W. Jr.

    1993-09-01

    This document provides a detailed leak detection test plan and schedule for leak testing many of the pipelines that comprise the active portion of the liquid low-level waste (LLLW) system at the Oak Ridge National Laboratory (ORNL). This plan was prepared in response to the requirements of the Federal Facility Agreement (FFA) between the US Department of Energy (DOE) and two other agencies, the US Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC). The LLLW system is an interconnected complex of tanks and pipelines. The FFA distinguishes four categories of tank and pipeline systems within this complex: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA specifically requires leak testing of the Category C systems. This plan and schedule addresses leak testing of the Category C pipelines and those doubly contained pipelines that do not fully meet the requirements for secondary containment as listed in the FFA

  14. CHANGING THE SAFETY CULTURE IN HANFORD TANK FARMS

    Energy Technology Data Exchange (ETDEWEB)

    BERRIOCHOA MV; ALCALA LJ

    2009-01-06

    In 2000 the Hanford Tank Farms had one of the worst safety records in the Department of Energy Complex. By the end of FY08 the safety performance of the workforce had turned completely around, resulting in one of the best safety records in the DOE complex for operations of its kind. This paper describes the variety of programs and changes that were put in place to accomplish such a dramatic turn-around. The U.S. Department of Energy's 586-square-mile Hanford Site in Washington State was established during World War II as part of the Manhattan Project to develop nuclear materials to end the war. For the next several decades it continued to produce plutonium for the nation's defense, leaving behind vast quantities of radioactive and chemical waste. Much of this waste, 53,000,000 gallons, remains stored in 149 aging single-shell tanks and 28 newer double-shell tanks. One of the primary objectives at Hanford is to safely manage this waste until it can be prepared for disposal, but this has not always been easy. These giant underground tanks, many of which date back to the beginning of the Manhattan Project, range in size from 55,000 gallons up to 1.1 million gallons, and are buried beneath 10 feet of soil near the center of the site. Up to 67 of the older single-shell tanks have leaked as much as one million gallons into the surrounding soil. Liquids from the single-shell tanks were removed by 2003 but solids remain in the form of saltcake, sludges and a hardened heel at the bottom of some tanks. The Department of Energy's Office of River Protection was established to safely manage this waste until it could be prepared for disposal. For most of the last seven years the focus has been on safely retrieving waste from the 149 aging single-shell and moving it to the newer double-shell tanks. Removing waste from the tanks is a difficult and complex task. The tanks were made to put waste in, not take it out. Because of the toxic nature of the waste, both

  15. Tank characterization report for double-shell tank 241-AN-102

    International Nuclear Information System (INIS)

    Jo, J.

    1996-01-01

    This characterization report summarizes the available information on the historical uses, current status, and sampling and analysis results of waste stored in double-shell underground storage tank 241- AN-102. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09 (Ecology et al. 1996). Tank 241-AN-102 is one of seven double-shell tanks located in the AN Tank Farm in the Hanford Site 200 East Area. The tank was hydrotested in 1981, and when the water was removed, a 6-inch heel was left. Tank 241-AN-102 began receiving waste from tank 241-SY-102 beginning in 1982. The tank was nearly emptied in the third quarter of 1983, leaving only 125 kL (33 kgal) of waste. Between the fourth quarter of 1983 and the first quarter of 1984, tank 241-AN-102 received waste from tanks 241-AY-102, 241-SY-102, 241-AW-105, and 241- AN-101. The tank was nearly emptied in the second quarter of 1984, leaving a heel of 129 kL (34 kgal). During the second and third quarters of 1984, the tank was filled with concentrated complexant waste from tank 241-AW-101. Since that time, only minor amounts of Plutonium-Uranium Extraction (PUREX) Plant miscellaneous waste and water have been received; there have been no waste transfer to or from the tank since 1992. Therefore, the waste currently in the tank is considered to be concentrated complexant waste. Tank 241-AN-102 is sound and is not included on any of the Watch Lists

  16. Leak detection on underground fuel oil transfer line using radio tracer iodine-131

    International Nuclear Information System (INIS)

    Wickramanayake, D.G.L.; Ranjith, H.L.A.

    1998-01-01

    Leak detection study was carried out on the fuel oil transfer line of the Ceylon Petroleum Corporation using 131 I tracer. The study was carried out to determine whether the technique developed can be used in the field and to monitor the condition of the pipeline. Radiation safety assessment was made prior to the test. The dynamic pressurization technique was used. Any detectable leak was not shown at the detecting sensitivity of 0.40 mm 2 under the test conditions. The method reported is considered to be successful and economically viable. (author)

  17. Static internal pressure capacity of Hanford Single-Shell Waste Tanks

    Energy Technology Data Exchange (ETDEWEB)

    Julyk, L.J.

    1994-07-19

    Underground single-shell waste storage tanks located at the Hanford Site in Richland, Washington, generate gaseous mixtures that could be ignited, challenging the structural integrity of the tanks. The structural capacity of the single-shell tanks to internal pressure is estimated through nonlinear finite-element structural analyses of the reinforced concrete tank. To determine their internal pressure capacity, designs for both the million-gallon and the half-million-gallon tank are evaluated on the basis of gross structural instability.

  18. Static internal pressure capacity of Hanford Single-Shell Waste Tanks

    International Nuclear Information System (INIS)

    Julyk, L.J.

    1994-01-01

    Underground single-shell waste storage tanks located at the Hanford Site in Richland, Washington, generate gaseous mixtures that could be ignited, challenging the structural integrity of the tanks. The structural capacity of the single-shell tanks to internal pressure is estimated through nonlinear finite-element structural analyses of the reinforced concrete tank. To determine their internal pressure capacity, designs for both the million-gallon and the half-million-gallon tank are evaluated on the basis of gross structural instability

  19. Data quality objectives lessons learned for tank waste characterization

    International Nuclear Information System (INIS)

    Eberlein, S.J.; Banning, D.L.

    1996-01-01

    The tank waste characterization process is an integral part of the overall effort to control the hazards associated with radioactive wastes stored in underground tanks at the Hanford Reservation. The programs involved in the characterization of the waste are employing the Data Quality Objective (DQO) process in all information and data collection activities. The DQO process is used by the programs to address an issue or problem rather than a specific sampling event. Practical limits (e.g., limited number and location of sampling points) do not always allow for precise characterization of a tank or the full implementation of the DQO process. Because of the flexibility of the DQO process, it can be used as a planning tool for sampling and analysis of the underground waste storage tanks. The iterative nature of the DQO process allows it to be used as additional information is obtained or open-quotes lessons are learnedclose quotes concerning an issue or problem requiring sampling and analysis of tank waste. In addition, the application of the DQO process forces alternative actions to be considered when precise characterization of a tank or the fall implementation of the DQO process is not practical

  20. Generalized geology of the 241-SY Tank Farm

    International Nuclear Information System (INIS)

    Price, W.H.; Fecht, K.R.

    1976-04-01

    A series of maps has been compiled to document the structure and stratigraphy of the sediments underlying the high-level radioactive waste storage tank farms located within the Energy Research and Development Administration Hanford Reservation. The primary purpose of these maps is to provide the basic geologic information to be utilized to evaluate the impact of suspected and confirmed tank leaks

  1. Engineering development of a lightweight high-pressure scarifier for tank waste retrieval

    Energy Technology Data Exchange (ETDEWEB)

    Hatchell, B.K.

    1997-09-01

    The Retrieval Process Development and Enhancements Program (RPD&E) is sponsored by the U.S. Department of Energy Tanks Focus Area to investigate existing and emerging retrieval processes suitable for the retrieval of high-level radioactive waste inside underground storage tanks. This program, represented by industry, national laboratories, and academia, seeks to provide a technical and cost basis to support site-remediation decisions. Part of this program has involved the development of a high-pressure waterjet dislodging system and pneumatic conveyance integrated as a scarifier. Industry has used high-pressure waterjet technology for many years to mine, cut, clean, and scarify materials with a broad range of properties. The scarifier was developed as an alternate means of retrieving waste inside Hanford single-shell tanks, particularly hard, stubborn waste. Testing of the scarifier has verified its ability to retrieve a wide range of tank waste ranging from extremely hard waste that is resistant to other dislodging means to soft sludge and even supernatant fluid. Since the scarifier expends water at a low rate and recovers most of the water as it is used, the scarifier is well suited for retrieval of tanks that leak and cannot be safely sluiced or applications where significant waste dilution is not acceptable. Although the original scarifier was effective, it became evident that a lighter, more compact version that would be compatible with light weight deployment systems under development, such as the Light Duty Utility Arm, was needed. At the end of FY 95, the Light Weight Scarifier (LWS) was designed to incorporate the features of the original scarifier in a smaller, lighter end effector. During FY 96, the detailed design of the LWS was completed and two prototypes were fabricated.

  2. Engineering development of a lightweight high-pressure scarifier for tank waste retrieval

    International Nuclear Information System (INIS)

    Hatchell, B.K.

    1997-09-01

    The Retrieval Process Development and Enhancements Program (RPD ampersand E) is sponsored by the U.S. Department of Energy Tanks Focus Area to investigate existing and emerging retrieval processes suitable for the retrieval of high-level radioactive waste inside underground storage tanks. This program, represented by industry, national laboratories, and academia, seeks to provide a technical and cost basis to support site-remediation decisions. Part of this program has involved the development of a high-pressure waterjet dislodging system and pneumatic conveyance integrated as a scarifier. Industry has used high-pressure waterjet technology for many years to mine, cut, clean, and scarify materials with a broad range of properties. The scarifier was developed as an alternate means of retrieving waste inside Hanford single-shell tanks, particularly hard, stubborn waste. Testing of the scarifier has verified its ability to retrieve a wide range of tank waste ranging from extremely hard waste that is resistant to other dislodging means to soft sludge and even supernatant fluid. Since the scarifier expends water at a low rate and recovers most of the water as it is used, the scarifier is well suited for retrieval of tanks that leak and cannot be safely sluiced or applications where significant waste dilution is not acceptable. Although the original scarifier was effective, it became evident that a lighter, more compact version that would be compatible with light weight deployment systems under development, such as the Light Duty Utility Arm, was needed. At the end of FY 95, the Light Weight Scarifier (LWS) was designed to incorporate the features of the original scarifier in a smaller, lighter end effector. During FY 96, the detailed design of the LWS was completed and two prototypes were fabricated

  3. High-level waste leakage from the 241-T-106 tank at Hanford

    International Nuclear Information System (INIS)

    Routson, R.C.; Price, W.H.; Brown, D.J.; Fecht, K.R.

    1979-02-01

    The history, status, fate, and impact of the 4.34 x 10 5 -liter (115,000-gal) radioactive waste tank leak from the 241-T-106 tank have been studied since 1973. As of May 1978, the maximum detected depth of the 1-microcurie per liter (μCi/l) concentration of 106 Ru penetration was 33 meters (108 ft) below the ground surface or 29 meters (95 ft) above the regional water table. This maximum depth of penetration was detected in two of the dry wells in the 241-T tank farm. In no other well has radioactivity greater than 1.0-μCi/l been found deeper than 29 meters (95 ft). This is approximately 43% of the distance from the bottom of the tank to the water table. The maximum horizontal movement of the 1-μCi/l 106 Ru concentration front from the tank was approximately 23 meters (75 ft) at a depth of 25 meters (82 ft). This distance is approximately equal to the diameter of the tank. The rate of frontal movement of radioactivity was qualitatively estimated. A large portion of the movement occurred in 1973, prior to the publication of an initial tank leak status report. From 1973 to 1974, detectable lateral movement occurred in at least some sediment layers. From 1974 to 1978, movement could not generally be detected. However, migration in wells near the leak perimeter was detected in 1978, and the probable cause defined. Calculations on vadose zone moisture and wetting frontal movement were found to be essentially in qualitative agreement in their assessed lack of movement of any waste above concentration guidelines to the Hanford ground water. Thus, during the hazardous lifetime of the fission products, there will likely be no amount of radioactivity enter the Hanford ground water. Therefore, there appears to be no impact of the leak on the Columbia River

  4. Hyperspectral reflectance of vegetation affected by underground hydrocarbon gas seepage

    NARCIS (Netherlands)

    Noomen, M.F.

    2007-01-01

    Anomalous concentrations of natural gas in the soil may be sourced from leaking underground gas pipelines or from natural microseepages. Due to the explosive nature of hydrocarbon gases, early detection of these gases is essential to avoid dangerous situations. It is known that natural gas in the

  5. Airborne pipeline leak detection: UV or IR?

    Science.gov (United States)

    Babin, François; Gravel, Jean-François; Allard, Martin

    2016-05-01

    This paper presents a study of different approaches to the measurement of the above ground vapor plume created by the spill caused by a small 0.1 l/min (or less) leak in an underground liquid petroleum pipeline. The scenarios are those for the measurement from an airborne platform. The usual approach is that of IR absorption, but in the case of liquid petroleum products, there are drawbacks that will be discussed, especially when using alkanes to detect a leak. The optical measurements studied include UV enhanced Raman lidar, UV fluorescence lidar and IR absorption path integrated lidars. The breadboards used for testing the different approaches will be described along with the set-ups for leak simulation. Although IR absorption would intuitively be the most sensitive, it is shown that UV-Raman could be an alternative. When using the very broad alkane signature in the IR, the varying ground spectral reflectance are a problem. It is also determined that integrated path measurements are preferred, the UV enhanced Raman measurements showing that the vapor plume stays very close to the ground.

  6. Draft Environmental Impact Statement for the tank waste remediation system. Volume 1

    International Nuclear Information System (INIS)

    1996-04-01

    This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, and Ex Situ/In Situ Combination. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. At this time, DOE and Ecology do not have a preferred alternative for the cesium and strontium capsules

  7. Tank characterization report for Single-Shell Tank B-111

    International Nuclear Information System (INIS)

    Remund, K.M.; Tingey, J.M.; Heasler, P.G.; Toth, J.J.; Ryan, F.M.; Hartley, S.A.; Simpson, D.B.; Simpson, B.C.

    1994-09-01

    Tank 241-B-111 (hereafter referred to as B-111) is a 2,006,300 liter (530,000 gallon) single-shell waste tank located in the 200 East B tank farm at Hanford. Two cores were taken from this tank in 1991 and analysis of the cores was conducted by Battelle's 325-A Laboratory in 1993. Characterization of the waste in this tank is being done to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05. Tank B-111 was constructed in 1943 and put into service in 1945; it is the second tank in a cascade system with Tanks B-110 and B-112. During its process history, B-111 received mostly second-decontamination-cycle waste and fission products waste via the cascade from Tank B-110. This tank was retired from service in 1976, and in 1978 the tank was assumed to have leaked 30,300 liters (8,000 gallons). The tank was interim stabilized and interim isolated in 1985. The tank presently contains approximately 893,400 liters (236,000 gallons) of sludge-like waste and approximately 3,800 liters (1,000 gallons) of supernate. Historically, there are no unreviewed safety issues associated with this tank and none were revealed after reviewing the data from the latest core sampling event in 1991. An extensive set of analytical measurements was performed on the core composites. The major constituents (> 0.5 wt%) measured in the waste are water, sodium, nitrate, phosphate, nitrite, bismuth, iron, sulfate and silicon, ordered from largest concentration to the smallest. The concentrations and inventories of these and other constituents are given. Since Tanks B-110 and B-111 have similar process histories, their sampling results were compared. The results of the chemical analyses have been compared to the dangerous waste codes in the Washington Dangerous Waste Regulations (WAC 173-303). This assessment was conducted by comparing tank analyses against dangerous waste characteristics 'D' waste codes; and against state waste codes

  8. Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks

    Energy Technology Data Exchange (ETDEWEB)

    ROGERS, C.A.

    2000-02-17

    This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

  9. Criticality Safety Evaluation of Hanford Site High-Level Waste Storage Tanks

    International Nuclear Information System (INIS)

    ROGERS, C.A.

    2000-01-01

    This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions

  10. Implementation of environmental compliance for operating radioactive liquid waste systems at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Hooyman, J.H.

    1993-01-01

    This paper addresses methods being implemented at the Oak Ridge National Laboratory (ORNL) to continue operating while achieving compliance with new standards for liquid low level waste (LLLW) underground storage tank systems. The Superfund Amendment and Reauthorization Act (SARA) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) required that the Department of Energy (DOE) execute a Federal Facility Agreement (FFA) with the Environmental Protection Agency (EPA) within 6 months of listing of the ORNL on the National Priorities List. An FFA for ORNL became effective January 1, 1992 among the EPA, DOE, and the Tennessee Department of Environment and Conservation (TDEC). The objective of the FFA as it relates to these tank systems is to ensure that structural integrity, containment, leak detection capability, and LLLW source control are maintained until final remedial action. The FFA requires that leaking LLLW tank systems be immediately removed from service, and that active tank systems be doubly contained, cathodically protected, and have leak detection capability. LLLW tank systems that do not meet requirements are to be either upgraded or replaced, but can remain in service if they do not leak in the interim

  11. Specialized video systems for use in waste tanks

    International Nuclear Information System (INIS)

    Anderson, E.K.; Robinson, C.W.; Heckendorn, F.M.

    1992-01-01

    The Robotics Development Group at the Savannah River Site is developing a remote video system for use in underground radioactive waste storage tanks at the Savannah River Site, as a portion of its site support role. Viewing of the tank interiors and their associated annular spaces is an extremely valuable tool in assessing their condition and controlling their operation. Several specialized video systems have been built that provide remote viewing and lighting, including remotely controlled tank entry and exit. Positioning all control components away from the facility prevents the potential for personnel exposure to radiation and contamination. The SRS waste tanks are nominal 4.5 million liter (1.3 million gallon) underground tanks used to store liquid high level radioactive waste generated by the site, awaiting final disposal. The typical waste tank (Figure 1) is of flattened shape (i.e. wider than high). The tanks sit in a dry secondary containment pan. The annular space between the tank wall and the secondary containment wall is continuously monitored for liquid intrusion and periodically inspected and documented. The latter was historically accomplished with remote still photography. The video systems includes camera, zoom lens, camera positioner, and vertical deployment. The assembly enters through a 125 mm (5 in) diameter opening. A special attribute of the systems is they never get larger than the entry hole during camera aiming etc. and can always be retrieved. The latest systems are easily deployable to a remote setup point and can extend down vertically 15 meters (50ft). The systems are expected to be a valuable asset to tank operations

  12. Remote installation of risers on underground nuclear waste storage tanks

    International Nuclear Information System (INIS)

    Jackson, J.P.; Gessner, R.F.

    1988-03-01

    The West Valley Demonstration Project was established to solidify 2120 m 3 (560,000) gallons of high-level nuclear waste generated during six years of commercial nuclear fuel reprocessing. This liquid will be processed to remove radioactive elements which, with the remaining sludge, will be combined with glass formers and be converted into borosilicate glass. Risers were installed on the high-level tank for installation of pumps which will be used to remove the liquid and sludge. The extensive use of remote technology was required to install the risers and to minimize operator exposure to high levels of radiation and contamination. The riser installation required remotely: drilling through two feet of concrete shielding; installing pump access pipes which are welded to the tank top; and cutting holes in tanks located 3658 mm (12) feet below ground. These operations were successfully completed 13 times without exposing personnel to high-level radiation or contamination. Specially designed remote equipment was developed for each step of this operation. Extensive operator training in the use of this equipment was performed on a tank with low radiation prior to work on the high-level tank. This paper discusses the application of remote technology that assured a quality job was safely accomplished. 3 refs., 18 figs., 2 tabs

  13. Tank characterization report for single-shell Tank 241-B-110

    International Nuclear Information System (INIS)

    Amato, L.C.; De Lorenzo, D.S.; DiCenso, A.T.; Rutherford, J.H.; Stephens, R.H.; Heasler, P.G.; Brown, T.M.; Simpson, B.C.

    1994-08-01

    Single-shell Tank 241-B-110 is an underground storage tank containing radioactive waste. The tank was sampled at various times between August and November of 1989 and later in April of 1990. The analytical data gathered from these sampling efforts were used to generate this Tank Characterization Report. Tank 241-B-110, located in the 200 East Area B Tank Farm, was constructed in 1943 and 1944, and went into service in 1945 by receiving second cycle decontamination waste from the B and T Plants. During the service life of the tank, other wastes were added including B Plant flush waste, B Plant fission product waste, B Plant ion exchange waste, PUREX Plant coating waste, and waste from Tank 241-B-105. The tank currently contains 246,000 gallons of non-complexed waste, existing primarily as sludge. Approximately 22,000 gallons of drainable interstitial liquid and 1,000 gallons of supernate remain. The solid phase of the waste is heterogeneous, for the top layer and subsequent layers have significantly different chemical compositions and are visually distinct. A complete analysis of the top layer has not been done, and auger sampling of the top layer is recommended to fully characterize the waste in Tank 241-B-110. The tank is not classified as a Watch List tank; however, it is a Confirmed Leaker, having lost nearly 10,000 gallons of waste. The waste in Tank 241-B-110 is primarily precipitated salts, some of which are composed of radioactive isotopes. The most prevalent analytes include water, bismuth, iron, nitrate, nitrite, phosphate, silicon, sodium, and sulfate. The major radionuclide constituents are 137 Cs and 90 Sr

  14. History of waste tank 9 , 1955--1974

    International Nuclear Information System (INIS)

    Tharin, D.W.; Lohr, D.R.

    1979-01-01

    Tank 9 was placed in service as a receiver for Purex HLW on July 19, 1955. Filling was essentially completed in December 1955, and this original complement of waste remained in the tank until December 1965, when most of the liquid was decanted to allow refilling. In July 1966, the remaining liquid and approximately 15 inches of sludge were removed using 3000 to 3500 psi water introduced through nozzles to mobilize the sludge. The tank was then used as a receiver and cooler for aged HLW solution concentrated by the tank farm evaporator; the resulting crystallized salt, covered with saturated solution, is now stored in this tank. Inspections have been made of the tank interior and annulus by direct observation and with a 40-ft optical periscope. Analytical samples have been taken of the sludge, supernate, vapor, and leaked material in the annulus. Top-to-bottom profiles of radiation and temperature have been obtained in the annulus and tank, respectively, and measurements have been made of roof deflection caused by salt adhering to roof-supported cooling coils. Leaked waste was discovered in the annulus pan in October 1957. During 1958-59, the annulus pan was flushed nine times with water in 2000-gallon batches, jetting the waste and flush water into the primary tank. However, waste leakage into the annulus continued. The maximum liquid depth reached in the annulus was about 12 inches. This was jetted out in 1961., but some leakage continued theeeafter as indicated by roddings. The roddings showed no standing liquid by August 1964, but some liquid may have been present undera salt crust. In March 1972, salt depth in the annulus was measured to be 8 to 10 in., and the bottom 3 in. was quite wet. The salt remains although most of the liquid has been removed

  15. Leak detection system design and operating considerations for the US-CRBRP

    International Nuclear Information System (INIS)

    Kruger, G.B.; Eng, K.Y.; Kelly, W.L.

    1976-01-01

    Diffusion membrane type hydrogen detectors are provided for monitoring the sodium exiting each evaporator and superheater in the Clinch River Breeder Reactor Plant. These detectors allow detection of small water to sodium leaks and provide the plant operator with an early warning signal. Hydrogen detectors are located at the exit sodium streams of each steam generator module, the vent from the module semi-stagnant region, the cold leg piping, and in an intermediate system sodium expansion tank cover gas region. In addition, an electrochemical oxygen detector is located in the cold leg piping. The leak detection system is capable of detecting the presence of steam/water leaks on the order of 0.45 x 10 -5 kg/sec or larger and of signaling within one to three minutes upon initiation of a leak, during normal operation. Operator action is taken upon receipt of a leak signal to shutdown the affected system, by closing steam/water isolation valves and depressurizing the affected unit

  16. EVALUATION OF SOIL WASHING TECHNOLOGY: RESULTS OF BENCH SCALE EXPERIMENTS ON PETROLEUM FUELS CONTAMINATED SOILS - EPA/600/S2-91/023

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) through its Risk Reduction Engineering Laboratory's Release Control Branch has undertaken research and development efforts to address the problem of leaking underground storage tanks (USTs). Under this effort, EPA is currently eva...

  17. Annual radioactive waste tank inspection program -- 1993

    International Nuclear Information System (INIS)

    McNatt, F.G. Sr.

    1994-05-01

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1993 to evaluate these vessels, and evaluations based on data accrued by inspections made since the tanks were constructed, are the subject of this report. The 1993 inspection program revealed that the condition of the Savannah River Site waste tanks had not changed significantly from that reported in the previous annual report. No new leaksites were observed. No evidence of corrosion or materials degradation was observed in the waste tanks. However, degradation was observed on covers of the concrete encasements for the out-of-service transfer lines to Tanks 1 through 8

  18. High level helium leak testing methods developed at ICSI Rm. Valcea

    International Nuclear Information System (INIS)

    Saros, Gili; Armeanu, Adrian; Saros, Irina; Ciortea, Constantin

    2007-01-01

    Full text: Helium leak detection is one of the most widely used methods of nondestructive testing in use today. In principle two methods are applied for leak testing and localization of leaks, the 'Vacuum method' and the 'Overpressure method'. In case of the 'Vacuum method' the object to be examined for leaks is evacuated and filled instead with Helium. The gas penetrates through any leaks found in the object and is detected by the leak test instrument. In case of the 'Overpressure method' the object to be examined for leaks is filled with Helium, under slight overpressure. The gas escapes through any leaks present and it is detected by a detector probe. This detector probe sometimes called a 'sniffer' acting as a gas sampling probe. Varian 979 Helium Leak Detector has a built-in turbo pump and an externally mounted dry forepump located below the system. The leak detector is configured for the evacuation type leak testing. In this case, the vacuum system under test is evacuated by the leak detector. Helium is then sprayed on the outside of the vacuum system and is pumped into the leak detector if a leak is present. The leak detector is capable to detect leaks down to 10 -9 atm-cc/sec range. The Specton 300E is a strong, rugged leak detector designed to operate in dirty industrial conditions as well as clean research areas. A number of applications are mentioned: - Generators; - Buried Pipelines; - Chemical and power plants; - Vacuum furnace installations; - Heat Exchangers; - Tank Floors; - Nuclear research centers; - Refrigeration installations; - Any type of industrial vacuum system. (authors)

  19. Material Balance Assessment for Double-Shell Tank Waste Pipeline Transfer

    International Nuclear Information System (INIS)

    Onishi, Yasuo; Wells, Beric E; Hartley, Stacey A; Enderlin, Carl W

    2001-01-01

    PNNL developed a material balance assessment methodology based on conservation of mass for detecting leaks and mis-routings in pipeline transfer of double-shell tank waste at Hanford. The main factors causing uncertainty in these transfers are variable property and tank conditions of density, existence of crust, and surface disturbance due to mixer pump operation during the waste transfer. The methodology was applied to three waste transfers from Tanks AN-105 and AZ-102

  20. Hanford Site Tank Waste Remediation System

    International Nuclear Information System (INIS)

    1993-05-01

    The US Department of Energy's (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives

  1. Tank 241-C-106 past-practice sluicing waste retrieval, Hanford Site, Richland, Washington. Environmental Assessment

    International Nuclear Information System (INIS)

    1995-02-01

    The US Department of Energy (DOE) needs to take action to eliminate safety concerns with storage of the high-heat waste in Tank 241-C-106 (Tank C-106), and demonstrate a tank waste retrieval technology. This Environmental Assessment (EA) was prepared to analyze the potential impacts associated with the proposed action, past-practice sluicing of Tank C-106, an underground single-shell tank (SST). Past-practice sluicing is defined as the mode of waste retrieval used extensively in the past at the Hanford Site on the large underground waste tanks, and involves introducing a high-volume, low-pressure stream of liquid to mobilize sludge waste prior to pumping. It is proposed to retrieve the waste from Tank C-106 because this waste is classified not only as transuranic and high-level, but also as high-heat, which is caused by the radioactive decay of strontium. This waste characteristic has led DOE to place Tank C-106 on the safety ''Watchlist.''

  2. Assessment of vadose zone radionuclide contamination around Single Shell Tank 241-C-103

    International Nuclear Information System (INIS)

    Kos, S.E.

    1995-12-01

    Five drywells surrounding single shell tank 241-C-103 were logged with the high-purity germanium logging system to investigate possible leakage of radioactive contamination from the tank. The investigation included integration of the drywell survey results with several other data sources. There is no conclusive evidence showing indications that the 241-C-103 tank has leaked

  3. Addendum to the corrective action plan for Underground Storage Tanks 1219-U, 1222-U, 2082-U, 2068-U at the Rust Garage Facility, Buildings 9720-15 and 9754-1: Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Facility ID number-sign 0-010117

    International Nuclear Information System (INIS)

    1994-01-01

    This document represents an addendum to the Corrective Action Plan (CAP) for underground storage tanks 1219-U, 2082-U, and 2068-U located at Buildings 9720-15 and 9754-1, Oak Ridge Y-12 Plant, Oak Ridge, TN. The site of the four underground storage tanks is commonly referred to as the Rust Garage Facility. The original CAP was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review in May 1992. During the time period after submission of the original CAP for the Rust Garage Facility, Y-12 Plant Underground Storage Tank (UST) Program personnel continued to evaluate improvements that would optimize resources and expedite the activities schedule presented in the original CAP. Based on these determinations, several revisions to the original corrective action process options for remediation of contaminated soils are proposed. The revised approach will involve excavation of the soils from the impacted areas, on-site thermal desorption of soil contaminants, and final disposition of the treated soils by backfilling into the subject site excavations. Based on evaluation of the corrective actions with regard to groundwater, remediation of groundwater under the Y-12 Plant CERCLA Program is proposed for the facility

  4. Detection of primary coolant leaks in NPP

    International Nuclear Information System (INIS)

    Slavov, S.; Bakalov, I.; Vassilev, H.

    2001-01-01

    The thermo-hydraulic analyses of the SG box behaviour of Kozloduy NPP units 3 and 4 in case of small primary circuit leaks and during normal operation of the existing ventilation systems in order to determine the detectable leakages from the primary circuit by analysing different parameters used for the purposes of 'Leak before break' concept, performed by ENPRO Consult Ltd. are presented. The following methods for leak detection: measurement of relative air humidity in SG box (can be used for detection of leaks with flow rate 3.78 l/min within one hour at ambient parameters - temperature 40 0 - 60 0 C and relative humidity form 30% to 60%); measurement of water level in SG box sumps (can not be used for reliable detection of small primary circuit leakages with flow rate about 3.78 l/min); measurement of gaseous radioactivity in SG box( can be used as a general global indication for detection of small leakages from the primary circuit); measurement of condensate flow after the air coolers of P-1 venting system (can be used for primary circuit leak detection) are considered. For determination of the confinement behaviour, a model used with computer code MELCOR has been developed by ENPRO Consult Ltd. A brief summary based on the capabilities of the different methods of leak detection, from the point of view of the applicability of a particular method is given. For both Units 3 and 4 of Kozloduy NPP a qualified complex system for small leak detection is planned to be constructed. Such a system has to unite the following systems: acoustic system for leak detection 'ALUS'; system for control of the tightness of the main primary circuit pipelines by monitoring the local humidity; system for primary circuit leakage detection by measuring condensate run-off in collecting tank after ventilation system P-1 air coolers

  5. Structural design and analysis of the multi-function waste tanks

    International Nuclear Information System (INIS)

    Farnworth, S.K.; Stine, M.D.; Miller, L.K.

    1993-10-01

    This paper describes structural design and analysis procedures to be used for the Multi-function Waste Tank Facility underground waste storage tanks proposed for the Hanford Site. The Multi-function Waste Tank Facility will consist of four one-million-gallon nominal capacity, double-shell, underground waste storage tanks and will include the associated process and control systems and aboveground structures. The tanks will consist of an inner primary steel tank and an outer secondary reinforced-concrete steel-lined tank. The primary tank head will be structurally attached to the concrete dome. A supporting layer of material will be placed between the bottom of the primary steel tank and the bottom of the steel liner on the secondary tank. The tank analysis is undertaken jointly by a team of engineers and analysts representing Kaiser Engineers Hanford, the site architect/engineer, and Westinghouse Hanford Company, the site management and operating contractor. This analysis is planned in several phases. Heat transfer solutions will address the anticipated mixing pump and cyclic fill/drain environment to provide steel and concrete temperature distributions. With this information, an in situ static analysis of the reinforced-concrete secondary tank will be carried out over the structure design life and will give material states and deformations along with strength and stability checks. Seismic analysis, accounting for soil-structure interaction and liquid loads, will be conducted with the most conservative material state, and the in situ deformations will be incorporated. Finally, penetrations and other components will be analyzed

  6. Structural design and analysis of the multi-function waste tanks

    International Nuclear Information System (INIS)

    Farnworth, S.K.; Stine, M.D.; Miller, L.K.

    1993-01-01

    This paper describes structural design and analysis procedures to be used for the Multi-function Waste Tank Facility underground waste storage tanks proposed for the Hanford Site. The Multi-function Waste Tank Facility will consist of four one-million-gallon nominal capacity, double-shell, underground waste storage tanks and will include the associated process and control systems and aboveground structures. The tanks will consist of an inner primary steel tank and an outer secondary reinforced-concrete steel-linked tank. The primary tank head will be structurally attached to the concrete dome. A supporting layer of material will be placed between the bottom of the primary steel tank and the bottom of the steel linear on the secondary tank. The tank analysis is undertaken jointly by a team of engineers and analysts representing Kaiser Engineers Hanford, the site architect/engineer, and Westinghouse Hanford Company, the site management and operating contractor. This analysis is planned in several phases. Heat transfer solutions will address the anticipated mixing pump and cyclic fill/drain environment to provide steel and concrete temperature distributions. With this information, an in situ static analysis of the reinforced-concrete secondary tank will be carried out over the structure design life and will give material states and deformations along with strength and stability checks. Seismic analysis, accounting for soil-structure interaction and liquid loads, will be conducted with the most conservative material state, and the in situ deformations will be incorporated. Finally, penetrations and other components will be analyzed

  7. Contaminant Release from Residual Waste in Closed Single-Shell Tanks and Other Waste Forms Associated with the Tanks

    International Nuclear Information System (INIS)

    Deutsch, William J.

    2008-01-01

    This chapter describes the release of contaminants from the various waste forms that are anticipated to be associated with closure of the single-shell tanks. These waste forms include residual sludge or saltcake that will remain in the tanks after waste retrieval. Other waste forms include engineered glass and cementitious materials as well as contaminated soil impacted by previous tank leaks. This chapter also describes laboratory testing to quantify contaminant release and how the release data are used in performance/risk assessments for the tank waste management units and the onsite waste disposal facilities. The chapter ends with a discussion of the surprises and lessons learned to date from the testing of waste materials and the development of contaminant release models

  8. Fuel storage tanks at FAA facilities : Order 1050.15A : executive summary.

    Science.gov (United States)

    1997-04-30

    The Federal Aviation Administration (FAA) has over 4,000 fuel storage tanks (FST) in its inventory. Most of these FSTs are underground storage tanks (UST) that contain fuel for emergency backup generators providing secondary power to air navigational...

  9. Batch test equilibration studies examining the removal of Cs, Sr, and Tc from supernatants from ORNL underground storage tanks by selected ion exchangers

    International Nuclear Information System (INIS)

    Collins, J.L.; Egan, B.Z.; Anderson, K.K.; Chase, C.W.; Bell, J.T.

    1995-01-01

    Bench-scale batch equilibration tests have been conducted with supernatants from two underground tanks at the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to determine the effectiveness of selected ion exchangers in removing cesium, strontium, and technetium. Seven sorbents were evaluated for cesium removal, nine for strontium removal, and four for technetium removal. The results indicate that granular potassium cobalt hexacyanoferrate was the most effective of the exchangers evaluated for removing cesium from the supernatants. The powdered forms of sodium titanate (NaTiO) and cystalline silicotitanate (CST) were superior in removing the strontium; however, for the sorbents of suitable particle size for column use, titanium monohydrogen phosphate (TiHP φ), sodium titanate/polyacrylonitrile (NaTiO-PAN), and titanium monohydrogen phosphate/polyacrylonitrile (TiP-PAN) gave the best results and were about equally effective. Reillex trademark 402 was the most effective exchanger in removing the technetium; however, it was only slightly more satisfactory than Reillex trademark HPQ

  10. Bioremediation Of Groundwater Contaminated Wtih Gasoline Hydrocarbons And Oxygenates Using A Membrane-Based Reactor

    Science.gov (United States)

    The objective of this study was to operate a novel, field-scale, aerobic bioreactor and assess its performance in the ex situ treatment of groundwater contaminated with gasoline from a leaking underground storage tank in Pascoag, RI. The groundwater contained elevated concentrat...

  11. POTENTIAL REUSE OF PETROLEUM-CONTAMINATED SOIL: A DIRECTORY OF PERMITTED RECYCLING FACILITIES

    Science.gov (United States)

    Soil contaminated by virgin petroleum products leaking from underground storage tanks Is a pervasive problem in the United States. Economically feasible disposal of such soil concerns the responsible party (RP), whether the RP is one individual small business owner, a group o...

  12. Where Did the Water Go?: Boyle's Law and Pressurized Diaphragm Water Tanks

    Science.gov (United States)

    Brimhall, James; Naga, Sundar

    2007-01-01

    Many homes use pressurized diaphragm tanks for storage of water pumped from an underground well. These tanks are very carefully constructed to have separate internal chambers for the storage of water and for the air that provides the pressure. One might expect that the amount of water available for use from, for example, a 50-gallon tank would be…

  13. Design, fabrication and operating experience of Monju ex-vessel fuel storage tank

    International Nuclear Information System (INIS)

    Yokota, Yoshio; Yamagishi, Yoshiaki; Kuroha, Mitsuo; Inoue, Tatsuya

    1995-01-01

    In FBRs there are two methods of storing and cooling the spent fuel - the in-vessel storage and the ex-vessel storage. Because of the sodium leaks through the tank at the beginning of pre-operation, the utilization of the ex-vessel fuel storage tank (EVST) of some FBR plant has been changed from the ex-vessel fuel storage to the interim fuel transfer tank. This led to reactor designers focusing on the material, structure and fabrication of the carbon steel sodium storage tanks worldwide. The Monju EVST was at the final stage of the design, when the leaks occurred. The lesson learned from that experience and the domestic fabrication technology are reflected to the design and fabrication of the Monju EVST. This paper describes the design, fabrication and R and D results for the tank, and operating experience in functional test. The items to be examined are as follows: (1) Overall structure of the tank and design philosophy on the function, (2) Structure of the cover shielding plug and its design philosophy, (3) Structures of the rotating rack and its bearings, and their design philosophy, (4) Cooling method and its design philosophy, (5) Structure and fabrication of the cooling coil support inside EVST with comparison of leaked case, (6) R and D effort for items above. The fabrication of the Monju EVST started in August 1986 and it was shipped to the site in March 1990. Installation was completed in November 1990, and sodium fill after pre-heating started in 1991. The operation has been continued since September 1992. In 1996 when the first spent fuel is stored, its total functions will be examined. (author)

  14. Performance evaluation of PFBR wire type sodium leak detectors

    International Nuclear Information System (INIS)

    Vijayakumar, G.; Rajan, K.K.; Nashine, B.K.; Chandramouli, S.; Madhusoodanan, K.; Kalyanasundaram, P.

    2011-01-01

    Highlights: → Performance evaluation of wire type leak detectors was conducted in LEENA facility by creating sodium leaks. → The lowest leak rate of 214 g/h was detected in 50 min and the highest detection time was 6 h for a leak rate of 222 g/h. → Factors affecting the leak detection time are packing density of thermal insulation, layout of heater, temperature, etc. → Relationship between leak rate and detection time was established and a leak rate of 100 g/h is likely to be detected in 11.1 h. → Contact resistance of leaked sodium increased to 3.5 kilo ohms in 20 h. - Abstract: Wire type leak detectors working on conductivity principle are used for detecting sodium leak in the secondary sodium circuits of fast breeder reactors. It is required to assess the performance of these detectors and confirm that they are meeting the requirements. A test facility by name LEENA was constructed at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam to test the wire type leak detector lay out by simulating different sodium leak rates. This test facility consists of a sodium dump tank, a test vessel, interconnecting pipelines with valves, micro filter and test section with leak simulators. There are three different test sections in the test set up of length 1000 mm each. These test sections simulate piping of Prototype Fast Breeder Reactor (PFBR) secondary circuit and the wire type leak detector layout in full scale. All test sections are provided with leak simulators. A leak simulator consists of a hole of size one mm drilled in the test section and closed with a tapered pin. The tapered pin position in the hole is adjusted by a screw mechanism and there by the annular gap of flow area is varied for getting different leak rates. Various experiments were conducted to evaluate the performance of the leak detectors by creating different sodium leak rates. This paper deals with the details of wire type leak detector layout for the secondary sodium circuit of

  15. Tank characterization report for single-shell tank 241-B-104

    International Nuclear Information System (INIS)

    Field, J.G.

    1996-01-01

    This document summarizes information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-104. Sampling and analyses meet safety screening and historical data quality objectives. This report supports the requirements of Tri-party Agreement Milestone M-44-09. his characterization report summoned the available information on the historical uses and the current status of single-shell tank 241-B-104, and presents the analytical results of the June 1995 sampling and analysis effort. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order Milestone M-44-09 (Ecology et al. 1994). Tank 241-B-104 is a single-shell underground waste storage tank located in the 200 East Area B Tank Farm on the Hanford Site. It is the first tank in a three-tank cascade series. The tank went into service in August 1946 with a transfer of second-cycle decontamination waste generated from the bismuth phosphate process. The tank continued to receive this waste type until the third quarter of 1950, when it began receiving first-cycle decontamination waste also produced during the bismuth phosphate process. Following this, the tank received evaporator bottoms sludge from the 242-B Evaporator and waste generated from the flushing of transfer lines. A description and the status of tank 241-B-104 are sum in Table ES-1 and Figure ES-1. The tank has an operating capacity of 2,010 kL (530 kgal), and presently contains 1,400 kL (371 kgal) of waste. The total amount is composed of 4 kL (1 kgal) of supernatant, 260 kL (69 kgal) of saltcake, and 1,140 kL (301 kgal) of sludge (Hanlon 1995). Current surveillance data and observations appear to support these results

  16. Safety analysis report for the North Tank Farm, Tank W-11, and the Gunite and Associated Tanks -- Treatability Study, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Platfoot, J.H.

    1997-02-01

    The North Tank Farm (NTF) tanks consist of eight underground storage tanks which have been removed from service because of age and changes in liquid waste system needs and requirements. Tank W-11, which was constructed in 1943, has been removed from service, and contains several hundred gallons of liquid low-level waste (LLLW). The Gunite and Associated Tanks (GAAT) Treatability Study involves the demonstration of sludge removal techniques and equipment for use in other waste storage tanks throughout the Department of Energy (DOE) complex. The hazards associated with the NTF, Tank W-11, and the Treatability Study are identified in hazard identification table in Appendixes A, B, and C. The hazards identified for the NTF, Tank W-11, and the Treatability Study were analyzed in the preliminary hazards analyses (PHA) included as Appendices D and E. The PHA identifies potential accident scenarios and qualitatively estimates the consequences. Because of the limited quantities of materials present in the tanks and the types of energy sources that may result in release of the materials, none of the accidents identified are anticipated to result in significant adverse health effects to on-site or off-site personnel

  17. The observation of eqrthquake in the neighborhood of a large underground cavity

    International Nuclear Information System (INIS)

    Komada, Hiroya; Hayashi, Masao

    1980-01-01

    Studies on the earthquake resistance design of underground site for such large important structures as nuclear power plants, high-level radioactive waste repositories, LNG tanks, petroleum tanks, big power transmission installations and compressed air energy storage installations have been examined at our research institute. The observations of earthquake have been examined at Shiroyama underground hydroelectric power station since July 1976 as one of the demonstration of the earthquake resistance, and the first report was already published. After the time accelerometers and dynamic strain meters were additionally installed. Good acceleration waves and dynamic strain waves of the Izu-Hanto-Toho-Oki Earthquake, June 29, 1980 were observed at Shiroyama site, at which the hypocentral distance is 77 km and the intensity scale is about 4. In this report, the characteristic of the oscillation wave in the neighborhood of underground cavity and the relationships among accelerations, velocities, deformations and dynamic strains are studied in detail on the above earthquake data. (author)

  18. Supporting document for the historical tank content estimate for SY-tank farm

    Energy Technology Data Exchange (ETDEWEB)

    Brevick, C.H.

    1997-08-12

    The purpose of this historical characterization document is to present the synthesized summaries of the historical records concerning the physical characteristics, radiological, and chemical composition of mixed wastes stored in underground double-shell tanks and the physical condition of these tanks. The double-shell tanks are located on the United States Department of Energy`s Hanford Site, approximately 25 miles northwest or Richland, Washington. The document will be used to assist in characterizing the waste in the tanks in conjunction with the current program of sampling and analyzing the tank wastes. Los Alamos National Laboratory (LANL) developed computer models that used the historical data to attempt to characterize the wastes and to generate estimates of each tank`s inventory. A historical review of the tanks may reveal anomalies or unusual contents that could be critical to characterization and post characterization activities. This document was developed by reviewing the operating plant process histories, waste transfer data, and available physical and chemical data from numerous resources. These resources were generated by numerous contractors from 1945 to the present. Waste characterization, the process of describing the character or quality of a waste, is required by Federal law (Resource Conservation and Recovery Act [RCRA]) and state law (Washington Administrative Code [WAC] 173-303, Dangerous Waste Regulations). Characterizing the waste is necessary to determine methods to safely retrieve, transport, and/or treat the wastes.

  19. Alternative designs for petroleum product storage tanks for groundwater protection.

    Science.gov (United States)

    Oke Adeleke, Samson

    In developing countries, there are numerous occurrences of petroleum product spillage in groundwater. The current practice of burying storage tanks beneath the surface without adequate safety devices facilitates this phenomenon. Underground tanks rust and leak, and spilled petroleum products migrate downward. The movement of the oil in the soil depends on its viscosity and quantity, the permeability of the soil/rock, and the presence of fractures within the rock. The oil spreads laterally in the form of a thin pancake due to its lower specific gravity, and soluble components dissolve in water. The pollution plume of petroleum products and dissolved phases moves in the direction of groundwater flow in the aquifer within the pores of soil and sediments or along fractures in basement complex areas. Most communities reply heavily on groundwater for potable and industrial supplies. However, the sustainability of this resource is under threat in areas where there are filling stations as a result of significant groundwater contamination from petroleum product spillage. Drinking water becomes unpalatable when it contains petroleum products in low concentrations, and small quantities may contaminate large volumes of water. Considering the losses incurred from spillage, the cost of cleaning the aquifer, and the fact that total cleansing and attenuation is impossible, the need to prevent spillage and if it happens to prevent it from getting into the groundwater system is of paramount importance. This paper proposes alternative design procedures with a view to achieving these objectives.

  20. Vitrification technology for Hanford Site tank waste

    International Nuclear Information System (INIS)

    Weber, E.T.; Calmus, R.B.; Wilson, C.N.

    1995-04-01

    The US Department of Energy's (DOE) Hanford Site has an inventory of 217,000 m 3 of nuclear waste stored in 177 underground tanks. The DOE, the US Environmental Protection Agency, and the Washington State Department of Ecology have agreed that most of the Hanford Site tank waste will be immobilized by vitrification before final disposal. This will be accomplished by separating the tank waste into high- and low-level fractions. Capabilities for high-capacity vitrification are being assessed and developed for each waste fraction. This paper provides an overview of the program for selecting preferred high-level waste melter and feed processing technologies for use in Hanford Site tank waste processing

  1. Detection of a leaking boron-carbide control rod in a TRIGA Mark I reactor

    Energy Technology Data Exchange (ETDEWEB)

    Blotcky, A J; Arsenault, L J [General Medical Research, Veterans Administration Hospital, Omaha (United States)

    1974-07-01

    During a routine quarterly inspection of the boron-carbide control rods of the Omaha Veterans Administration Hospital 18 kW Triga Mark I reactor, a pin hole leak was detected approximately 3 mm from the chamfered edge. The leak was found by observing bubbles when the rod was withdrawn from the reactor tank for visual observation, and could not be seen with the naked eye. This suggests that pin hole leaks could occur and not be visually detected in control rods and fuel elements examined underwater. A review of the rod calibrations showed that the leak had not caused a loss in rod worth. Slides will be presented showing the bubbles observed during the inspection, together with an unmagnified and magnified view of the pin hole. (author)

  2. Detection of a leaking boron-carbide control rod in a TRIGA Mark I reactor

    International Nuclear Information System (INIS)

    Blotcky, A.J.; Arsenault, L.J.

    1974-01-01

    During a routine quarterly inspection of the boron-carbide control rods of the Omaha Veterans Administration Hospital 18 kW Triga Mark I reactor, a pin hole leak was detected approximately 3 mm from the chamfered edge. The leak was found by observing bubbles when the rod was withdrawn from the reactor tank for visual observation, and could not be seen with the naked eye. This suggests that pin hole leaks could occur and not be visually detected in control rods and fuel elements examined underwater. A review of the rod calibrations showed that the leak had not caused a loss in rod worth. Slides will be presented showing the bubbles observed during the inspection, together with an unmagnified and magnified view of the pin hole. (author)

  3. Tank waste treatment science

    International Nuclear Information System (INIS)

    LaFemina, J.P.; Blanchard, D.L.; Bunker, B.C.; Colton, N.G.; Felmy, A.R.; Franz, J.A.; Liu, J.; Virden, J.W.

    1994-01-01

    Remediation efforts at the U.S. Department of Energy's Hanford Site require that many technical and scientific principles be combined for effectively managing and disposing the variety of wastes currently stored in underground tanks. Based on these principles, pretreatment technologies are being studied and developed to separate waste components and enable the most suitable treatment methods to be selected for final disposal of these wastes. The Tank Waste Treatment Science Task at Pacific Northwest Laboratory is addressing pretreatment technology development by investigating several aspects related to understanding and processing the tank contents. The experimental work includes evaluating the chemical and physical properties of the alkaline wastes, modeling sludge dissolution, and evaluating and designing ion exchange materials. This paper gives some examples of results of this work and shows how these results fit into the overall Hanford waste remediation activities. This work is part of series of projects being conducted for the Tank Waste Remediation System

  4. Bacterial distribution and metabolic activity in subsurface sediments from a gasoline spill

    International Nuclear Information System (INIS)

    Krauter, P.W.; Hanna, M.L.; Taylor, R.T.; Rice, D.W. Jr.

    1992-05-01

    At the Lawrence Livermore National Laboratory (LLNL) in California, a records inspection in 1979 indicated an inventory of about 17,500 gal was missing from underground fuel tanks. A leak or leaks in the southernmost tank and/or pipe lines were suspected to be the source of the loss. All four tanks were taken out of service and filled with sand in 1980. The gasoline spill cleanup effort affords an opportunity to study the collective effect of fuel hydrocarbons (HCs) on the indigenous microbial population within the heterogeneous alluvial subsurface environment. This paper presents the early results of an ongoing study to (1) characterize naturally acclimated microbial populations capable of transforming HCs and (2) understand the effects of environmental factors on these biotransformations

  5. Tank 19F Folding Crawler Final Evaluation

    International Nuclear Information System (INIS)

    Nance, T.

    2000-01-01

    The Department of Energy (DOE) is committed to removing millions of gallons of high-level radioactive waste FR-om 51 underground waste storage tanks at the Savannah River Site (SRS). The primary radioactive waste constituents are strontium, plutonium,and cesium. It is recognized that the continued storage of this waste is a risk to the public, workers, and the environment. SRS was the first site in the DOE complex to have emptied and operationally closed a high-level radioactive waste tank. The task of emptying and closing the rest of the tanks will be completed by FY28

  6. Tank waste remediation system: An update

    International Nuclear Information System (INIS)

    Alumkal, W.T.; Babad, H.; Dunford, G.L.; Honeyman, J.O.; Wodrich, D.D.

    1995-02-01

    The US Department of Energy's Hanford Site, located in southeastern Washington State, contains the largest amount and the most diverse collection of highly radioactive waste in the US. High-level radioactive waste has been stored at the Hanford Site in large, underground tanks since 1944. Approximately 217,000 M 3 (57 Mgal) of caustic liquids, slurries, saltcakes, and sludges have accumulated in 177 tanks. In addition, significant amounts of 90 Sr and 137 Cs were removed from the tank waste, converted to salts, doubly encapsulated in metal containers, and stored in water basins. The Tank Waste Remediation System Program was established by the US Department of Energy in 1991 to safely manage and immobilize these wastes in anticipation of permanent disposal of the high-level waste fraction in a geologic repository. Since 1991, significant progress has been made in resolving waste tank safety issues, upgrading Tank Farm facilities and operations, and developing a new strategy for retrieving, treating, and immobilizing the waste for disposal

  7. Risk characterization data manual for Category D inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-09-01

    This manual reports the results of a risk characterization of Category D inactive liquid low-level radioactive waste (LLLW) underground storage tanks (Uses) at the Oak Ridge National Laboratory (ORNL). The risk characterization is required by the Federal Facility Agreement between the Department of Energy-Oak Ridge Operations Office, the Environmental Protection Agency-Region IV, and the Tennessee Department of Environment and Conservation. The intent of the risk characterization is to determine relative priorities for assessment and remediation. A total of 55 FFA Category D inactive LLLW tanks are discussed in this manual. Of the 39 tanks at ORNL that have been accepted into the Environmental Restoration (ER) Program, all have been sampled for preliminary characterization, except for 5 tanks that were found to be empty plus I that was found not to exist. The remaining 16 tanks are in the Waste Management (WM) Program. Twelve were sampled for preliminary characterization, and four were found empty. Each sampled tank was scored on a scale of I to 5 on the basis of three criteria: (1) leak characteristics, (2) location, and (3) toxicological characteristics of residual sludges and liquids. Each criterion was assigned a weighing factor based on perceived importance. The criterion score multiplied by the weighting factor equaled the tank's total score for that criterion. The three weighted criterion scores for each tank were then summed for a total score for that tank. When the scores for all tanks had been weighted and summed, the tanks were ranked in descending order on the basis of their total scores. The highest possible score for a tank is 30. The descending rank order represents the recommended priorities for evaluation: the higher the score, the higher the priority for evaluation. Of the 54 tanks sampled in the risk characterization, 23 tanks scored 16 or higher, 11 scored between 10 and 15, 5 scored between 4 and 9, and 15 scored 3 or less

  8. Risk characterization data manual for Category D inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-07-01

    This manual reports the results of a risk characterization of Category D inactive liquid low-level radioactive waste (LLLW) underground storage tanks (USTs) at the Oak Ridge National Laboratory (ORNL). The risk characterization is required by the Federal Facility Agreement between the Department of Energy-Oak Ridge Operations Office, the Environmental Protection Agency-Region IV, and the Tennessee Department of Environment and Conservation. The intent of the risk characterization is to determine relative priorities for assessment and remediation. A total of 55 FFA Category D inactive LLLW tanks are discussed in this manual. Of the 39 tanks at ORNL that have been accepted into the Environmental Restoration (ER) Pregrain, all have been sampled for preliminary characterization, except for 5 tanks that were found to be empty plus 1 that was found not to exist. The remaining 16 tanks are in the Waste Management (WM) Program. Twelve were sampled for preliminary characterization, and four were found empty. Each sampled tank was scored on a scale of I to 5 on the basis of three criteria: (1) leak characteristics, (2) location, and (3) toxicological characteristics of residual sludges and liquids. Each criterion was assigned a weighing factor based on perceived importance. The criterion score multiplied by the weighting factor equaled the tank's total score for that criterion. The three weighted criterion scores for each tank were then summed for a total score for that tank. When the scores for all tanks had been weighted and summed, the tanks were ranked in descending order on the basis of their total scores. The highest possible score for a tank is 30. The descending rank order represents the recommended priorities for evaluation: the higher the score, the higher the priority for evaluation. Of the 54 tanks sampled in the risk characterization, 23 tanks scored 16 or higher, 11 scored between 10 and 15, 5 scored between 4 and 9, and 15 scored 3 or less

  9. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final environmental impact statement. Summary

    International Nuclear Information System (INIS)

    1996-08-01

    This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

  10. Recommended Practices to Improve Nurse Tank Safety: Phase II

    Science.gov (United States)

    2013-12-01

    This project addressed four topics: Pinhole leaks in nurse tanks were studied by radiography, serial milling, and side-angle ultrasound. These measurements indicated that welding surfaces contaminated by water, mill scale, rust, or other contamin...

  11. REMEDIATION OF MTBE - CONTAMINATED WATER: STUDIES ON THE DEGRADATION OF MTBE INTERMEDIATES USING THE FENTON'S REAGENT

    Science.gov (United States)

    The recent findings of unusual oncentrations of MTBE in groundwater aquifers and surface waters [1] originated most probably from the leaking of underground storage gasoline tanks [2[ has led to a series of judicial and legislative actions, especially in the state of California w...

  12. Position paper: Live load design criteria for Project W-236A Multi-Function Waste Tank Facility

    International Nuclear Information System (INIS)

    Giller, R.A.

    1995-01-01

    The purpose of this paper is to discuss the live loads applied to the underground storage tanks of the Multi Function Waste Tank Facility, and to provide the basis for Project W-236A live load criteria. Project 236A provides encompasses building a Weather Enclosure over the two underground storage tanks at the 200-West area. According to the Material Handling Study, the Groves AT 1100 crane used within the Weather Enclosure will have a gross vehicle weight of 66.5 tons. Therefore, a 100-ton concentrated live load is being used for the planning of the construction of the Weather Enclosure

  13. Engineering study - installation of new risers in Single-Shell Tanks

    International Nuclear Information System (INIS)

    Magruder, W.J.

    1994-08-01

    A sampling program is being developed to characterize the 149 underground SSTs on the Hanford Site. The sampling effort will require access to the tank interior in a minimum of two locations per tank. Some of the risers suitable for sampling are either unavailable or are not in locations for proper characterization of the tank contents. Additional risers will be required in the SSTs to support the tank characterization sampling program. The purpose of this engineering study is to review alternatives for installation of new riser in the SSTs

  14. Flammable gas tank waste level reconciliation tank 241-SX-105

    International Nuclear Information System (INIS)

    Brevick, C.H.; Gaddie, L.A.

    1997-01-01

    Fluor Daniel Northwest was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 241-SX-105 (SX-105, typical). The trapped gas evaluation document states that Tank SX-105 exceeds the 25% of the lower flammable limit criterion, based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the Welty Report is the basis for this letter report. The Welty Report is also a part of the trapped gas evaluation document criteria. The Welty Report contains various tank information, including: physical information, status, levels, and dry wells. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unaccounted for surface level rise. From 1973 through 1980, the Welty Report tracked Tank SX-105 transfers and reported a net cumulative change of 20.75 in. This surface level increase is from an unknown source or is unaccounted for. Duke Engineering and Services Hanford and Lockheed Martin Hanford Corporation are interested in determining the validity of unexplained surface level changes reported in the Welty Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unaccounted for surface level changes as shown in the Welty Report from 1973 through 1980. Tank SX-105 initially received waste from REDOX starting the second quarter of 1955. After June 1975, the tank primarily received processed waste (slurry) from the 242-S Evaporator/Crystallizer and transferred supernate waste to Tanks S-102 and SX-102. The Welty Report shows a cumulative change of 20.75 in. from June 1973 through December 1980

  15. Historical tank content estimate for the northwest quadrant of the Hanford 200 west area

    International Nuclear Information System (INIS)

    Brevick, C.H.; Stroup, J.L.; Funk, J.W.

    1997-01-01

    The Historical Tank Content Estimate for the Quadrant provides historical information on a tank-by-tank basis of the radioactive mixed wastes stored in the underground single-shell tanks for the Hanford 200 West Area. This report summarized historical information such as waste history, level history, temperature history, riser configuration, tank integrity, and inventory estimates on a tank-by-tank basis. Tank farm aerial photographs and interior tank montages are also provided for each tank. A description of the development of data for the document of the inventory estimates provided by Los Alamos National Laboratory are also given in this report

  16. Waste tank ventilation rates measured with a tracer gas method

    International Nuclear Information System (INIS)

    Huckaby, J.L.; Evans, J.C.; Sklarew, D.S.; Mitroshkov, A.V.

    1998-08-01

    Passive ventilation with the atmosphere is used to prevent accumulation of waste gases and vapors in the headspaces of 132 of the 177 high-level radioactive waste Tanks at the Hanford Site in Southeastern Washington State. Measurements of the passive ventilation rates are needed for the resolution of two key safety issues associated with the rates of flammable gas production and accumulation and the rates at which organic salt-nitrate salt mixtures dry out. Direct measurement of passive ventilation rates using mass flow meters is not feasible because ventilation occurs va multiple pathways to the atmosphere (i.e., via the filtered breather riser and unsealed tank risers and pits), as well as via underground connections to other tanks, junction boxes, and inactive ventilation systems. The tracer gas method discussed in this report provides a direct measurement of the rate at which gases are removed by ventilation and an indirect measurement of the ventilation rate. The tracer gas behaves as a surrogate of the waste-generated gases, but it is only diminished via ventilation, whereas the waste gases are continuously released by the waste and may be subject to depletion mechanisms other than ventilation. The fiscal year 1998 tracer studies provide new evidence that significant exchange of air occurs between tanks via the underground cascade pipes. Most of the single-shell waste tanks are connected via 7.6-cm diameter cascade pipes to one or two adjacent tanks. Tracer gas studies of the Tank U-102/U-103 system indicated that the ventilation occurring via the cascade line could be a significant fraction of the total ventilation. In this two-tank cascade, air evidently flowed from Tank U-103 to Tank U-102 for a time and then was observed to flow from Tank U-102 to Tank U-103

  17. Tank waste processing analysis: Database development, tank-by-tank processing requirements, and examples of pretreatment sequences and schedules as applied to Hanford Double-Shell Tank Supernatant Waste - FY 1993

    International Nuclear Information System (INIS)

    Colton, N.G.; Orth, R.J.; Aitken, E.A.

    1994-09-01

    This report gives the results of work conducted in FY 1993 by the Tank Waste Processing Analysis Task for the Underground Storage Tank Integrated Demonstration. The main purpose of this task, led by Pacific Northwest Laboratory, is to demonstrate a methodology to identify processing sequences, i.e., the order in which a tank should be processed. In turn, these sequences may be used to assist in the development of time-phased deployment schedules. Time-phased deployment is implementation of pretreatment technologies over a period of time as technologies are required and/or developed. The work discussed here illustrates how tank-by-tank databases and processing requirements have been used to generate processing sequences and time-phased deployment schedules. The processing sequences take into account requirements such as the amount and types of data available for the tanks, tank waste form and composition, required decontamination factors, and types of compact processing units (CPUS) required and technology availability. These sequences were developed from processing requirements for the tanks, which were determined from spreadsheet analyses. The spreadsheet analysis program was generated by this task in FY 1993. Efforts conducted for this task have focused on the processing requirements for Hanford double-shell tank (DST) supernatant wastes (pumpable liquid) because this waste type is easier to retrieve than the other types (saltcake and sludge), and more tank space would become available for future processing needs. The processing requirements were based on Class A criteria set by the U.S. Nuclear Regulatory Commission and Clean Option goals provided by Pacific Northwest Laboratory

  18. Supporting document for the historical tank content estimate for SY-tank farm

    International Nuclear Information System (INIS)

    Brevick, C.H.

    1997-01-01

    The purpose of this historical characterization document is to present the synthesized summaries of the historical records concerning the physical characteristics, radiological, and chemical composition of mixed wastes stored in underground double-shell tanks and the physical condition of these tanks. The double-shell tanks are located on the United States Department of Energy's Hanford Site, approximately 25 miles northwest or Richland, Washington. The document will be used to assist in characterizing the waste in the tanks in conjunction with the current program of sampling and analyzing the tank wastes. Los Alamos National Laboratory (LANL) developed computer models that used the historical data to attempt to characterize the wastes and to generate estimates of each tank's inventory. A historical review of the tanks may reveal anomalies or unusual contents that could be critical to characterization and post characterization activities. This document was developed by reviewing the operating plant process histories, waste transfer data, and available physical and chemical data from numerous resources. These resources were generated by numerous contractors from 1945 to the present. Waste characterization, the process of describing the character or quality of a waste, is required by Federal law (Resource Conservation and Recovery Act CRA and state law (Washington Administrative Code AC 173-303, Dangerous Waste Regulations). Characterizing the waste is necessary to determine methods to safely retrieve, transport, and/or treat the wastes

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

    International Nuclear Information System (INIS)

    FIELD, J.G.

    1999-01-01

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

  20. Fiber optic distributed chemical sensor for the real time detection of hydrocarbon fuel leaks

    Science.gov (United States)

    Mendoza, Edgar; Kempen, C.; Esterkin, Yan; Sun, Sunjian

    2015-09-01

    With the increase worldwide demand for hydrocarbon fuels and the vast development of new fuel production and delivery infrastructure installations around the world, there is a growing need for reliable hydrocarbon fuel leak detection technologies to provide safety and reduce environmental risks. Hydrocarbon leaks (gas or liquid) pose an extreme danger and need to be detected very quickly to avoid potential disasters. Gas leaks have the greatest potential for causing damage due to the explosion risk from the dispersion of gas clouds. This paper describes progress towards the development of a fast response, high sensitivity, distributed fiber optic fuel leak detection (HySense™) system based on the use of an optical fiber that uses a hydrocarbon sensitive fluorescent coating to detect the presence of fuel leaks present in close proximity along the length of the sensor fiber. The HySense™ system operates in two modes, leak detection and leak localization, and will trigger an alarm within seconds of exposure contact. The fast and accurate response of the sensor provides reliable fluid leak detection for pipelines, storage tanks, airports, pumps, and valves to detect and minimize any potential catastrophic damage.

  1. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume I

    International Nuclear Information System (INIS)

    1996-08-01

    This document, Volume 1 of the Final Environmental Impact Statement, analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

  2. Decontamination Study for Mixed Waste Storage Tanks RCRA Closure

    International Nuclear Information System (INIS)

    Leaphart, D.M.; Reed, S.R.; Rankin, W.N.

    1995-01-01

    The Savannah River Site (SRS) plans to close six underground tanks storing mixed waste under RCRA regulations. In support of this closure effort, a study was performed to determine the optimal method of decontaminating these tanks to meet the closure requirements. Items consaidered in the evaluation of the decontamination methods included effectiveness, compatibility with existing waste residues, possible cleaning solution disposal methods, and cost

  3. A petroleum contaminated soil bioremediation facility

    Energy Technology Data Exchange (ETDEWEB)

    Lombard, K.; Hazen, T.

    1994-06-01

    The amount of petroleum contaminated soil (PCS) at the Savannah River site (SRS) that has been identified, excavated and is currently in storage has increased several fold during the last few years. Several factors have contributed to this problem: (1) South Carolina Department of Health ad Environmental control (SCDHEC) lowered the sanitary landfill maximum concentration for total petroleum hydrocarbons (TPH) in the soil from 500 to 100 parts per million (ppm), (2) removal and replacement of underground storage tanks at several sites, (3) most recently SCDHEC disallowed aeration for treatment of contaminated soil, and (4) discovery of several very large contaminated areas of soil associated with leaking underground storage tanks (LUST), leaking pipes, disposal areas, and spills. Thus, SRS has an urgent need to remediate large quantities of contaminated soil that are currently stockpiled and the anticipated contaminated soils to be generated from accidental spills. As long as we utilize petroleum based compounds at the site, we will continue to generate contaminated soil that will require remediation.

  4. A petroleum contaminated soil bioremediation facility

    International Nuclear Information System (INIS)

    Lombard, K.; Hazen, T.

    1994-01-01

    The amount of petroleum contaminated soil (PCS) at the Savannah River site (SRS) that has been identified, excavated and is currently in storage has increased several fold during the last few years. Several factors have contributed to this problem: (1) South Carolina Department of Health ad Environmental control (SCDHEC) lowered the sanitary landfill maximum concentration for total petroleum hydrocarbons (TPH) in the soil from 500 to 100 parts per million (ppm), (2) removal and replacement of underground storage tanks at several sites, (3) most recently SCDHEC disallowed aeration for treatment of contaminated soil, and (4) discovery of several very large contaminated areas of soil associated with leaking underground storage tanks (LUST), leaking pipes, disposal areas, and spills. Thus, SRS has an urgent need to remediate large quantities of contaminated soil that are currently stockpiled and the anticipated contaminated soils to be generated from accidental spills. As long as we utilize petroleum based compounds at the site, we will continue to generate contaminated soil that will require remediation

  5. Contaminação de aqüífero por hidrocarbonetos: estudo de caso na Vila Tupi, Porto Velho - Rondônia Hydrocarbon contamination in groundwater: the case of Tupi Village, Porto Velho-RO

    Directory of Open Access Journals (Sweden)

    Elcimar Juarez Forte

    2007-01-01

    Full Text Available Underground storage tanks (UST are widely used in the Porto Velho area. A large number of these USTs are in bad condition due to corrosion processes causing groundwater contamination. A large number of these leaking underground fuel tanks (LUFT are in urban areas but due to the lack of water quality monitoring, they are only detected when there is a high contamination level. This study identified petroleum hydrocarbons, derived from a LUFT, by a silica gel/petroleum ether partitioning gravimetric method and by gas chromatographic analysis of samples collected in wells dug in a gas station and in houses in the aforementioned neighborhood.

  6. Streamlined approach for environmental restoration closure report for Corrective Action Unit 464: Historical underground storage tank release sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report addresses the site characterization of two historical underground storage tank petroleum hydrocarbon release sites identified by Corrective Action Site (CAS) Numbers 02-02-03 and 09-02-01. The sites are located at the Nevada Test Site in Areas 2 and 9 and are concrete bunker complexes (Bunker 2-300, and 9-300). Characterization was completed using drilling equipment to delineate the extent of petroleum hydrocarbons at release site 2-300-1 (CAS 02-02-03). Based on site observations, the low hydrocarbon concentrations detected, and the delineation of the vertical and lateral extent of subsurface hydrocarbons, an ``A through K`` evaluation was completed to support a request for an Administrative Closure of the site.

  7. Streamlined approach for environmental restoration closure report for Corrective Action Unit 464: Historical underground storage tank release sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    This report addresses the site characterization of two historical underground storage tank petroleum hydrocarbon release sites identified by Corrective Action Site (CAS) Numbers 02-02-03 and 09-02-01. The sites are located at the Nevada Test Site in Areas 2 and 9 and are concrete bunker complexes (Bunker 2-300, and 9-300). Characterization was completed using drilling equipment to delineate the extent of petroleum hydrocarbons at release site 2-300-1 (CAS 02-02-03). Based on site observations, the low hydrocarbon concentrations detected, and the delineation of the vertical and lateral extent of subsurface hydrocarbons, an ''A through K'' evaluation was completed to support a request for an Administrative Closure of the site

  8. First generation long-reach manipulator for retrieval of waste from Hanford single-shell tanks

    International Nuclear Information System (INIS)

    Gibbons, P.W.; McDaniel, L.B.

    1994-10-01

    The US Department of Energy, Richland Operations Office, has established the Tank Waste Remediation System to resolve environmental and safety issues related to underground waste-storage tanks at the Hanford Site. The Tank Waste Remediation System has identified the use of an advanced-technology, long-reach manipulator system as a low-water-addition retrieval alternative to past-practice sluicing

  9. Design assessment for Melton Valley liquid low-level waste collection and transfer system upgrade project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1994-10-01

    This project is designed for collecting liquid low level waste (LLLW) from generating points inside the Radioisotope Engineering and Development Center (Buildings 7920 and 7930) facility and transferring this waste to the Collection Tank (F-1800) in the new Monitoring and Control Station (MCS) facility. The LLLW is transferred to the MCS in a new, underground, jacketed, stainless steel piping system. The LLLW will then be transferred from Tank F-1800 through a new, underground, jacketed, stainless steel piping system that connects the existing Bethel Valley LLLW Collection System and the Evaporator Facility Service Tanks. The interface for the two systems will be at the existing Interconnecting Pipe Line (ICPL) Valve Box adjacent to the Nonradiological Wastewater Treatment Plant. The project scope consists of the following systems: (1) Building 7920 LLLW Collection System; (2) Building 7930 LLLW Collection System; (3) LLLW Underground Transfer System to MCS; (4) MCS Building (including all equipment contained therein); (5) LLLW Underground Transfer System to ICPL Valve Box; and (6) Leak detection system for jacketed piping systems (3) and (5)

  10. AT on Buried LPG Tanks Over 13 m3: An Innovative and Practical Solution

    Science.gov (United States)

    Di Fratta, Crescenzo; Ferraro, Antonio; Tscheliesnig, Peter; Lackner, Gerald; Correggia, Vincenzo; Altamura, Nicola

    In Italy, since 2005, techniques based on Acoustic Emission have been introduced for testing of underground LPG tanks up to 13 m3, according to the European standard EN 12818:2004. The testing procedure for these tanks plans to install one or more pairs of sensors inside the "dome" suited for the access to the valves and fittings of the tank, directly on the accessible metal shell. This methodology is not applicable for the underground LPG buried tanks, where it is necessary to install a larger number of AE sensors, in order to cover at 100% the whole tank shell, even at very deep positions. Already in 2004, the European standard EN 12820 (Appendix C - Informative)give the possibility to use Acoustic Emission testing of LPG underground or buried tanks with a capacity exceeding 13 m3, but no technique was specified for the application. In 2008, TÜV AUSTRIA ITALIA - BLU SOLUTIONS srl - Italian company of TÜV AUSTRIA Group - has developed a technique to get access at tank shell, where tank capacity is greater than 13 m3 and its' diameter greater than 3,5 m. This methodology was fully in comply with the provisions of the European Standard EN 12819:2010, becoming an innovative solution widely appreciated and is used in Italy since this time. Currently, large companies and petrochemical plants, at the occurrence of the tank's requalification, have engaged TÜV AUSTRIA ITALIA - BLU SOLUTIONS to install such permanent predispositions, which allow access to the tank shell - test object - with diameters from 4 to 8 m. Through this access, you can install the AE sensors needed to cover at 100% the tank surface and then to perform AE test. In an economic crisis period, this technique is proving a valid and practically applicable answer, in order to reduce inspection costs and downtime by offering a technically advanced solution (AT), increasing the safety of the involved operators, protecting natural resources and the environment.

  11. Probabilistic safety assessment for Hanford high-level waste tanks

    International Nuclear Information System (INIS)

    MacFarlane, D.R.; Stack, D.S.; Kindinger, J.P.; Deremer, R.K.

    1995-01-01

    This paper gives results from the first comprehensive level-3 probabilistic safety assessment (PSA), including consideration of external events, for the Hanford tank farm (HTF). This work was sponsored by the U.S. Department of Energy/Environmental Restoration and Waste Management Division (DOE/EM). At the HTF, there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/saltcake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is ∼60 million gal, containing ∼200 million Ci of radioactivity

  12. Assessing the accuracy of TDR-based water leak detection system

    Science.gov (United States)

    Fatemi Aghda, S. M.; GanjaliPour, K.; Nabiollahi, K.

    2018-03-01

    The use of TDR system to detect leakage locations in underground pipes has been developed in recent years. In this system, a bi-wire is installed in parallel with the underground pipes and is considered as a TDR sensor. This approach greatly covers the limitations arisen with using the traditional method of acoustic leak positioning. TDR based leak detection method is relatively accurate when the TDR sensor is in contact with water in just one point. Researchers have been working to improve the accuracy of this method in recent years. In this study, the ability of TDR method was evaluated in terms of the appearance of multi leakage points simultaneously. For this purpose, several laboratory tests were conducted. In these tests in order to simulate leakage points, the TDR sensor was put in contact with water at some points, then the number and the dimension of the simulated leakage points were gradually increased. The results showed that with the increase in the number and dimension of the leakage points, the error rate of the TDR-based water leak detection system increases. The authors tried, according to the results obtained from the laboratory tests, to develop a method to improve the accuracy of the TDR-based leak detection systems. To do that, they defined a few reference points on the TDR sensor. These points were created via increasing the distance between two conductors of TDR sensor and were easily identifiable in the TDR waveform. The tests were repeated again using the TDR sensor having reference points. In order to calculate the exact distance of the leakage point, the authors developed an equation in accordance to the reference points. A comparison between the results obtained from both tests (with and without reference points) showed that using the method and equation developed by the authors can significantly improve the accuracy of positioning the leakage points.

  13. Assessing the accuracy of TDR-based water leak detection system

    Directory of Open Access Journals (Sweden)

    S.M. Fatemi Aghda

    2018-03-01

    Full Text Available The use of TDR system to detect leakage locations in underground pipes has been developed in recent years. In this system, a bi-wire is installed in parallel with the underground pipes and is considered as a TDR sensor. This approach greatly covers the limitations arisen with using the traditional method of acoustic leak positioning. TDR based leak detection method is relatively accurate when the TDR sensor is in contact with water in just one point. Researchers have been working to improve the accuracy of this method in recent years.In this study, the ability of TDR method was evaluated in terms of the appearance of multi leakage points simultaneously. For this purpose, several laboratory tests were conducted. In these tests in order to simulate leakage points, the TDR sensor was put in contact with water at some points, then the number and the dimension of the simulated leakage points were gradually increased. The results showed that with the increase in the number and dimension of the leakage points, the error rate of the TDR-based water leak detection system increases.The authors tried, according to the results obtained from the laboratory tests, to develop a method to improve the accuracy of the TDR-based leak detection systems. To do that, they defined a few reference points on the TDR sensor. These points were created via increasing the distance between two conductors of TDR sensor and were easily identifiable in the TDR waveform. The tests were repeated again using the TDR sensor having reference points. In order to calculate the exact distance of the leakage point, the authors developed an equation in accordance to the reference points. A comparison between the results obtained from both tests (with and without reference points showed that using the method and equation developed by the authors can significantly improve the accuracy of positioning the leakage points. Keywords: Multiple leakage points, TDR, Reference points

  14. Hanford Site Tank 241-SY-101, damaged equipment removal

    International Nuclear Information System (INIS)

    Titzler, P.A.; Legare, D.E.; Barrus, H.G.

    1993-11-01

    Hanford Site Tank 241-SY-101 has a history of generating hydrogen-nitrous oxide gases. The gases are generated and trapped in the non-convective waste layer near the bottom of the 23-m- (75-ft-) diameter underground tank. Approximately every three months the pressure in the tank is relieved as the trapped gases are released through or around the surface crust into the tank dome. This process moves large amounts of liquid waste and crust material around in the tank. The moving waste displaced air lances and thermocouple assemblies (2-in. schedule-40 pipe) installed in four tank risers and permanently bent them to a maximum angle of 40 degrees. The bends were so severe that assemblies could not be removed from the tank using the originally designed hardware. Just after the tank releases the trapped gas, a 20-to-30-day work ''window'' opens

  15. F/H area high level waste tank status report

    International Nuclear Information System (INIS)

    Hayes, C.R. Jr.; Wells, M.N.

    1997-03-01

    Section IX.E.3 of the SRS Federal Facility Agreement requires the DOE to submit to EPA and SCDHEC, an annual report on the status of tanks being removed from service. Tanks that are slated for removal from service either do not meet secondary containment standards or have leak sites. The attached document is intended to meet this annual report requirement. An updated status of relevant portions of the Waste Removal Plan and Schedule is also included

  16. State Waste Discharge Permit Application: Electric resistance tomography testing

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    This permit application documentation is for a State Waste Discharge Permit issued in accordance with requirements of Washington Administrative Code 173-216. The activity being permitted is a technology test using electrical resistance tomography. The electrical resistance tomography technology was developed at Lawrence Livermore National Laboratory and has been used at other waste sites to track underground contamination plumes. The electrical resistance tomography technology measures soil electrical resistance between two electrodes. If a fluid contaminated with electrolytes is introduced into the soil, the soil resistance is expected to drop. By using an array of measurement electrodes in several boreholes, the areal extent of contamination can be estimated. At the Hanford Site, the purpose of the testing is to determine if the electrical resistance tomography technology can be used in the vicinity of large underground metal tanks without the metal tank interfering with the test. It is anticipated that the electrical resistance tomography technology will provide a method for accurately detecting leaks from the bottom of underground tanks, such as the Hanford Site single-shell tanks.

  17. State Waste Discharge Permit Application: Electric resistance tomography testing

    International Nuclear Information System (INIS)

    1994-04-01

    This permit application documentation is for a State Waste Discharge Permit issued in accordance with requirements of Washington Administrative Code 173-216. The activity being permitted is a technology test using electrical resistance tomography. The electrical resistance tomography technology was developed at Lawrence Livermore National Laboratory and has been used at other waste sites to track underground contamination plumes. The electrical resistance tomography technology measures soil electrical resistance between two electrodes. If a fluid contaminated with electrolytes is introduced into the soil, the soil resistance is expected to drop. By using an array of measurement electrodes in several boreholes, the areal extent of contamination can be estimated. At the Hanford Site, the purpose of the testing is to determine if the electrical resistance tomography technology can be used in the vicinity of large underground metal tanks without the metal tank interfering with the test. It is anticipated that the electrical resistance tomography technology will provide a method for accurately detecting leaks from the bottom of underground tanks, such as the Hanford Site single-shell tanks

  18. Role of Competitive Cation Exchange on Chromatographic Displacement of Cesium in the Vadose Zone beneath the Hanford S/SX Tank Farm

    International Nuclear Information System (INIS)

    Lichtner, Peter C.; Yabusaki, Steven B.; Pruess, Karsten; Steefel, Carl

    2004-01-01

    Migration of radionuclides under the SX-tank farm at the Hanford nuclear waste complex involves interaction of variably water saturated sediments with concentrated NaOH-NaNO 3 -NaNO 2 solutions that have leaked from the tanks. Constant K d models for describing radionuclide retardation are not valid under these conditions because of strong competition for sorption sites by abundant Na + ions, and because of dramatically changing solution compositions with time as the highly concentrated tank fluid becomes diluted as it mixes with infiltrating rainwater. A mechanistic multicomponent sorption model is required that can account for effects of competition and spatially and temporally variable solution compositions. To investigate the influence of the high ionic strength tank fluids on Cs + migration, numerical calculations are performed using the multiphase-multicomponent reactive transport code FLOTRAN. The computer model describes reactive transport in nonisothermal, variably saturated porous media including both liquid and gas phases. Pitzer activity coefficient corrections are used to describe the high ionic strength solutions. The calculations take into account multicomponent cation exchange based on measured selectivity coefficients specific to the Hanford sediments. Solution composition data obtained from Well 299-W23-19, documenting a moderately concentrated leak from the SX-115 tank, are used to calibrate the model. In addition to exchange of cations Na + , K + , Ca 2+ , and Cs + , aqueous complexing and a kinetic description of precipitation and dissolution of calcite are also included in the calculations. The fitted infiltration rate of 0.08 m yr -1 , and fitted cation exchange capacity of 0.05 mol kg -1 are consistent with measured values for the Hanford sediments. A sensitivity analysis is performed for Na + concentrations ranging from 5 to 20 m to investigate the mobility of Cs + interacting with a highly concentrated background electrolyte solution

  19. Robotic systems for the high level waste tank farm replacement project at INEL

    International Nuclear Information System (INIS)

    Berger, A.; White, D.; Thompson, B.; Christensen, M.

    1993-01-01

    Westinghouse Idaho Nuclear Company (WINCO) is specifying and designing a new high level waste tank farm at the Idaho National Engineering Laboratory (INEL). The farm consists of four underground storage tanks, which replace the existing tanks. The new facility includes provisions for remote operations. One of the planned remote operations is robotic inspection of the tank from the interior and exterior. This paper describes the process used to design the robotic system for the inspection tasks

  20. Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 2: Final report

    International Nuclear Information System (INIS)

    Peters, B.B.; Cameron, R.J.; McCormack, W.D.

    1994-08-01

    The objective of DOE's Radioactive Waste Tank Remediation Technology Focus Area is to identify and develop new technologies that will reduce the risk and/or cost of remediating DOE underground waste storage tanks and tank contents. There are, however, many more technology investment opportunities than the current budget can support. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program. The report identifies the project objectives and provides a description of the model. Development of the first ''demonstration'' version of this model and a trial application have been completed and the results are presented. This model will continue to evolve as it undergoes additional user review and testing

  1. Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 2: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Peters, B.B.; Cameron, R.J.; McCormack, W.D. [Enserch Environmental Corp., Richland, WA (United States)

    1994-08-01

    The objective of DOE`s Radioactive Waste Tank Remediation Technology Focus Area is to identify and develop new technologies that will reduce the risk and/or cost of remediating DOE underground waste storage tanks and tank contents. There are, however, many more technology investment opportunities than the current budget can support. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program. The report identifies the project objectives and provides a description of the model. Development of the first ``demonstration`` version of this model and a trial application have been completed and the results are presented. This model will continue to evolve as it undergoes additional user review and testing.

  2. Operating experience with decommissioning of underground components, USA

    International Nuclear Information System (INIS)

    2006-01-01

    In the USA there has over the years been widespread use of underground piping and tank storage systems, as well as use of other storage vaults and miscellaneous underground storage systems. In most instances these systems are associated with other operating facilities such as large nuclear facilities. There has been considerable experience over the last 60 years in the design, installation, operation and decommissioning of these radioactive waste handling and storage structures and systems. Legislation was enacted in the 1980s that required extensive upgrades to existing systems, with newly installed systems being required to meet stringent installation, operation and removal requirements. This has had an impact on the use of some of these underground systems. One major problem with many of these systems is to gauge the integrity of the systems after they have been in operation for many years and to accurately determine whether they have leaked or not. Depending on the results of these investigations, the next question is whether these systems even need to be excavated or if they can be dispositioned in place rather than expending a large amount of effort to excavate them and remove the materials in question to a disposal site for final dispositioning. In some areas this is possible while in others excavation is required. Over the years that nuclear facilities have been operational in the USA, advantage has been taken of the fact that the earth serves as a good location for emplacement of otherwise obtrusive (or even less aesthetically pleasing) structures. These structures are also still clearly able to support the useful mission they were always intended to fulfil. This arrangement also serves as a structural feature favourable to minimizing radiation exposure levels emanating from systems and components containing radioactive materials. In some cases, embedding of various components such as tanks, pits, vaults, pipes and ducting was an easy way to avoid these

  3. Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1

    International Nuclear Information System (INIS)

    Groth, B.D.

    1995-01-01

    The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements

  4. Leak detection, monitoring, and mitigation technology trade study update

    International Nuclear Information System (INIS)

    HERTZEL, J.S.

    1998-01-01

    This document is a revision and update to the initial report that describes various leak detection, monitoring, and mitigation (LDMM) technologies that can be used to support the retrieval of waste from the single-shell tanks (SST) at the Hanford Site. This revision focuses on the improvements in the technical performance of previously identified and useful technologies, and it introduces new technologies that might prove to be useful

  5. Leak detection, monitoring, and mitigation technology trade study update

    Energy Technology Data Exchange (ETDEWEB)

    HERTZEL, J.S.

    1998-11-10

    This document is a revision and update to the initial report that describes various leak detection, monitoring, and mitigation (LDMM) technologies that can be used to support the retrieval of waste from the single-shell tanks (SST) at the Hanford Site. This revision focuses on the improvements in the technical performance of previously identified and useful technologies, and it introduces new technologies that might prove to be useful.

  6. Treatment of septic tank effluents by a full-scale capillary seepage soil biofiltration system.

    Science.gov (United States)

    Fan, Chihhao; Chang, Fang-Chih; Ko, Chun-Han; Teng, Chia-Ji; Chang, Tzi-Chin; Sheu, Yiong-Shing

    2009-03-01

    The purpose of this study is to evaluate the efficiency of septic tank effluent treatment by an underground capillary seepage soil biofiltration system in a suburban area of Taipei, Taiwan. In contrast to traditional subsurface wastewater infiltration systems, capillary seepage soil biofiltration systems initially draw incoming influent upwards from the distribution pipe by capillary and siphonage actions, then spread influent throughout the soil biofiltration bed. The underground capillary seepage soil biofiltration system consists of a train of underground treatment units, including one wastewater distribution tank, two capillary seepage soil biofiltration units in series, and a discharge tank. Each capillary seepage soil biofiltration unit contains one facultative digestion tank and one set of biofiltration beds. At the flow rate of 50 m3/day, average influent concentrations of biochemical oxygen demand (BOD), suspended solid (SS), ammonia nitrogen (NH3-N), and total phosphates (TP), were 36.15 mg/L, 29.14 mg/L, 16.05 mg/L, and 1.75 mg/L, respectively. After 1.5 years of system operation, the measured influent and effluent results show that the treatment efficiencies of the soil biofiltration system for BOD, SS, NH3-N, TP, and total coliforms are 82.96%, 60.95%, 67.17%, 74.86%, and 99.99%, respectively.

  7. Historical Tank Content Estimate for the Northwest Quandrant of the Hanford 200 East Area

    Energy Technology Data Exchange (ETDEWEB)

    Brevick, C.H.; Gaddis, L.A.; Pickett, W.W.

    1994-06-01

    Historical Tank Content Estimate of the Northeast Quadrant provides historical evaluations on a tank by tank basis of the radioactive mixed wastes stored in the underground single-shell tanks of the Hanford 200 East area. This report summaries historical information such at waste history, temperature, tank integrity, inventory estimates and tank level history on a tank by tank basis. Tank Farm aerial photos and in-tank photos of each tank are provided. A brief description of instrumentation methods used for waste tank surveillance, along with the components of the data management effort, such as waste status and Transaction Record Summary, Tank Layering Model, Defined Waste Types, and Inventory Estimates to generate these tank content estimates are also given in this report.

  8. Historical Tank Content Estimate for the Northwest Quandrant of the Hanford 200 East Area

    International Nuclear Information System (INIS)

    Brevick, C.H.; Gaddis, L.A.; Pickett, W.W.

    1994-06-01

    Historical Tank Content Estimate of the Northeast Quadrant provides historical evaluations on a tank by tank basis of the radioactive mixed wastes stored in the underground single-shell tanks of the Hanford 200 East area. This report summaries historical information such at waste history, temperature, tank integrity, inventory estimates and tank level history on a tank by tank basis. Tank Farm aerial photos and in-tank photos of each tank are provided. A brief description of instrumentation methods used for waste tank surveillance, along with the components of the data management effort, such as waste status and Transaction Record Summary, Tank Layering Model, Defined Waste Types, and Inventory Estimates to generate these tank content estimates are also given in this report

  9. Hanford waste tank cone penetrometer

    International Nuclear Information System (INIS)

    Seda, R.Y.

    1995-12-01

    A new tool is being developed to characterize tank waste at the Hanford Reservation. This tool, known as the cone penetrometer, is capable of obtaining chemical and physical properties in situ. For the past 50 years, this tool has been used extensively in soil applications and now has been modified for usage in Hanford Underground Storage tanks. These modifications include development of new ''waste'' data models as well as hardware design changes to accommodate the hazardous and radioactive environment of the tanks. The modified cone penetrometer is scheduled to be deployed at Hanford by Fall 1996. At Hanford, the cone penetrometer will be used as an instrumented pipe which measures chemical and physical properties as it pushes through tank waste. Physical data, such as tank waste stratification and mechanical properties, is obtained through three sensors measuring tip pressure, sleeve friction and pore pressure. Chemical data, such as chemical speciation, is measured using a Raman spectroscopy sensor. The sensor package contains other instrumentation as well, including a tip and side temperature sensor, tank bottom detection and an inclinometer. Once the cone penetrometer has reached the bottom of the tank, a moisture probe will be inserted into the pipe. This probe is used to measure waste moisture content, water level, waste surface moisture and tank temperature. This paper discusses the development of this new measurement system. Data from the cone penetrometer will aid in the selection of sampling tools, waste tank retrieval process, and addressing various tank safety issues. This paper will explore various waste models as well as the challenges associated with tank environment

  10. Cathodic protection for the bottoms of above ground storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Mohr, John P. [Tyco Adhesives, Norwood, MA (United States)

    2004-07-01

    Impressed Current Cathodic Protection has been used for many years to protect the external bottoms of above ground storage tanks. The use of a vertical deep ground bed often treated several bare steel tank bottoms by broadcasting current over a wide area. Environmental concerns and, in some countries, government regulations, have introduced the use of dielectric secondary containment liners. The dielectric liner does not allow the protective cathodic protection current to pass and causes corrosion to continue on the newly placed tank bottom. In existing tank bottoms where inadequate protection has been provided, leaks can develop. In one method of remediation, an old bottom is covered with sand and a double bottom is welded above the leaking bottom. The new bottom is welded very close to the old bottom, thus shielding the traditional cathodic protection from protecting the new bottom. These double bottoms often employ the use of dielectric liner as well. Both the liner and the double bottom often minimize the distance from the external tank bottom. The minimized space between the liner, or double bottom, and the bottom to be protected places a challenge in providing current distribution in cathodic protection systems. This study examines the practical concerns for application of impressed current cathodic protection and the types of anode materials used in these specific applications. One unique approach for an economical treatment using a conductive polymer cathodic protection method is presented. (author)

  11. High-level waste tank modifications, installation of mobilization equipment/check out

    International Nuclear Information System (INIS)

    Schiffhauer, M.A.; Thompson, S.C.

    1992-01-01

    PUREX high-level waste (HLW) is contained at the West Valley Demonstration Project (WVDP) in an underground carbon-steel storage tank. The HLW consists of a precipitated sludge and an alkaline supernate. This report describes the system that the WVDP has developed and implemented to resuspend and wash the HLW sludge from the tank. The report discusses Sludge Mobilization and Wash System (SMWS) equipment design, installation, and testing. The storage tank required modifications to accommodate the SMWS. These modifications are discussed as well

  12. Bioremediation of diesel contamination at an underground storage tank site: a spatial analysis of the microbial community.

    Science.gov (United States)

    Andreolli, Marco; Albertarelli, Nicola; Lampis, Silvia; Brignoli, Pierlorenzo; Khoei, Nazaninalsadat Seyed; Vallini, Giovanni

    2016-01-01

    The present study reports on a real case of contamination due to the chronic leakage of diesel fuel from an underground tank at a dismissed service station. Speciation of the microbial community according to both lateral and vertical gradients from the origin of the contaminant release was analyzed by means of the PCR-DGGE technique. Moreover, the effects of a landfarming treatment on both the microbial community structure and the abatement of contamination were analyzed. The concentration of total petrol hydrocarbons (TPHs) decreased along the horizontal gradient (from 7042.2 ± 521.9 to 112.2 ± 24.3 mg kg(-1)), while increased downwards from the position of the tank (from 502.6 ± 43.7 to 4972.5 ± 275.3 mg kg(-1)). PCR-DGGE analyses and further statistical treatment of the data indicated a correlation between structure of the bacterial communities and amount of diesel fuel contamination. On the other hand, level of contamination, soil texture and depth were shown to affect the fungal community. Chloroflexi and Ascomycota were the most abundant microbes ascertained through culture-independent procedures. Landfarming promoted 91.6 % reduction of TPHs in 75 days. Furthermore, PCR-DGGE analyses evidenced that both bacterial and fungal communities of the treated soil were restored to the pristine conditions of uncontaminated topsoil. The present study demonstrated that bacterial and fungal communities were affected differently by soil factors such as level of hydrocarbon contamination as well as soil depth and texture. This report shows that a well-planned landfarming treatment can drive the restoration of the soil in terms of both abatement of the contaminants and resilience of the microbial community structure.

  13. Flammable gas tank waste level reconcilliation tank 241-SX-102

    International Nuclear Information System (INIS)

    Brevick, C.H.; Gaddie, L.A.

    1997-01-01

    Fluoro Dynel Northwest (FDNW) was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 24 1-S-1 1 1 (S-I 1 1, typical). The trapped gas evaluation document (ref 1) states that Tank SX-102 exceeds the 25% of the lower flammable limit (FL) criterion (ref 2), based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the ''Wallet Report'' is the basis for this letter report (ref 3). The Wallet Report is also a part of the trapped gas evaluation document criteria. The Wallet Report contains various tank information, including: physical information, status, levels, and dry wells, see Appendix A. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unacquainted for surface level rise. From 1973 through 1980, the Wallet Report tracked Tank S- 102 transfers and reported a net cumulative change of 19.95 in. This surface level increase is from an unknown source or is unacquainted for. Duke Engineering and Services Hanford (DASH) and Leached Martin Hanford Corporation (LMHC) are interested in determining the validity of the unexplained surface level changes reported in the 0611e Wallet Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unacquainted for surface level changes as shown in the Wallet Report from 1973 through 1980

  14. Soil structure interaction analysis for the Hanford Site 241-SY-101 double-shell waste storage tanks

    International Nuclear Information System (INIS)

    Giller, R.A.; Weiner, E.O.

    1991-09-01

    The 241-SY-101 tank is a double-shell waste storage tank buried in the 241-SY tank farm in the 200 West Area of the Hanford Site. This analysis addresses the effects of seismic soil-structure interaction on the tank structure and includes a parametric soil-structure interaction study addressing three configurations: two-dimensional soil structure, a two-dimensional structure-soil-structure, and a three-dimensional soil-structure interaction. This study was designed to determine an optimal method for addressing seismic-soil effects on underground storage tanks. The computer programs calculate seismic-soil pressures on the double-shell tank walls and and seismic acceleration response spectra in the tank. The results of this soil-structure interaction parametric study as produced by the computer programs are given in terms of seismic soil pressures and response spectra. The conclusions of this soil-structure interaction evaluation are that dynamically calculated soil pressures in the 241-SY-101 tank are significantly reduce from those using standard hand calculation methods and that seismic evaluation of underground double-shell waste storage tanks must consider soil-structure interaction effects in order to predict conservative structural response. Appendixes supporting this study are available in Volume 2 of this report

  15. Analytical study of sodium combustion phenomena under sodium leak accidents

    International Nuclear Information System (INIS)

    Kim, Byung Ho; Jeong, J. Y.; Jeong, K. C.; Kim, T. J.; Choi, J. H.

    2001-12-01

    The rise of temperature and pressure, the release of aerosol in the buildings as a result of sodium fire must be considered for the safety measures of LMR. Therefore for the safety of the LMR, it is necessary to understand the characteristics of sodium fire, resulting from the various type of leakage. ASSCOPS(Analysis of Simultaneous Sodium Combustion in Pool and Spray) is the computer code for the analysis of the thermal consequence of sodium leak and fire in LMR that has been developed by Japan Nuclear Cycle Development Institute(JNC) in Japan. In this study, a preliminary analysis of sodium leak and fire accidents in S/G building of KALIMER is made by using ASSCOPS code. Various phenomena of interest are spray and pool burning, peak pressure, temperature change, local structure temperature, aerosol behavior, drain system into smothering tank, ventilation characteristics at each cell with the safety venting system and nitrogen injection system. In this calculation, the dimension of the S/G building was chosen in accordance with the selected options of LMR name KALIMER(Korea). As a result of this study, it was shown that subsequent effect of sodium fire depended upon whether the sodium continued to leak from the pipe or not, whether the ventilation system was running, whether the inert gas injection system was provided, whether the sodium on floor was drained into the smothering tank or not, whether the building was sealed or not, etc. Specially the excessive rise of pressure into each cell was prevented by installing the pressure release plates on wall of the building

  16. Low-level tank waste simulant data base

    International Nuclear Information System (INIS)

    Lokken, R.O.

    1996-04-01

    The majority of defense wastes generated from reprocessing spent N- Reactor fuel at Hanford are stored in underground Double-shell Tanks (DST) and in older Single-Shell Tanks (SST) in the form of liquids, slurries, sludges, and salt cakes. The tank waste remediation System (TWRS) Program has the responsibility of safely managing and immobilizing these tank wastes for disposal. This report discusses three principle topics: the need for and basis for selecting target or reference LLW simulants, tanks waste analyses and simulants that have been defined, developed, and used for the GDP and activities in support of preparing and characterizing simulants for the current LLW vitrification project. The procedures and the data that were generated to characterized the LLW vitrification simulants were reported and are presented in this report. The final section of this report addresses the applicability of the data to the current program and presents recommendations for additional data needs including characterization and simulant compositional variability studies

  17. Leak detection of SF6 gas pressure vessel safety devices at BARC-TIFR Pelletron accelerator

    International Nuclear Information System (INIS)

    Ninawe, N.G.; Sharma, S.C.; Nair, J.P.; Sparrow, H.; Bolar, P.C.; Gudekar, P.V.; Mahapatra, S.; Vishwakarma, R.S.; Ramjilal; Matkar, U.V.; Gore, J.A.; Gupta, A.K.

    2015-01-01

    Pelletron accelerator is in operation since last more than 26 years. To achieve desired voltage gradient SF6 gas of about 20 tons is used to have 75-80 psig pressure in main accelerator tank. During accelerator tank maintenance gas is transferred to four storage tanks, kept in open space in the vicinity of sea. Recently refurbishment and retrofitting of four storage tanks was carried out which includes the installation of new drift space, rupture disc assembly, relief valves and manual valves along with civil and painting work. All components to be installed were tested for high pressure. Helium gas sniffer technique was used to check micro leaks for new joints for all components before installing for storage tanks. Subsequently, the tanks were tested up to 90 psig SF6 gradually in succession. No pressure drop was observed in storage tanks. This work was carried out as per recommendation of the then particle accelerator committee (PASC). (author)

  18. Operational Philosophy Concerning Manned Spacecraft Cabin Leaks

    Science.gov (United States)

    DeSimpelaere, Edward

    2011-01-01

    The last thirty years have seen the Space Shuttle as the prime United States spacecraft for manned spaceflight missions. Many lessons have been learned about spacecraft design and operation throughout these years. Over the next few decades, a large increase of manned spaceflight in the commercial sector is expected. This will result in the exposure of commercial crews and passengers to many of the same risks crews of the Space Shuttle have encountered. One of the more dire situations that can be encountered is the loss of pressure in the habitable volume of the spacecraft during on orbit operations. This is referred to as a cabin leak. This paper seeks to establish a general cabin leak response philosophy with the intent of educating future spacecraft designers and operators. After establishing a relative definition for a cabin leak, the paper covers general descriptions of detection equipment, detection methods, and general operational methods for management of a cabin leak. Subsequently, all these items are addressed from the perspective of the Space Shuttle Program, as this will be of the most value to future spacecraft due to similar operating profiles. Emphasis here is placed upon why and how these methods and philosophies have evolved to meet the Space Shuttle s needs. This includes the core ideas of: considerations of maintaining higher cabin pressures vs. lower cabin pressures, the pros and cons of a system designed to feed the leak with gas from pressurized tanks vs. using pressure suits to protect against lower cabin pressures, timeline and consumables constraints, re-entry considerations with leaks of unknown origin, and the impact the International Space Station (ISS) has had to the standard Space Shuttle cabin leak response philosophy. This last item in itself includes: procedural management differences, hardware considerations, additional capabilities due to the presence of the ISS and its resource, and ISS docking/undocking considerations with a

  19. D.F.R. liquid metal leaks - Case histories. Liquid metal leaks from No. 7 secondary and No. 3 thermal syphon circuits

    International Nuclear Information System (INIS)

    Hargreaves, K.

    1971-01-01

    During the last shift of Friday, 29th July 1966, a liquid metal leak alarm was initiated by the detector in No. 7/8 secondary heat exchanger cubicle. A check on the insulation resistance to earth of the leak detector probe was reported to show a low value (150 ohms). A visual inspection of the cubicle interior through small holes in the lower side screens gave no indication of liquid metal leakage. The leak detector was repaired and replaced. On the following day a further alarm was given by the same detector. It was again checked, and as before, found to have a low insulation resistance. On removal from the cubible it was noted that the probe was contaminated with small amounts of grey crusty deposit. A preliminary analysis of the substance indicated strong alkalinity and sodium content. At this time there was still no evidence of severe coolant leakage. Variation in readings of the expansion tank level were inconclusive over a short term but when later these were plotted over a three month period a definite trend was established. The toal fall in level of 2.6 inches at steady temperature, which is equivalent to 150 lbs. of NaK, is shown. After the discovery of deposit on the leak detector, two cubicle heaters were disconnected and removed to allow a wider view of the interior. Occasional spurts of flame in the catch tray were then noticed together with an accumulation of oxidized NaK, confirming the existence of a leak from No. 7 heat exchanger

  20. Thermal stratification in LH2 tank of cryogenic propulsion stage tested in ISRO facility

    Science.gov (United States)

    Xavier, M.; Raj, R. Edwin; Narayanan, V.

    2017-02-01

    Liquid oxygen and hydrogen are used as oxidizer and fuel respectively in cryogenic propulsion system. These liquids are stored in foam insulated tanks of cryogenic propulsion system and are pressurized using warm pressurant gas supplied for tank pressure maintenance during cryogenic engine operation. Heat leak to cryogenic propellant tank causes buoyancy driven liquid stratification resulting in formation of warm liquid stratum at liquid free surface. This warm stratum is further heated by the admission of warm pressurant gas for tank pressurization during engine operation. Since stratified layer temperature has direct bearing on the cavitation free operation of turbo pumps integrated in cryogenic engine, it is necessary to model the thermal stratification for predicting stratified layer temperature and mass of stratified liquid in tank at the end of engine operation. These inputs are required for estimating the minimum pressure to be maintained by tank pressurization system. This paper describes configuration of cryogenic stage for ground qualification test, stage hot test sequence, a thermal model and its results for a foam insulated LH2 tank subjected to heat leak and pressurization with hydrogen gas at 200 K during liquid outflow at 38 lps for engine operation. The above model considers buoyancy flow in free convection boundary layer caused by heat flux from tank wall and energy transfer from warm pressurant gas etc. to predict temperature of liquid stratum and mass of stratified liquid in tank at the end of engine operation in stage qualification tests carried out in ISRO facility.

  1. RCSLK9: reactor coolant system leak rate determination for PWRs. User's guide

    International Nuclear Information System (INIS)

    Kirkpatrick, D.C.; Woodruff, R.W.; Holland, R.A.

    1984-12-01

    RCSLK9 is a computer program that was developed to analyze the leak tightness of the primary cooling system for any pressurized water reactor. From system conditions, water levels in tanks, and certain system design parameters, RCSLK9 calculates the loss of water from the cooling system and the increase of water in the leakage collection system during an arbitrary time interval. The program determines the system leak rates and displays or prints a report of the results. For initial application of the program at a reactor, RCSLK9 creates a file of system parameters and stores it for future use. RCSLK9 is written for use on the IBM PC

  2. Model based, sensor directed remediation of underground storage tanks

    International Nuclear Information System (INIS)

    Christensen, B.; Drotning, W.; Thunborg, S.

    1991-01-01

    Sensor rich, intelligent robots which function with respect to models of their environment have significant potential to reduce the time and cost for the cleanup of hazardous waste while increasing operator safety. Sandia National Laboratories is performing experimental investigations into the application of intelligent robot control technology to the problem of removing waste stored tanks. This paper describes the experimental environment employed at Saudi with particular attention to the computing and software control environment. Intelligent system control is achieved though the integration of extensive geometric and kinematic world models with real-time sensor based control. All operator interactions with the system are validate all operator commands before execution to provide a safe operation. Sensing is used to add information to the robot system's world model and to allow sensor based sensor control during selected operations. The results of a first Critical Feature Test are reported and the potential for applying advanced intelligent control concepts to the removal of waste in storage tanks is discussed

  3. Waste salt recovery, recycle, and destruction

    International Nuclear Information System (INIS)

    Hickman, R.G.

    1992-12-01

    Starting in 1943 and continuing into the 1970s, radioactive wastes resulting from plutonium processing at Hanford were stored underground in 149 single shell tanks. Of these tanks, 66 are known or believedto be leaking, and over a period are believed to have leaked about 750,000 gal into the surrounding soil. The bulk of the aqueous solution has been removed and transferred to double shell tanks, none of which are leaking. The waste consists of 37 million gallons of salt cake and sludge. Most of the salt cake is sodium nitrate and other sodium salts. A substantial fraction of the sludge is sodium nitrate. Small amounts of the radionuclides are present in the sludge as oxides or hydroxides. In addition, some of the tanks contain organic compounds and ferrocyanide complexes, many of which have undergone radiolytic induced chemical changes during the years of storage. As part of the Hanford site remediation effort, the tank wastes must be removed, treated, and the residuals must be immobilized and disposed of in an environmentally acceptable manner. Removal methods of the waste from the tanks fall generally into three approaches: dry removal, slurry removal, and solution removed. The latter two methods are likely to result in some additional leakage to the surrounding soil, but that may be acceptable if the tank can be emptied and remediated before the leaked material permeates deeply into the soil. This effort includes three parts: salt splitting, acid separation, and destruction, with initial emphasis on salt splitting

  4. An Initial Evaluation of Characterization and Closure Options for Underground Pipelines within a Hanford Site Single-Shell Tank Farm - 13210

    Energy Technology Data Exchange (ETDEWEB)

    Badden, Janet W.; Connelly, Michael P. [Washington River Protection Services, P.O. Box 850, Richland, Washington, 99352 (United States); Seeley, Paul N. [Cenibark International, Inc., 104318 Nicole Drive, Kennewick, Washington, 99338-7596 (United States); Hendrickson, Michelle L. [Washington State Department of Ecology, 3100 Port of Benton Blvd, Richland, Washington, 99354 (United States)

    2013-07-01

    The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies

  5. An Initial Evaluation Of Characterization And Closure Options For Underground Pipelines Within A Hanford Site Single-Shell Tank Farm-13210

    International Nuclear Information System (INIS)

    Badden, Janet W.; Connelly, Michael P.; Seeley, Paul N.; Hendrickson, Michelle L.

    2013-01-01

    The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and

  6. In Shop Acceptance Test Report for the SY Farm Annulus Leak Detectors

    International Nuclear Information System (INIS)

    SMITH, S.G.

    1999-01-01

    The following test report was written for the SY tank farm annulus leak detectors. The test plan used was HNF-4546, Revision 1. The purpose of the test plan was to test the ENRAF series 854 ATG with SPU II card prior to installation. The test plan set various parameters and verifies the gauge and alarms functionality

  7. Sampling plan to support HLW tank 16

    International Nuclear Information System (INIS)

    Rodwell, P.O.; Martin, B.

    1997-01-01

    Plans are to remove the residual waste from the annulus of High-Level Waste Tank 16, located in the H-Area Tank Farm, in 1998. The interior of the tank is virtually clean. In the late 1970's, the waste was removed from the interior of the tank by several campaigns of waste removal with slurry pumps, spray washing, and oxalic acid cleaning. The annulus of the tank at one time had several thousand gallons of waste salt, which had leaked from the tank interior. Some of this salt was removed by adding water to the annulus and circulating, but much of the salt remains in the annulus. In order to confirm the source term used for fate and transport modeling, samples of the tank interior and annulus will be obtained and analyzed. If the results of the analyses indicate that the data used for the initial modeling is bounding then no changes will be made to the model. However, if the results indicate that the source term is higher than that assumed in the initial modeling, thus not bounding, additional modeling will be performed. The purpose of this Plan is to outline the approach to sampling the annulus and interior of Tank 16 as a prerequisite to salt removal in the annulus and closure of the entire tank system. The sampling and analysis of this tank system must be robust to reasonably ensure the actual tank residual is within the bounds of analysis error

  8. Leaking tankers: how much oil was spilled?

    International Nuclear Information System (INIS)

    Simecek-Beatty, D. A.; Lehr, W. J.; Lankford, J. F.

    1997-01-01

    A model to estimate leak rates from tankers has been developed for use in emergency situations when more direct oil-loss estimation methods are not available. The model includes algorithms for gravity outflow and air and water ingestion. Three laboratory tests were conducted using fresh water and canola oil to evaluate the model output. Comparison with results from the laboratory experiments indicate good correlation of model results with measured data. However, it is not yet possible in the case of very large crude carriers to answer the question 'how much oil was spilled?' Sensitivity analysis and further laboratory testing were suggested to determine the effect of factors such as: pressure vacuum relief valves that prevent cavitation in the event of tank puncture; changing outside water levels due to wave and tidal action; tank and hole dimensions; and the amount and density of the product.10 refs., 4 figs

  9. Sodium fire tests for investigating the sodium leak in Monju

    International Nuclear Information System (INIS)

    Seino, Hiroshi; Miyahara, Shinya; Miyake, Osamu; Tanabe, Hiromi

    1996-01-01

    As a part of the work for investigating the sodium leak accident which occurred in Monju on December 8, 1995, three tests, (1) sodium leak test, (2) sodium fire test-I, and (3) sodium fire test-II, were carried out at OEC/PNC. Main objectives of these tests are to confirm leak and burning behavior of sodium from the damaged thermometer, and effects of the sodium fire on integrity of the surrounding structure, etc. The main conclusions obtained from the tests are shown as below. 1) Average sodium leak rate obtained from the sodium leak test was about 50 g/sec. This was equivalent to the value estimated from level change in the sodium overflow tank in the Monju accident. 2) Observation from video cameras in the sodium fire tests revealed that in early stages of sodium leak, sodium dropped down out of the flexible tube of thermometer in drips. This dripping and burning were expanded in range as sodium splashed on the duct. 3) Though, in the sodium fire test-I, there was a decrease of about 1 mm at a thickness of the burning pan in the vicinity in just under in the leak point, there were completely no crack and failure. In the meantime, in the sodium fire test-II the six open holes were found in the floor liner. By this liner failure, the reaction between sodium and concrete might take place. At present, while the detailed evaluation on the sodium fire test-II has been mainly carried out, the investigation for clarifying the cause of the liner failure has been also carried out. (author)

  10. Arrangement for underground storage of materials of every kind

    International Nuclear Information System (INIS)

    Marek, O.; Seisenbacher, H.; Toth, L.

    1982-01-01

    Construction of a spheroidal tank, made of two sheets of concrete, used for underground storage. Space between inner and outer sheet is filled with a vibration absorbing material. The bottom of the outer sheet is made of material with lower rigidness, which allows the line of fault in cases of tectonic motions to slide off. (J.K.) [de

  11. In situ stabilization of mixed radioactive waste storage tanks and contaminated soil areas

    International Nuclear Information System (INIS)

    Matthern, G.E.; Meservey, R.H.

    1997-01-01

    Within the Department of Energy (DOE) Complex, there are a number of small (<50,000 gallons) underground Storage tanks containing mixed waste materials. The radioactive content of wastes eliminates the feasibility for hazardous waste treatment in accordance with previously prescribed Resource Conservation and Recovery Act (RCRA) technologies. As a result, DOE is funding in situ stabilization technology development for these tanks, Some of this development work has been done at the Idaho National Engineering and Environmental Laboratory (INEEL) and the initial efforts there were concentrated on the stabilization of the contents of the Test Area North (TAN) V-9 Tank. This is a 400 gallon underground tank filled with about 320 gallons of liquids and silty sediments. Sampling data indicates that approximately 50 wt% of the tank contents is aqueous-phase liquids. The vertically oriented cylindrical tank has a conical bottom and a chordal baffle that separates the tank inlet from its outlet. Access to the tank is through a six inch diameter access pipe on top of the tank. Because of the high volume, and the high concentration of aqueous-phase materials, Tank V-9 stabilization efforts have focussed on applying in situ agitation with dry feed addition to stabilize its contents. Materials selected for dry feed addition to this tank include a mixture of Aquaset IIH, and Type I/II Portland cement. This paper describes the results of proof-of-concept tests performed on full scale mockups of the Tank V-9. This proof-of-concept test were used to set operating parameters for in situ mixing, as well as evaluate how variations in Aquaset IIH/Portland cement ratio and sediment to liquid volume affected mixing of the tank

  12. Mitigated subsurface transfer line leak resulting in a surface pool

    Energy Technology Data Exchange (ETDEWEB)

    SCOTT, D.L.

    1999-02-08

    This analysis evaluates the mitigated consequences of a potential waste transfer spill from an underground pipeline. The spill forms a surface pool. One waste composite, a 67% liquid, 33% solid, from a single shell tank is evaluated. Even drain back from a very long pipeline (50,000 ft), does not pose dose consequences to the onsite or offsite individual above guideline values.

  13. Mitigated subsurface transfer line leak resulting in a surface pool

    International Nuclear Information System (INIS)

    SCOTT, D.L.

    1999-01-01

    This analysis evaluates the mitigated consequences of a potential waste transfer spill from an underground pipeline. The spill forms a surface pool. One waste composite, a 67% liquid, 33% solid, from a single shell tank is evaluated. Even drain back from a very long pipeline (50,000 ft), does not pose dose consequences to the onsite or offsite individual above guideline values

  14. Uncertainties in the measured quantities of water leaving waste Tank 241-C-106 via the ventilation system

    Energy Technology Data Exchange (ETDEWEB)

    Minteer, D.J.

    1995-01-23

    The purpose of this analysis is to estimate the uncertainty in the measured quantity of water which typically leaves Tank 241-C-106 via the ventilation system each month. Such measurements are essential for heat removal estimation and tank liquid level verification purposes. The uncertainty associated with the current, infrequent, manual method of measurement (involves various psychrometric and pressure measurements) is suspected to be unreasonably high. Thus, the possible reduction of this uncertainty using a continuous, automated method of measurement will also be estimated. There are three major conclusions as a result of this analysis: (1) the uncertainties associated with the current (infrequent, manual) method of measuring the water which typically leaves Tank 241-C-106 per month via the ventilation system are indeed quite high (80% to 120%); (2) given the current psychrometric and pressure measurement methods and any tank which loses considerable moisture through active ventilation, such as Tank 241-C-106, significant quantities of liquid can actually leak from the tank before a leak can be positively identified via liquid level measurement; (3) using improved (continuous, automated) methods of taking the psychrometric and pressure measurements, the uncertainty in the measured quantity of water leaving Tank 241-C-106 via the ventilation system can be reduced by approximately an order of magnitude.

  15. Uncertainties in the measured quantities of water leaving waste Tank 241-C-106 via the ventilation system

    International Nuclear Information System (INIS)

    Minteer, D.J.

    1995-01-01

    The purpose of this analysis is to estimate the uncertainty in the measured quantity of water which typically leaves Tank 241-C-106 via the ventilation system each month. Such measurements are essential for heat removal estimation and tank liquid level verification purposes. The uncertainty associated with the current, infrequent, manual method of measurement (involves various psychrometric and pressure measurements) is suspected to be unreasonably high. Thus, the possible reduction of this uncertainty using a continuous, automated method of measurement will also be estimated. There are three major conclusions as a result of this analysis: (1) the uncertainties associated with the current (infrequent, manual) method of measuring the water which typically leaves Tank 241-C-106 per month via the ventilation system are indeed quite high (80% to 120%); (2) given the current psychrometric and pressure measurement methods and any tank which loses considerable moisture through active ventilation, such as Tank 241-C-106, significant quantities of liquid can actually leak from the tank before a leak can be positively identified via liquid level measurement; (3) using improved (continuous, automated) methods of taking the psychrometric and pressure measurements, the uncertainty in the measured quantity of water leaving Tank 241-C-106 via the ventilation system can be reduced by approximately an order of magnitude

  16. Grout Placement and Property Evaluation for Closing Hanford High-Level Waste Tanks - Scale-Up Testing

    International Nuclear Information System (INIS)

    LANGTON, CHRISTINE

    2003-01-01

    Hanford has 149 single-shell high level waste (HLW) tanks that were constructed between 1943 and 1964. Many of these tanks have leaked or are suspected of leaking HLW into the soil above the ground water. Consequently, a major effort is ongoing to transfer the liquid portion of the waste to the 28 newer, double-shell tanks. Savannah River National Laboratory (SRNL) was tasked to develop grout formulations for the three-layer closure concept selected by CH2M HILL for closing Tank C-106. These grout formulations were also evaluated for use as fill materials in the next six tanks scheduled to be closed. The overall scope consisted of both bench-scale testing to confirm mix designs and scale-up testing to confirm placement properties. This report provides results of the scale-up testing for the three-phase tank closure strategy. It also contains information on grouts for equipment and riser filling. The three-phase fill strategy is summarized as follows: Phase I fill encapsulates and minimizes dispersion of the residual waste in the tank. This fill is referred to as the Stabilization Layer and consists of the Stabilization Grout. The Phase II fill provides structural stability to the tank system and prevents subsidence. It is referred to as the Structural Layer and consists of the Structural Grout. A final Phase III fill consists of a grout designed to provide protection against intrusion and is referred to as the Capping Layer or Capping Grout

  17. Steel corrosion in radioactive waste storage tanks

    International Nuclear Information System (INIS)

    Carranza, Ricardo M.; Giordano, Celia M.; Saenz, E.; Weier, Dennis R.

    2004-01-01

    A collaborative study is being conducted by CNEA and USDOE (Department of Energy of the United States of America) to investigate the effects of tank waste chemistry on radioactive waste storage tank corrosion. Radioactive waste is stored in underground storage tanks that contain a combination of salts, consisting primarily of sodium nitrate, sodium nitrite and sodium hydroxide. The USDOE, Office of River Protection at the Hanford Site, has identified a need to conduct a laboratory study to better understand the effects of radioactive waste chemistry on the corrosion of waste storage tanks at the Hanford Site. The USDOE science need (RL-WT079-S Double-Shell Tanks Corrosion Chemistry) called for a multi year effort to identify waste chemistries and temperatures within the double-shell tank (DST) operating limits for corrosion control and operating temperature range that may not provide the expected corrosion protection and to evaluate future operations for the conditions outside the existing corrosion database. Assessment of corrosion damage using simulated (non-radioactive) waste is being made of the double-shell tank wall carbon steel alloy. Evaluation of the influence of exposure time, and electrolyte composition and/or concentration is being also conducted. (author) [es

  18. Federal Facility Agreement plans and schedules for liquid low-level radioactive waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1992-03-01

    Although the Federal Facility Agreement (FFA) addresses the entire Oak Ridge Reservation, specific requirements are set forth for the liquid low-level radioactive waste (LLLW) storage tanks and their associated piping and equipment, tank systems, at ORNL. The stated objected of the FFA as it relates to these tank systems is to ensure that structural integrity, containment and detection of releases, and source control are maintained pending final remedial action at the site. The FFA requires that leaking LLLW tank systems be immediately removed from service. It also requires the LLLW tank systems that do not meet the design and performance requirements established for secondary containment and leak detection be either upgraded or replaced. The FFA establishes a procedural framework for implementing the environmental laws. For the LLLW tank systems, this framework requires the specified plans and schedules be submitted to EPA and TDEC for approval within 60 days, or in some cases, within 90 days, of the effective date of the agreement

  19. Tank 241-AY-102 Secondary Liner Corrosion Evaluation - 14191

    International Nuclear Information System (INIS)

    Boomer, Kayle D.; Washenfelder, Dennis J.; Johnson, Jeremy M.

    2014-01-01

    In October 2012, Washington River Protection Solutions, LLC (WRPS) determined that the primary tank of 241-AY-102 (AY-102) was leaking. A number of evaluations were performed after discovery of the leak which identified corrosion from storage of waste at the high waste temperatures as one of the major contributing factors in the failure of the tank. The propensity for corrosion of the waste on the annulus floor will be investigated to determine if it is corrosive and must be promptly removed or if it is benign and may remain in the annulus. The chemical composition of waste, the temperature and the character of the steel are important factors in assessing the propensity for corrosion. Unfortunately, the temperatures of the wastes in contact with the secondary steel liner are not known; they are estimated to range from 45 deg C to 60 deg C. It is also notable that most corrosion tests have been carried out with un-welded, stress-relieved steels, but the secondary liner in tank AY-102 was not stress-relieved. In addition, the cold weather fabrication and welding led to many problems, which required repeated softening of the metal to flatten secondary bottom during its construction. This flame treatment may have altered the microstructure of the steel

  20. Leak rate models and leak detection

    International Nuclear Information System (INIS)

    1992-01-01

    Leak detection may be carried out by a number of detection systems, but selection of the systems must be carefully adapted to the fluid state and the location of the leak in the reactor coolant system. Computer programs for the calculation of leak rates contain different models to take into account the fluid state before its entrance into the crack, and they have to be verified by experiments; agreement between experiments and calculations is generally not satisfactory for very small leak rates resulting from narrow cracks or from a closing bending moment