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Sample records for single-shell storage tanks

  1. 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

  2. Single Shell Tank (SST) Program Plan

    International Nuclear Information System (INIS)

    HAASS, C.C.

    2000-01-01

    This document provides an initial program plan for retrieval of the single-shell tank waste. Requirements, technical approach, schedule, organization, management, and cost and funding are discussed. The program plan will be refined and updated in fiscal year 2000

  3. Single Shell Tank (SST) Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    HAASS, C.C.

    2000-03-21

    This document provides an initial program plan for retrieval of the single-shell tank waste. Requirements, technical approach, schedule, organization, management, and cost and funding are discussed. The program plan will be refined and updated in fiscal year 2000.

  4. Single-Shell tank system description

    International Nuclear Information System (INIS)

    FIELD, J.G.

    2003-01-01

    The Hanford Site single-shell tank (SST) system consists of 149 underground SSTs and processing equipment designed and constructed between 1940 and 1964 to transport and store radioactive hazardous/dangerous wastes generated from irradiated nuclear fuel processing. The tanks, designed to store waste, vary in size from between 190,000 to 3,800,000 L (50,000 gal to 1,000,000 gal) and contain a variety of solid and liquid waste. The system also includes miscellaneous underground storage tanks (IMUST). In addition to the tanks, there is a large amount of ancillary equipment associated with the system and although not designed to store wastes, the ancillary equipment is contaminated through contact with the waste. Waste was routed to the tanks through a network of underground piping, with interconnections provided in concrete pits that allowed changes to the routing through instrumentation. Processing vaults used during waste handling operations, evaporators used to reduce the waste stored in the system, and other miscellaneous structures used for a variety of waste handling operations are also included in the system. The SST system was taken out of service in 1980 and no additional waste has been added to the tanks. The SSTs and ancillary equipment were designed and constructed before promulgation of Resource Conservation and Recovery Act (RCRA) in 1986. The purpose of this document is to describe the SST system for use in performing an engineering and compliance assessment in support of M-23 milestones (Ecology, et al. 2000). This system description provides estimated locations and volumes of waste within the SST system, including storage tanks, transfer systems, evaporators aid miscellaneous support facilities

  5. Initial Single-Shell Tank Retrieval System mission analysis report

    International Nuclear Information System (INIS)

    Hertzel, J.S.

    1996-03-01

    This document provides the mission analysis for the Initial Single-Shell Tank Retrieval System task, which supports the Single-Shell Tank Waste Retrieval Program in its commitment to remove waste from single-shell tanks for treatment and final closure

  6. Single-shell tank riser resistance to ground test plan

    International Nuclear Information System (INIS)

    Kiewert, L.R.

    1996-01-01

    This Test Procedure provides the general directions for conducting Single-Shell Tank Riser to Earth Measurements which will be used by engineering as a step towards providing closure for the Lightning Hazard Issue

  7. 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

  8. 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.

  9. Overview of Hanford Single Shell Tank (SST) Structural Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Rast, Richard S.; Washenfelder, Dennis J.; Johnson, Jeremy M.

    2013-11-14

    To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project (SSTIP) 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 structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford Single-Shell Tanks. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS. The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford Single-Shell Tanks has concluded that the tanks are structurally sound and meet current industry standards. Analysis of the remaining Hanford Single-Shell Tanks is scheduled for FY2014. Hanford Single-Shell Tanks are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than 1/4 inch. No such deflections have been recorded. The tanks are also subjected to visual inspection. Digital cameras record the interior surface of

  10. Single-shell tank retrieval program mission analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Stokes, W.J.

    1998-08-11

    This Mission Analysis Report was prepared to provide the foundation for the Single-Shell Tank (SST) Retrieval Program, a new program responsible for waste removal for the SSTS. The SST Retrieval Program is integrated with other Tank Waste Remediation System activities that provide the management, technical, and operations elements associated with planning and execution of SST and SST Farm retrieval and closure. This Mission Analysis Report provides the basis and strategy for developing a program plan for SST retrieval. This Mission Analysis Report responds to a US Department of Energy request for an alternative single-shell tank retrieval approach (Taylor 1997).

  11. Single-shell tank retrieval program mission analysis report

    International Nuclear Information System (INIS)

    Stokes, W.J.

    1998-01-01

    This Mission Analysis Report was prepared to provide the foundation for the Single-Shell Tank (SST) Retrieval Program, a new program responsible for waste removal for the SSTS. The SST Retrieval Program is integrated with other Tank Waste Remediation System activities that provide the management, technical, and operations elements associated with planning and execution of SST and SST Farm retrieval and closure. This Mission Analysis Report provides the basis and strategy for developing a program plan for SST retrieval. This Mission Analysis Report responds to a US Department of Energy request for an alternative single-shell tank retrieval approach (Taylor 1997)

  12. Single-shell tank interim stabilization risk analysis

    International Nuclear Information System (INIS)

    Basche, A.D.

    1998-01-01

    The purpose of the Single-Shell Tank (SST) Interim Stabilization Risk Analysis is to provide a cost and schedule risk analysis of HNF-2358, Rev. 1, Single-Shell Tank Interim Stabilization Project Plan (Project Plan) (Ross et al. 1998). The analysis compares the required cost profile by fiscal year (Section 4.2) and revised schedule completion date (Section 4.5) to the Project Plan. The analysis also evaluates the executability of the Project Plan and recommends a path forward for risk mitigation

  13. Single-shell tank interim stabilization project plan

    International Nuclear Information System (INIS)

    Ross, W.E.

    1998-01-01

    Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE's Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

  14. Single-shell tank interim stabilization project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.E.

    1998-05-11

    This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  15. Single shell tank sluicing history and failure frequency

    Energy Technology Data Exchange (ETDEWEB)

    HERTZEL, J.S.

    1998-11-10

    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.

  16. Single Shell Tank (SST) Interim Stabilization Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    VLADIMIROFF, D.T.; BOYLES, V.C.

    2000-05-22

    This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  17. Single-shell tank closure work plan. Revision A

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

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

  18. Single-shell tank closure work plan. Revision A

    International Nuclear Information System (INIS)

    1995-06-01

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

  19. Functions and requirements for single-shell tank leakage mitigation

    International Nuclear Information System (INIS)

    Cruse, J.M.

    1994-01-01

    This document provides the initial functions and requirements for the leakage mitigation mission applicable to past and potential future leakage from the Hanford Site's 149 single-shell high-level waste tanks. This mission is a part of the overall mission of the Westinghouse Hanford Company Tank Waste Remediation System division to remediate the tank waste in a safe and acceptable manner. Systems engineering principles are being applied to this effort. A Mission Analysis has been completed, this document reflects the next step in the systems engineering approach to decompose the mission into primary functions and requirements. The functions and requirements in this document apply to mitigative actions to be taken regarding below ground leaks from SST containment boundaries and the resulting soil contamination. Leakage mitigation is invoked in the TWRS Program in three fourth level functions: (1) Store Waste, (2) Retrieve Waste, and (3) Disposition Excess Facilities

  20. FLAMMABLE GAS DIFFUSION THROUGH SINGLE SHELL TANK (SST) DOMES

    Energy Technology Data Exchange (ETDEWEB)

    MEACHAM, J.E.

    2003-11-10

    This report quantified potential hydrogen diffusion through Hanford Site Single-Shell tank (SST) domes if the SSTs were hypothetically sealed airtight. Results showed that diffusion would keep headspace flammable gas concentrations below the lower flammability limit in the 241-AX and 241-SX SST. The purpose of this document is to quantify the amount of hydrogen that could diffuse through the domes of the SSTs if they were hypothetically sealed airtight. Diffusion is assumed to be the only mechanism available to reduce flammable gas concentrations. The scope of this report is limited to the 149 SSTs.

  1. Overview Of Hanford Single Shell Tank (SST) Structural Integrity - 12123

    International Nuclear Information System (INIS)

    Rast, R.S.; Rinker, M.W.; Washenfelder, D.J.; Johnson, J.B.

    2012-01-01

    To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank 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 structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford SSTs. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford SSTs is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS(reg s ign) The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford SSTs has concluded that the tanks are structurally sound and meet current industry standards. Analyses of the remaining Hanford SSTs are scheduled for FY2013. Hanford SSTs are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than 1/4 inch. No such deflections have been recorded. The tanks are also subjected to visual inspection. Digital cameras record the interior surface of the concrete tank domes, looking for cracks and

  2. OVERVIEW OF HANFORD SINGLE SHELL TANK (SST) STRUCTURAL INTEGRITY - 12123

    Energy Technology Data Exchange (ETDEWEB)

    RAST RS; RINKER MW; WASHENFELDER DJ; JOHNSON JB

    2012-01-25

    To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank 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 structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford SSTs. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford SSTs is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS{reg_sign} The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford SSTs has concluded that the tanks are structurally sound and meet current industry standards. Analyses of the remaining Hanford SSTs are scheduled for FY2013. Hanford SSTs are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than 1/4 inch. No such deflections have been recorded. The tanks are also subjected to visual inspection. Digital cameras record the interior surface of the concrete tank domes, looking for cracks and

  3. Organic carbon in Hanford single-shell tank waste

    International Nuclear Information System (INIS)

    Toth, J.J.; Willingham, C.E.; Heasler, P.G.; Whitney, P.D.

    1994-04-01

    Safety of Hanford single-shell tanks (SSTs) containing organic carbon is a concern because the carbon in the presence of oxidizers (NO 3 or NO 2 ) is combustible when sufficiently concentrated and exposed to elevated temperatures. A propagating chemical reaction could potentially occur at high temperature (above 200 C). The rapid increase in temperature and pressure within a tank might result in the release of radioactive waste constituents to the environment. The purpose of this study is to gather available laboratory information about the organic carbon waste inventories stored in the Hanford SSTs. Specifically, the major objectives of this investigation are: Review laboratory analytical data and measurements for SST composite core and supernatant samples for available organic data; Assess the correlation of organic carbon estimated utilizing the TRAC computer code compared to laboratory measurements; and From the laboratory analytical data, estimate the TOC content with confidence levels for each of the 149 SSTs

  4. Organic carbon in Hanford single-shell tank waste

    International Nuclear Information System (INIS)

    Toth, J.J.; Willingham, C.E.; Heasler, P.G.; Whitney, P.D.

    1994-07-01

    This report documents an analysis performed by Pacific Northwest Laboratory (PNL) involving the organic carbon laboratory measurement data for Hanford single-shell tanks (SSTS) obtained from a review of the laboratory analytical data. This activity was undertaken at the request of Westinghouse Hanford Company (WHC). The objective of this study is to provide a best estimate, including confidence levels, of total organic carbon (TOC) in each of the 149 SSTs at Hanford. The TOC analyte information presented in this report is useful as part of the criteria to identify SSTs for additional measurements or monitoring for the organic safety program. This report is a precursor to an investigation of TOC and moisture in Hanford SSTS, in order to provide best estimates for each together in one report. Measured laboratory data were obtained for 75 of the 149 SSTS. The data represent a thorough investigation of data from 224 tank characterization datasets, including core-sampling and process laboratory data. Liquid and solid phase TOC values were investigated by examining selected tanks with both reported TOC values in solid and liquid phases. Some relationships were noted, but there was no clustering of data or significance between the solid and liquid phases. A methodology was developed for estimating the distribution and levels of TOC in SSTs using a logarithmic scale and an analysis of variance (ANOVA) technique. The methodology grouped tanks according to waste type using the Sort On Radioactive Waste Type (SORWT) grouping method. The SORWT model categorizes Hanford SSTs into groups of tanks expected to exhibit similar characteristics based on major waste types and processing histories. The methodology makes use of laboratory data for the particular tank and information about the SORWT group of which the tank is a member. Recommendations for a simpler tank grouping strategy based on organic transfer records were made

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

    Energy Technology Data Exchange (ETDEWEB)

    Benar, C.J.

    1996-09-26

    This characterization report summarizes the available information on the historical uses, current status, and the sampling and analysis results of waste contained in underground storage tank 241-BY-104. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09. Tank 241-BY-104 is one of 12 single-shell tanks located in the BY-Tank Farm in the 200 East Area of the Hanford Site. Tank 241-BY-104 entered service in the first quarter of 1950 with a transfer of metal waste from an unknown source. Through cascading, the tank was full of metal waste by the second quarter of 1951. The waste was sluiced in the second quarter of 1954. Uranium recovery (tributyl phosphate) waste was sent from tank 241-BY-107 during the second quarter of 1955 and from tank 241-BY-110 during the third quarter of 1955. Most of this waste was sent to a crib during the fourth quarter of 1955. During the third and fourth quarters of 1956 and the second and third quarters of 1957, the tank received waste from the in-plant ferrocyanide scavenging process (PFeCN2) from tanks 241-BY-106, -107, -108, and -110. This waste type is predicted to compose the bottom layer of waste currently in the tank. The tank received PUREX cladding waste (CWP) periodically from 1961 to 1968. Ion-exchange waste from cesium recovery operations was received from tank 241-BX-104 during the second and third quarters of 1968. Tank 241-BY-104 received evaporator bottoms waste from the in-tank solidification process that was conducted in the BY-Tank Farm 0247from tanks 241 -BY- 109 and 241 -BY- 1 12 from 1970 to 1974. The upper portion of tank waste is predicted to be composed of BY saltcake. Tank 241-BY-104 was declared inactive in 1977. Waste was saltwell pumped from the tank during the third quarter of 1982 and the fourth quarter of 1985. Table ES-1 and Figure ES-1 describe tank 241-BY-104 and its status. The tank has an operating capacity of 2,869 kL and presently

  6. Tank characterization report for single shell tank 241-SX-108

    Energy Technology Data Exchange (ETDEWEB)

    Eggers, R.F., Westinghouse Hanford

    1996-07-11

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in tank 241-SX-108. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

  7. Tank characterization report for single shell tank 241-S-107

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.

    1996-09-19

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-S-107. This report supports the requirements of Tri- Party Agreement Milestone M-44-09.

  8. Preliminary tank characterization report for single-shell tank 241-SX-112: Best-basis inventory

    International Nuclear Information System (INIS)

    Kupfer, M.J.; Schulz, W.W.; Winward, R.T.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-SX-112 was performed, and a best-basis, inventory was established. This work follows the methodology that was established by the standard inventory task

  9. Preliminary tank characterization report for single-shell tank 241-BY-101: best-basis inventory

    International Nuclear Information System (INIS)

    Kupfer, M.J.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-BY-101 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  10. Preliminary tank characterization report for single-shell tank 241-c-102: best-basis inventory

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, S.L.

    1997-08-26

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-C-102 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.

  11. Preliminary tank characterization report for single-shell tank 241-TX-116: best-basis inventory

    Energy Technology Data Exchange (ETDEWEB)

    Place, D.E.

    1997-06-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-TX-116 was performed, and a bost-basis inventory was established. This work follows the methodology that was established by the standard inventory task.

  12. Preliminary tank characterization report for single-shell tank 241-TX-117: best-basis inventory

    Energy Technology Data Exchange (ETDEWEB)

    Place, D.E.

    1997-06-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-TX-117 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.

  13. Preliminary tank characterization report for single-shell tank 241-TY-101: best-basis inventory

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, S.L.

    1997-09-02

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-TY-101 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.

  14. Preliminary tank characterization report for single-shell tank 241-BX-111: best-basis inventory

    International Nuclear Information System (INIS)

    Kupfer, M.J.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-BX-111 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  15. Prelimainary tank characterization report for single-shell tank 241-TY-103 : Best-Basis inventory

    International Nuclear Information System (INIS)

    Hendrickson, D.W.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241'-TY-103 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  16. Preliminary tank characterization report for single-shell tank 241-TX-117: best-basis inventory

    International Nuclear Information System (INIS)

    Place, D.E.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-TX-117 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  17. Preliminary tank characterization report for single-shell tank 241-TX-116: best-basis inventory

    International Nuclear Information System (INIS)

    Place, D.E.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-TX-116 was performed, and a bost-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  18. Preliminary tank characterization report for single-shell tank 241-BX-102: best-basis inventory

    International Nuclear Information System (INIS)

    Kupfer, M.J.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-BX-102 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  19. Preliminary tank characterization report for single-shell tank 241-TY-101: best-basis inventory

    International Nuclear Information System (INIS)

    Lambert, S.L.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-TY-101 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  20. 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

  1. 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

    current mechanics properties. The work on the liner leak integrity has examined the leaks from 23 tanks with liner failures. Individual leak assessments are being developed for each tank to identify the leak cause and location. Also a common cause study is being performed to take the data from individual tanks to look for trends in the failure. Supporting this work is an assessment of the leak rate from tanks at both Hanford and the Savannah River Site and a new method to locate leak sites in tank liner using ionic conductivity. A separate activity is being conducted to examine the propensity for corrosion in select single shell tanks with aggressive waste layers. The work for these two main efforts will provide the basis for the phase two planning. If the margins identified aren't sufficient to ensure the integrity through the life of the mission, phase two would focus on activities to further enhance the understanding of tank integrity. Also coincident with any phase-two work would be the integrity analysis for the tanks, which would be complete in 2018. With delays in the completion of waste treatment facilities at Hanford, greater reliance on safe, continued storage of waste in the single shell tanks is increased in importance. The goal of integrity assessment would provide basis to continue SST activities till the end of the treatment mission.

  2. 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

    of current mechanics properties. The work on the liner leak integrity has examined the leaks from 23 tanks with liner failures. Individual leak assessments are being developed for each tank to identify the leak cause and location. Also a common cause study is being performed to take the data from individual tanks to look for trends in the failure. Supporting this work is an assessment of the leak rate from tanks at both Hanford and the Savannah River Site and a new method to locate leak sites in tank liner using ionic conductivity. A separate activity is being conducted to examine the propensity for corrosion in select single shell tanks with aggressive waste layers. The work for these two main efforts will provide the basis for the phase two planning. If the margins identified aren't sufficient to ensure the integrity through the life of the mission, phase two would focus on activities to further enhance the understanding of tank integrity. Also coincident with any phase-two work would be the integrity analysis for the tanks, which would be complete in 2018. With delays in the completion of waste treatment facilities at Hanford, greater reliance on safe, continued storage of waste in the single shell tanks is increased in importance. The goal of integrity assessment would provide basis to continue SST activities till the end of the treatment mission.

  3. Preliminary tank characterization report for single-shell tank 241-TX-101: best-basis inventory

    International Nuclear Information System (INIS)

    Kupfer, M.J.

    1997-01-01

    This document is a preliminary Tank Characterization Report (TCR). It only contains the current best-basis inventory (Appendix D) for single-shell tank 241-TX-101. No TCRs have been previously issued for this tank, and current core sample analyses are not available. The best-basis inventory, therefore, is based on an engineering assessment of waste type, process flowsheet data, early sample data, and/or other available information. The Standard Inventories of Chemicals and Radionuclides in Hanford Site Tank Wastes describes standard methodology used to derive the tank-by-tank best-basis inventories. This preliminary TCR will be updated using this same methodology when additional data on tank contents become available

  4. Polyethylene encapsulation of single-shell tank low-level wastes

    International Nuclear Information System (INIS)

    Kalb, P.D.

    1993-06-01

    For the past 50 years, the US Department of Energy and its predecessor agencies have stored large volumes of defense-related radioactive and mixed wastes in underground tanks. Initially, these tanks were constructed of single steel walls surrounded by reinforced concrete and are known as single-shell tanks (SSTs). Over time, the highly corrosive contents caused many of the tanks to begin to leak. As part of its effort to remediate leaking and potentially leaky tanks, DOE has established the Underground Storage Tank Integrated Demonstration (UST-ID). The overall objectives of the UST-ID include facilitating the development and demonstration of enhanced technologies that will lead to improved treatment and stabilization of underground storage tank wastes. The host site for the UST-ID is Hanford, but the program addresses potential use of these emerging technologies in remediation of tanks at five DOE facilities: Hanford, Fernald, Idaho, Oak Ridge, and Savannah River. In order to meet its objectives, the UST-ID supports technology development in six focus areas including: (1) waste characterization, (2) high- and low-level waste treatment and disposal, (3) retrieval, transfer, and storage, (4) waste separation, (5) in situ treatment and disposal, and (6) site closure. This report describes work supported by the UST-ID, conducted at Brookhaven National Laboratory, to develop and demonstrate a polyethylene waste encapsulation process for low-level radioactive and hazardous mixed wastes stored in underground tanks. The objective of Phase I is to investigate the potential impacts of residual heat and high radiation doses on key waste forms properties including mechanical integrity, strength, and leachability

  5. 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

  6. Review of technologies for the pretreatment of retrieved single-shell tank waste at Hanford

    International Nuclear Information System (INIS)

    Gerber, M.A.

    1992-08-01

    The purpose of the study reported here was to identify and evaluate innovative processes that could be used to pretreat mixed waste retrieved from the 149 single-shell tanks (SSTs) on the US Department of Energy's (DOE) Hanford site. The information was collected as part of the Single Shell Tank Waste Treatment project at Pacific Northwest Laboratory (PNL). The project is being conducted for Westinghouse Hanford Company under their SST Disposal Program

  7. Preliminary tank characterization report for single-shell tank 241-SX-111: Best-basis inventory

    International Nuclear Information System (INIS)

    Kupfer, M.J.; Schulz, W.W.; Winward, R.T.

    1997-01-01

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort,.an evaluation of available information for single-shell tank 241-SX-111 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  8. 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

  9. Single-Shell Tank (SST) Retrieval Sequence Fiscal Year 2000 Update

    International Nuclear Information System (INIS)

    GARFIELD, J.S.

    2000-01-01

    This document describes the baseline single-shell tank (SST) waste retrieval sequence for the River Protection Project (RPP) updated for Fiscal Year 2000. The SST retrieval sequence identifies the proposed retrieval order (sequence), the tank selection and prioritization rationale, and planned retrieval dates for Hanford SSTs. In addition, the tank selection criteria and reference retrieval method for this sequence are discussed

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

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.

    1997-05-23

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

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

    International Nuclear Information System (INIS)

    Simpson, B.C.

    1997-01-01

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

  12. Tank selection for Light Duty Utility Arm (LDUA) system hot testing in a single shell tank

    Energy Technology Data Exchange (ETDEWEB)

    Bhatia, P.K.

    1995-01-31

    The purpose of this report is to recommend a single shell tank in which to hot test the Light Duty Utility Arm (LDUA) for the Tank Waste Remediation System (TWRS) in Fiscal Year 1996. The LDUA is designed to utilize a 12 inch riser. During hot testing, the LDUA will deploy two end effectors (a High Resolution Stereoscopic Video Camera System and a Still/Stereo Photography System mounted on the end of the arm`s tool interface plate). In addition, three other systems (an Overview Video System, an Overview Stereo Video System, and a Topographic Mapping System) will be independently deployed and tested through 4 inch risers.

  13. Identification of single-shell tank in-tank hardware obstructions to retrieval at Hanford Site Tank Farms

    International Nuclear Information System (INIS)

    Ballou, R.A.

    1994-10-01

    Two retrieval technologies, one of which uses robot-deployed end effectors, will be demonstrated on the first single-shell tank (SST) waste to be retrieved at the Hanford Site. A significant impediment to the success of this technology in completing the Hanford retrieval mission is the presence of unique tank contents called in-tank hardware (ITH). In-tank hardware includes installed and discarded equipment and various other materials introduced into the tank. This paper identifies those items of ITH that will most influence retrieval operations in the arm-based demonstration project and in follow-on tank operations within the SST farms

  14. Preliminary design requirements document for the initial single-shell tank retrieval system

    Energy Technology Data Exchange (ETDEWEB)

    Hertzel, J.S., Westinghouse Hanford

    1996-07-24

    The scope of this Preliminary Design Requirements Document is to identify and define the functions, with associated requirements, which must be performed to demonstrate and accomplish the initial single-shell tank saltcake retrieval from selected tanks. This document sets forth functions, requirements, performance requirements and design constraints necessary to begin conceptual design for the Initial Single-shell Tank Retrieval System. System and physical interfaces between the Initial Single-shell Tank Retrieval System project and the Tank Waste Remediation are identified. The constraints, performance requirements, and transfer of information and data across a technical interface will be documented in an Interface Control Document. The design requirements provided in this document will be augmented by additional detailed design to be documented by the project.

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

    Energy Technology Data Exchange (ETDEWEB)

    Stock, Leon M.; Huckaby, James L.

    2000-10-31

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

  16. Polyethylene encapsulation of single shell tank low-level wastes

    International Nuclear Information System (INIS)

    Kalb, P.D.; Fuhrmann, M.; Colombo, P.

    1993-01-01

    Polyethylene encapsulation is being explored for potential use in treating nitrate salts and sludges at US Department of Energy (US DOE) underground storage tank facilities. Some of these wastes contain high concentrations of fission products and are expected to maintain equilibrium temperatures of 50--70 degrees C for many years. The potential effects of elevated temperature and high radiation conditions on key waste form properties (e.g., mechanical integrity, leachability) are examined. After 6 months of thermal conditioning, waste form tests specimens show no degradation in mechanical integrity. Leaching at elevated temperature resulted in a small increase in leach rate (a factor of less than two), while diffusion remained the dominant mechanism of release. Full-scale polyethylene waste forms containing 50--70 wt % nitrate salt can be expected to leach a total of 5--17% of the original contaminant source term after 300 years of leaching under worst-case conditions (fully saturated at 70 degrees C)

  17. Best-basis estimates of solubility of selected radionuclides in sludges in Hanford single-shell tanks

    International Nuclear Information System (INIS)

    HARMSEN, R.W.

    1999-01-01

    The Hanford Defined Waste (HDW) model (Rev. 4) (Agnew et al. 1997) projects inventories (as of January 1, 1994) of 46 radionuclides in the Hanford Site underground waste storage tanks. To model the distribution of the 46 radionuclides among the 177 tanks, it was necessary for Agnew et al. to estimate the solubility of each radionuclide in the various waste types originally added to the single-shell tanks. Previous editions of the HDW model used single-point solubility estimates. The work described in this report was undertaken to provide more accurate estimates of the solubility of all 46 radionuclides in the various wastes

  18. Best-basis estimates of solubility of selected radionuclides in sludges in Hanford single-shell tanks

    Energy Technology Data Exchange (ETDEWEB)

    HARMSEN, R.W.

    1999-02-24

    The Hanford Defined Waste (HDW) model (Rev. 4) (Agnew et al. 1997) projects inventories (as of January 1, 1994) of 46 radionuclides in the Hanford Site underground waste storage tanks. To model the distribution of the 46 radionuclides among the 177 tanks, it was necessary for Agnew et al. to estimate the solubility of each radionuclide in the various waste types originally added to the single-shell tanks. Previous editions of the HDW model used single-point solubility estimates. The work described in this report was undertaken to provide more accurate estimates of the solubility of all 46 radionuclides in the various wastes.

  19. Contaminant Release from Residual Waste in Single Shell Tanks at the Hanford Site, Washington, USA - 9276

    International Nuclear Information System (INIS)

    Cantrell, Kirk J.; Krupka, Kenneth M.; Deutsch, William J.; Lindberg, Michael J.

    2009-01-01

    Determinations of elemental and solid-phase compositions, and contaminant release studies have been applied in an ongoing study of residual tank wastes (i.e., waste remaining after final retrieval operations) from five of 149 underground single-shell storage tanks (241-C-103, 241-C-106, 241-C-202, 241-C-203, and 241-S-112) at the U.S. Department of Energy's Hanford Site in Washington State. This work is being conducted to support performance assessments that will be required to evaluate long-term health and safety risks associated with tank site closure. The results of studies completed to date show significant variability in the compositions, solid phase properties, and contaminant release characteristics from these residual tank wastes. This variability is the result of differences in waste chemistry/composition of wastes produced from several different spent fuel reprocessing schemes, subsequent waste reprocessing to remove certain target constituents, tank farm operations that concentrated wastes and mixed wastes between tanks, and differences in retrieval processes used to remove the wastes from the tanks. Release models were developed based upon results of chemical characterization of the bulk residual waste, solid-phase characterization (see companion paper 9277 by Krupka et al.), leaching and extraction experiments, and geochemical modeling. In most cases empirical release models were required to describe contaminant release from these wastes. Release of contaminants from residual waste was frequently found to be controlled by the solubility of phases that could not be identified and/or for which thermodynamic data and/or dissolution rates have not been measured. For example, significant fractions of Tc-99, I-129, and Cr appear to be coprecipitated at trace concentrations in metal oxide phases that could not be identified unambiguously. In the case of U release from tank 241-C-103 residual waste, geochemical calculations indicated that leachate

  20. Test procedures and instructions for single shell tank saltcake cesium removal with crystalline silicotitanate

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, J.B.

    1997-01-07

    This document provides specific test procedures and instructions to implement the test plan for the preparation and conduct of a cesium removal test, using Hanford Single Shell Tank Saltcake from tanks 24 t -BY- I 10, 24 1 -U- 108, 24 1 -U- 109, 24 1 -A- I 0 1, and 24 t - S-102, in a bench-scale column. The cesium sorbent to be tested is crystalline siticotitanate. The test plan for which this provides instructions is WHC-SD-RE-TP-024, Hanford Single Shell Tank Saltcake Cesium Removal Test Plan.

  1. Evaluation of Hanford Single-Shell Waste Tanks Suspected of Water Intrusion

    International Nuclear Information System (INIS)

    Feero, Amie J.; Washenfelder, Dennis J.; Johnson, Jeremy M.; Schofield, John S.

    2013-01-01

    Intrusions evaluations for twelve single-shell tanks were completed in 2013. The evaluations consisted of remote visual inspections, data analysis, and calculations of estimated intrusion rates. The observation of an intrusion or the preponderance of evidence confirmed that six of the twelve tanks evaluated had intrusions. These tanks were tanks 241-A-103, BX-101, BX-103, BX-110, BY-102, and SX-106

  2. Geology Data Package for the Single-Shell Tank Waste Management Areas at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Reidel, Steve P.; Chamness, Mickie A.

    2007-01-01

    This data package discusses the geology of the single-shell tank (SST) farms and the geologic history of the area. The focus of this report is to provide the most recent geologic information available for the SST farms. This report builds upon previous reports on the tank farm geology and Integrated Disposal Facility geology with information available after those reports were published.

  3. Ventilation system consequence calculations to support salt well pumping single-shell tank 241-A-101

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, G.W.

    1997-05-07

    This document presents the radiological dose and toxicological exposure calculations for an accident scenario involved with the ventilation system used to support salt well pumping single-shell tank 241-A-101. This tank has been listed on the Hydrogen Watch List.

  4. Ventilation system consequence calculations to support salt well pumping single-shell tank 241-A-101

    International Nuclear Information System (INIS)

    Ryan, G.W.

    1997-01-01

    This document presents the radiological dose and toxicological exposure calculations for an accident scenario involved with the ventilation system used to support salt well pumping single-shell tank 241-A-101. This tank has been listed on the Hydrogen Watch List

  5. Engineering task plan for determining breathing rates in single shell tanks using tracer gas

    International Nuclear Information System (INIS)

    Andersen, J.A.

    1997-01-01

    The testing of single shell tanks to determine breathing rates. Inert tracer gases helium, and sulfur hexafluoride will be injected into the tanks AX-103, BY-105, C-107 and U-103. Periodic samples will be taken over a three month interval to determine actual headspace breathing rates

  6. Tank characterization report for single-shell tank 241-T-104

    International Nuclear Information System (INIS)

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

    1994-01-01

    In August 1992, Single-Shell Tank 241-T-104 was sampled to determine proper handling of the waste, to address corrosivity and compatibility issues, and to comply with requirements of the Washington Administrative Code (Ecology, 1991). This Tank Characterization Report presents an overview of that tank sampling and analysis effort, and contains observations regarding waste characteristics. It also addresses expected concentration and bulk inventory data for the waste contents based on this latest sampling data and background tank information. The purpose of this report is to describe and characterize the waste in Single-Shall Tank 241-T-104 (hereafter, Tank 241-T-104) based on information given from various sources. This report summarizes the available information regarding the waste in Tank 241-T-104, and using the historical information to place the analytical data in context, arranges this information in a useful format for making management and technical decisions concerning this waste tank. In addition, conclusions and recommendations are given based on safety issues and further characterization needs

  7. Tank characterization report for single-shell tank 241-U-103

    Energy Technology Data Exchange (ETDEWEB)

    SASAKI, L.M.

    1999-02-24

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-U-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-U-103 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with Waste Information Requirements Documents developed for 1998.''

  8. Tank Characterization report for single-shell tank 241-SX-103

    International Nuclear Information System (INIS)

    WILMARTH, S.R.

    1999-01-01

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-103 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for fiscal year 1999'' (Adams et al. 1998)

  9. Tank characterization report for single-shell tank 241-SX-115

    Energy Technology Data Exchange (ETDEWEB)

    HULSE, N.L.

    1999-05-13

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-SX-115. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-115 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for FY 1999'' (Adams et al. 1998).

  10. Tank characterization report for single-shell tank 241-T-105

    Energy Technology Data Exchange (ETDEWEB)

    Field, J.G.

    1998-06-18

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-105. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-105 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ``issue characterization deliverables consistent with the waste information requirements documents developed for 1998``.

  11. Tank characterization report for single-shell tank 241-TX-104

    International Nuclear Information System (INIS)

    FIELD, J.G.

    1999-01-01

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-TX-104. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-TX-104 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for FY 1999'' (Adams et al. 1998)

  12. Tank characterization report for single-shell tank 241-T-105

    International Nuclear Information System (INIS)

    Field, J.G.

    1998-01-01

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-105. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-105 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ''issue characterization deliverables consistent with the waste information requirements documents developed for 1998''

  13. Fifth Single-Shell Tank Integrity Project Expert Panel Meeting August 28-29, 2014

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Todd M. [Washington River Protection Solutions, LLC, Richland, WA (United States; Gunter, Jason R. [Washington River Protection Solutions, LLC, Richland, WA (United States); Boomer, Kayle D. [Washington River Protection Solutions, LLC, Richland, WA (United States)

    2015-01-07

    On August 28th and 29th, 2014 the Single-Shell Tank Integrity Project (SSTIP) Expert Panel (Panel) convened in Richland, Washington. This was the Panel’s first meeting since 2011 and, as a result, was focused primarily on updating the Panel on progress in response to the past recommendations (Single-Shell Tank Integrity Expert Panel Report, RPP-RPT-45921, Rev 0, May 2010). This letter documents the Panel’s discussions and feedback on Phase I activities and results.

  14. Developing a scarifier to retrieve radioactive waste from Hanford single-shell tanks

    International Nuclear Information System (INIS)

    Bamberger, J.A.; Steele, D.E.

    1993-08-01

    Radioactive waste is stored in 149 3,785 m 3 (million gal) single-shell tanks on the US Department of Energy's Hanford Reservation in eastern Washington. To minimize leakage as the tanks age, the free liquid has been pumped out, leaving concentrated solidified salt cake and sludge deposits. Now methods to dislodge and remove this waste are being developed so that the waste can be retrieved and processed for permanent storage. This paper presents research and development on ultrahigh-pressure water-jet technology to fracture and dislodge the wastes in these tanks. A water-based prototype scarifier with an integral conveyance system is being developed, and its performance demonstrated in a coupled analytical and experimental investigation. This paper describes experimental objectives and approach and results of the single jet experiments. Previous testing indicates that the method can be readily applied to salt cake waste forms; retrieval and conveyance of sludge and viscous fluid waste forms may present additional challenges

  15. Regulatory compliance analysis for the closure of single-shell tanks

    International Nuclear Information System (INIS)

    Smith, E.H.; Boomer, K.D.; Letourneau, M.; Oakes, L.; Lorang, R.

    1991-08-01

    This document provides a regulatory compliance analysis of the baseline environmental protection requirements for the closure of single-shell tanks. In preparing this document, the Westinghouse Hanford Company has analyzed the regulatory pathways and decisions points that have been identified to data through systems engineering and related studies as they relate to environmental protection. This regulatory compliance analysis has resulted in several conclusions that will aid the US Department of Energy in managing the single-shell tank waste and in developing strategies for the closure of these tanks. These conclusions include likely outcomes of current strategies, regulatory rulings that are required for future actions, variances and exemptions to be pursued, where appropriate, and potential rulings that may affect systems engineering and other portions of the single-shell tank closure effort. The conclusions and recommendations presented here are based on analysis of current regulations, regulatory exemptions and variances, and federal facility agreements. Because the remediation of the single-shell tanks will span 30 years, regulations that have yet to be promulgated and future interpretations of existing laws and regulations may impact the recommendations and conclusions presented here. 50 refs., 22 figs

  16. Tank characterization report for single-shell tank 241-C-104

    Energy Technology Data Exchange (ETDEWEB)

    Baldwin, J.H.

    1997-05-21

    A major function of the Tank Waste Remediation System is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-C-104. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-C-104 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-10.

  17. Tank characterization report for single-shell tank 241-S-111

    International Nuclear Information System (INIS)

    Conner, J.M.

    1997-01-01

    One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-S-111. The objectives of this report are: (1) to use characterization data to address technical issues associated with tank 241-S-111 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report also supports the requirements of Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-10

  18. Characterization of Direct Push Vadose Zone Sediments from the 241-U Single-Shell Tank Farm

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Christopher F.; Valenta, Michelle M.; Serne, R. Jeffrey; Bjornstad, Bruce N.; Lanigan, David C.; Iovin, Cristian; Clayton, Ray E.; Geiszler, Keith N.; Clayton, Eric T.; Kutnyakov, Igor V.; Baum, Steven R.; Lindberg, Michael J.; Orr, Robert D.

    2007-12-20

    The overall goals of the Tank Farm Vadose Zone Project, led by CH2M HILL Hanford Group, Inc., are 1) to define risks from past and future single-shell tank farm activities, 2) to identify and evaluate the efficacy of interim measures, and 3) to aid, via collection of geochemical information and data, the future decisions that must be made by the U.S. Department of Energy (DOE) regarding the near-term operations, future waste retrieval, and final closure activities for the single-shell tank Waste Management Areas (WMAs). For a more complete discussion of the goals of the Tank Farm Vadose Zone Project, see the overall work plan, Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for the Single-Shell Tank Waste Management Areas (DOE 1999). Specific details on the rationale for activities performed at WMA U are found in Crumpler (2003). To meet these goals, CH2M HILL Hanford Group, Inc., asked scientists from Pacific Northwest National Laboratory (PNNL) to perform detailed analyses of vadose zone sediment collected within the U Single-Shell Tank Farm. Specifically, this report contains all the geochemical and selected physical characterization data collected on vadose zone sediment recovered from ten direct push characterization holes emplaced to investigate vadose zone contamination associated with potential leaks within the 241-U Single-Shell Tank Farm. Specific tanks targeted during this characterization campaign included tanks 241-U-104/241-U-105, 241-U-110, and 241-U-112. Additionally, this report compiles data from direct push samples collected north of tank 241-U-201, as well as sediment collected from the background borehole (C3393). After evaluating all the characterization and analytical data, there is no question that the vadose zone in the vicinity of tanks 241-U-104 and 241-U-105 has been contaminated by tank-related waste. This observation is not new, as gamma logging of drywells in the area has identified uranium contamination at the

  19. Engineering report single-shell tank farms interim measures to limit infiltration through the vadose zone

    Energy Technology Data Exchange (ETDEWEB)

    HAASS, C.C.

    1999-10-14

    Identifies, evaluates and recommends interim measures for reducing or eliminating water sources and preferential pathways within the vadose zone of the single-shell tank farms. Features studied: surface water infiltration and leaking water lines that provide recharge moisture, and wells that could provide pathways for contaminant migration. An extensive data base, maps, recommended mitigations, and rough order of magnitude costs are included.

  20. Tank characterization report for single-shell tank 241-U-106

    Energy Technology Data Exchange (ETDEWEB)

    Brown, T.M.

    1997-04-15

    One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-U-106. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-U-106 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 of this report summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations regarding safety status and additional sampling. The appendixes contain supporting data and information. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ikology et al. 1996), Milestone M-44-10.

  1. Tank characterization report for single-shell tank 241-U-106

    International Nuclear Information System (INIS)

    Brown, T.M.

    1997-01-01

    One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-U-106. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-U-106 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 of this report summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations regarding safety status and additional sampling. The appendixes contain supporting data and information. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ikology et al. 1996), Milestone M-44-10

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

    International Nuclear Information System (INIS)

    Jo, J.

    1997-01-01

    One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-S-104. The objectives of this report are: (1) to use characterization data in response to technical issues associated with 241-S- 104 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendixes. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-05

  3. FRACTIONAL CRYSTALLIZATION OF HANFORD SINGLE-SHELL TANK WASTES. A MODELING APPROACH

    International Nuclear Information System (INIS)

    HAMILTON, D.W.

    2006-01-01

    The Hanford site has 149 underground single-shell tanks (SST) storing mostly soluble, multi-salt, mixed wastes resulting from Cold War era weapons material production. These wastes must be retrieved and the salts immobilized before the tanks can be closed to comply with an overall site closure consent order entered into by the U.S. Department of Energy (DOE), the Environmental Protection Agency, and Washington State. Water will be used to retrieve the wastes and the resulting solution will be pumped to the proposed treatment process where a high curie (primarily 137 Cs) waste fraction will be separated from the other waste constituents. The separated waste streams will then be vitrified to allow for safe storage as an immobilized high level waste, or low level waste, borosilicate glass. Fractional crystallization, a common unit operation for production of industrial chemicals and pharmaceuticals, was proposed as the method to separate the salt wastes; it works by evaporating excess water until the solubilities of various species in the solution are exceeded (the solubility of a particular species depends on its concentration, temperature of the solution, and the presence of other ionic species in the solution). By establishing the proper conditions, selected pure salts can be crystallized and separated from the radioactive liquid phase

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

    International Nuclear Information System (INIS)

    Raphael, G.F.

    1994-09-01

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

  5. Gas retention and release behavior in Hanford single-shell waste tanks

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, C.W.; Brewster, M.E.; Gauglitz, P.A.; Mahoney, L.A.; Meyer, P.A.; Recknagle, K.P.; Reid, H.C.

    1996-12-01

    This report describes the current understanding of flammable gas retention and release in Hanford single-shell waste tanks based on theory, experimental results, and observations of tank behavior. The single-shell tanks likely to pose a flammable gas hazard are listed and described, and photographs of core extrusions and the waste surface are included. The credible mechanisms for significant flammable gas releases are described, and release volumes and rates are quantified as much as possible. The only mechanism demonstrably capable of producing large ({approximately}100 m{sup 3}) spontaneous gas releases is the buoyant displacement, which occurs only in tanks with a relatively deep layer of supernatant liquid. Only the double-shell tanks currently satisfy this condition. All release mechanisms believed plausible in single-shell tanks have been investigated, and none have the potential for large spontaneous gas releases. Only small spontaneous gas releases of several cubic meters are likely by these mechanisms. The reasons several other postulated gas release mechanisms are implausible or incredible are also given.

  6. Gas retention and release behavior in Hanford single-shell waste tanks

    International Nuclear Information System (INIS)

    Stewart, C.W.; Brewster, M.E.; Gauglitz, P.A.; Mahoney, L.A.; Meyer, P.A.; Recknagle, K.P.; Reid, H.C.

    1996-12-01

    This report describes the current understanding of flammable gas retention and release in Hanford single-shell waste tanks based on theory, experimental results, and observations of tank behavior. The single-shell tanks likely to pose a flammable gas hazard are listed and described, and photographs of core extrusions and the waste surface are included. The credible mechanisms for significant flammable gas releases are described, and release volumes and rates are quantified as much as possible. The only mechanism demonstrably capable of producing large (∼100 m 3 ) spontaneous gas releases is the buoyant displacement, which occurs only in tanks with a relatively deep layer of supernatant liquid. Only the double-shell tanks currently satisfy this condition. All release mechanisms believed plausible in single-shell tanks have been investigated, and none have the potential for large spontaneous gas releases. Only small spontaneous gas releases of several cubic meters are likely by these mechanisms. The reasons several other postulated gas release mechanisms are implausible or incredible are also given

  7. Summary of Group Development and Testing for Single Shell Tank Closure at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Harbour, John, R.

    2005-04-28

    This report is a summary of the bench-scale and large scale experimental studies performed by Savannah River National Laboratory for CH2M HILL to develop grout design mixes for possible use in producing fill materials as a part of Tank Closure of the Single-Shell Tanks at Hanford. The grout development data provided in this report demonstrates that these design mixes will produce fill materials that are ready for use in Hanford single shell tank closure. The purpose of this report is to assess the ability of the proposed grout specifications to meet the current requirements for successful single shell tank closure which will include the contracting of services for construction and operation of a grout batch plant. The research and field experience gained by SRNL in the closure of Tanks 17F and 20F at the Savannah River Site was leveraged into the grout development efforts for Hanford. It is concluded that the three Hanford grout design mixes provide fill materials that meet the current requirements for successful placement. This conclusion is based on the completion of recommended testing using Hanford area materials by the operators of the grout batch plant. This report summarizes the regulatory drivers and the requirements for grout mixes as tank fill material. It is these requirements for both fresh and cured grout properties that drove the development of the grout formulations for the stabilization, structural and capping layers.

  8. Tank characterization report for single-shell tank 241-C-110. Revision 1

    International Nuclear Information System (INIS)

    Benar, C.J.

    1997-01-01

    One of the major functions of the Tank Waste Remediation System (IWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-C-110. The objectives of this report are to use characterization data in response to technical issues associated with 241-C-110 waste and to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Supporting data and information are contained in the appendixes. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order milestone M-44-05. Characterization information presented in this report originated from sample analyses and known historical sources. While only the results from recent sample events will be used to fulfill the requirements of the data quality objectives (DQOs), other information can be used to support or question conclusions derived from these results. Historical information for tank 241-C-110 are provided included surveillance information, records pertaining to waste transfers and tank operations, and 1124 expected tank contents derived from a process knowledge model. The sampling events are listed, as well as sample data obtained before 1989. The results of the 1992 sampling events are also reported in the data package. The statistical analysis and numerical manipulation of data used in issue resolution are reported in Appendix C. Appendix D contains the evaluation to establish the best basis for the inventory estimate and the statistical analysis performed for this evaluation. A bibliography that resulted from an in-depth literature search of all known information sources applicable to tank 241-C-110 and its respective waste types is contained in Appendix E

  9. Progress of the Enhanced Hanford Single Shell Tank (SST) Integrity Project

    Energy Technology Data Exchange (ETDEWEB)

    Venetz, Theodore J. [Washington River Protection Solutions, Richland, WA (United States); Washenfelder, Dennis J. [Washington River Protection Solutions, Richland, WA (United States); Boomer, Kayle D. [Washington River Protection Solutions, Richland, WA (United States); Johnson, Jeremy M. [USDOE Office of River Protection, Richland, WA (United States); Castleberry, Jim L. [Washington River Protection Solutions, Richland, WA (United States)

    2015-01-07

    To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project (SSTIP) 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. In late 2010, 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.

  10. FRACTIONAL CRYSTALLIZATION OF HANFORD SINGLE SHELL TANK (SST) WASTES FROM CONCEPT TO PILOT PLANT

    Energy Technology Data Exchange (ETDEWEB)

    GENIESSE, D.J.; NELSON, E.A.; HAMILTON, D.W.; MAJORS, J.H.; NORDAHL, T.K.

    2006-12-08

    The Hanford site has 149 underground single-shell tanks (SST) storing mostly soluble, multi-salt mixed wastes resulting from Cold War era weapons material production. These wastes must be retrieved and the salts immobilized before the tanks can be closed to comply with an overall site-closure consent order entered into by the US Department of Energy, the Environmental Protection Agency, and the State of Washington. Water will be used to retrieve the wastes and the resulting solution will be pumped to a proposed pretreatment process where a high-curie (primarily {sup 137}Cs) waste fraction will be separated from the other waste constituents. The separated waste streams will then be vitrified to allow for safe storage as an immobilized high-level waste, or low-level waste, borosilicate glass. Fractional crystallization, a common unit operation for production of industrial chemicals and pharmaceuticals, was proposed as the method to separate the salt wastes; it works by evaporating excess water until the solubilities of various species in the solution are exceeded (the solubility of a particular species depends on its concentration, temperature of the solution, and the presence of other ionic species in the solution). By establishing the proper conditions, selected pure salts can be crystallized and separated from the radioactive liquid phase. The aforementioned parameters, along with evaporation rate, proper agitation, and residence time, determine nucleation and growth kinetics and the resulting habit and size distribution of the product crystals. These crystals properties are important considerations for designing the crystallizer and solid/liquid separation equipment. A structured program was developed to (a) demonstrate that fractional crystallization could be used to pre-treat Hanford tank wastes and (b) provide data to develop a pilot plant design.

  11. FRACTIONAL CRYSTALLIZATION OF HANFORD SINGLE-SHELL TANK WASTES FROM CONCEPT TO PILOT PLANT

    International Nuclear Information System (INIS)

    GENIESSE, D.J.; NELSON, E.A.; HAMILTON, D.W.; MAJORS, J.H.; NORDAHL, T.K.

    2006-01-01

    The Hanford site has 149 underground single-shell tanks (SST) storing mostly soluble, multi-salt mixed wastes resulting from Cold War era weapons material production. These wastes must be retrieved and the salts immobilized before the tanks can be closed to comply with an overall site-closure consent order entered into by the US Department of Energy, the Environmental Protection Agency, and the State of Washington. Water will be used to retrieve the wastes and the resulting solution will be pumped to a proposed pretreatment process where a high-curie (primarily 137 Cs) waste fraction will be separated from the other waste constituents. The separated waste streams will then be vitrified to allow for safe storage as an immobilized high-level waste, or low-level waste, borosilicate glass. Fractional crystallization, a common unit operation for production of industrial chemicals and pharmaceuticals, was proposed as the method to separate the salt wastes; it works by evaporating excess water until the solubilities of various species in the solution are exceeded (the solubility of a particular species depends on its concentration, temperature of the solution, and the presence of other ionic species in the solution). By establishing the proper conditions, selected pure salts can be crystallized and separated from the radioactive liquid phase. The aforementioned parameters, along with evaporation rate, proper agitation, and residence time, determine nucleation and growth kinetics and the resulting habit and size distribution of the product crystals. These crystals properties are important considerations for designing the crystallizer and solid/liquid separation equipment. A structured program was developed to (a) demonstrate that fractional crystallization could be used to pre-treat Hanford tank wastes and (b) provide data to develop a pilot plant design

  12. Tank characterization report for single-shell tank 241-T-102

    International Nuclear Information System (INIS)

    Baldwin, J.H.

    1997-01-01

    A major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-T-102. The objectives of this report are to use characterization data in response to technical issues associated with tank 241-T-102 waste; and to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendixes. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order milestone M-44-05. Characterization information presented in this report originated from sample analyses and known historical sources. The most recent core sampling of tank 241-T-102 (March 1993) predated the existence of data quality objectives (DQOs). An assessment of the technical issues from the currently applicable DQOs was made using data from the 1993 push mode core sampling event, a July 1994 grab sampling event, and a May 1996 vapor flammability measurement. Historical information for tank 241-T-102, provided in Appendix A, includes surveillance information, records pertaining to waste transfers and tank operations, and expected tank contents derived from a process knowledge model. Appendix B contains further sampling and analysis data from the March 1993 push mode core sampling event and data from the grab sampling event in August 1994 and May 1996 vapor flammability measurement. Of the two push mode cores taken in March of 1993, cores 55

  13. Analysis of organic carbon and moisture in Hanford single-shell tank waste

    Energy Technology Data Exchange (ETDEWEB)

    Toth, J.J.; Heasler, P.G.; Lerchen, M.E.; Hill, J.G.; Whitney, P.D.

    1995-05-01

    This report documents a revised analysis performed by Pacific Northwest Laboratory involving the organic carbon laboratory measurement data for Hanford single-shell tanks (SSTs) obtained from a review of the laboratory analytical data. This activity has as its objective to provide a best-estimate, including confidence levels, of total organic carbon (TOC) and moisture in each of the 149 SSTs at Hanford. The TOC and moisture information presented in this report is useful as part of the criteria to identify SSTs for additional measurements, or monitoring for the Organic Safety Program. In April 1994, an initial study of the organic carbon in Hanford single-shell tanks was completed at PNL. That study reflected the estimates of TOC based on tank characterizations datasets that were available at the time. Also in that study, estimation of dry basis TOC was based on generalized assumptions pertaining to the moisture of the tank wastes. The new information pertaining to tank moisture and TOC data that has become available from the current study influences the best estimates of TOC in each of the SSTs. This investigation of tank TOC and moisture has resulted in improved estimates based on waste phase: saltcake, sludge, or liquid. This report details the assumptions and methodologies used to develop the estimates of TOC and moisture in each of the 149 SSTs at Hanford.

  14. Analysis of organic carbon and moisture in Hanford single-shell tank waste

    International Nuclear Information System (INIS)

    Toth, J.J.; Heasler, P.G.; Lerchen, M.E.; Hill, J.G.; Whitney, P.D.

    1995-05-01

    This report documents a revised analysis performed by Pacific Northwest Laboratory involving the organic carbon laboratory measurement data for Hanford single-shell tanks (SSTs) obtained from a review of the laboratory analytical data. This activity has as its objective to provide a best-estimate, including confidence levels, of total organic carbon (TOC) and moisture in each of the 149 SSTs at Hanford. The TOC and moisture information presented in this report is useful as part of the criteria to identify SSTs for additional measurements, or monitoring for the Organic Safety Program. In April 1994, an initial study of the organic carbon in Hanford single-shell tanks was completed at PNL. That study reflected the estimates of TOC based on tank characterizations datasets that were available at the time. Also in that study, estimation of dry basis TOC was based on generalized assumptions pertaining to the moisture of the tank wastes. The new information pertaining to tank moisture and TOC data that has become available from the current study influences the best estimates of TOC in each of the SSTs. This investigation of tank TOC and moisture has resulted in improved estimates based on waste phase: saltcake, sludge, or liquid. This report details the assumptions and methodologies used to develop the estimates of TOC and moisture in each of the 149 SSTs at Hanford

  15. Characterization of the corrosion behavior of the carbon steel liner in Hanford Site single-shell tanks

    International Nuclear Information System (INIS)

    Anantatmula, R.P.; Schwenk, E.B.; Danielson, M.J.

    1994-06-01

    Six safety initiatives have been identified for accelerating the resolution of waste tank safety issues and closure of unreviewed safety questions. Safety Initiative 5 is to reduce safety and environmental risk from tank leaks. Item d of Safety Initiative 5 is to complete corrosion studies of single-shell tanks to determine failure mechanisms and corrosion control options to minimize further degradation by June 1994. This report has been prepared to fulfill Safety Initiative 5, Item d. The corrosion mechanisms that apply to Hanford Site single-shell tanks are stress corrosion cracking, pitting/crevice corrosion, uniform corrosion, hydrogen embrittlement, and microbiologically influenced corrosion. The corrosion data relevant to the single-shell tanks dates back three decades, when results were obtained from in-situ corrosion coupons in a few single-shell tanks. Since that time there have been intertank transfers, evaporation, and chemical alterations of the waste. These activities have changed the character and the present composition of the waste is not well characterized. All conclusions and recommendations are made in the absence of relevant laboratory experimental data and tank inspection data. The report attempts to identify the failure mechanisms by a literature survey of carbon steel data in environments similar to the single-shell tank wastes, and by a review of the work performed at the Savannah River Site where similar wastes are stored in similar carbon steel tanks. Based on these surveys, and in the absence of data specific to Hanford single-shell tanks, it may be concluded that the single-shell tanks identified as leakers failed primarily by stress corrosion cracking due to the presence of high nitrate/low hydroxide wastes and residual stresses. In addition, some failures may be attributed to pitting under crevices in low hydroxide locations

  16. Corrective action strategy for single-shell tanks containing organic chemicals

    International Nuclear Information System (INIS)

    Turner, D.A.

    1993-08-01

    A Waste Tank Organic Safety Program (Program) Plan is to be transmitted to the U.S. Department of Energy, Richland Operations Office (RL) for approval by December 31, 1993. In April 1993 an agreement was reached among cognizant U.S. Department of Energy - Headquarters (HQ), RL and Westinghouse Hanford Company (WHC) staff that the Program Plan would be preceded by a ''Corrective Action Strategy,'' which addressed selected planning elements supporting the Program Plan. The ''Corrective Action Strategy'' would be reviewed and consensus reached regarding the planning elements. A Program Plan reflecting this consensus would then be prepared. A preliminary ''corrective action strategy'' is presented for resolving the organic tanks safety issue based on the work efforts recommended in the ISB (Interim Safety Basis for Hanford Site tank farm facilities). A ''corrective action strategy'' logic was prepared for individual SSTs (single-shell tanks), or a group of SSTs having similar characteristics, as appropriate. Four aspects of the organic tanks safety issue are addressed in the ISB: SSTs with the potential for combustion in the tank's headspace; combustion of a floating organic layer as a pool fire; surface fires in tanks that formerly held floating organic layers; SSTs with the potential for organic-nitrate reactions. A preliminary ''corrective action strategy'' for each aspect of the organic tanks safety issue is presented

  17. Single Shell Tank Waste Characterization Project for Tank B-110, Core 9 - data package and PNL validation summary report

    International Nuclear Information System (INIS)

    Pool, K.N.; Jones, T.E.; McKinley, S.G.; Tingey, J.M.; Longaker, T.M.; Gibson, J.A.

    1990-01-01

    This Data Package contains results obtained by Pacific Northwest Laboratory (PNL) staff in the characterization and analyses of Core 9 segments taken from the Single-Shell Tank (SST) 110B. The characterization and analysis of Core 9 segments are outlined in the Waste Characterization Plan for Hanford Site Single-Shell Tanks and in the Pacific Northwest Laboratory (PNL) Single-Shell Tank Waste Characterization Support FY 89/90 Statement of Work (SOW), Rev. 1 dated March, 1990. Specific analyses for each sub-sample taken from a segment are delineated in Test Instructions prepared by the PNL Single-Shell Tank Waste Characterization Project Management Office (SST Project) in accordance with procedures contained in the SST Waste Characterization Procedure Compendium (PNL-MA-599). Analytical procedures used in the characterization activities are also included in PNL-MA-599. Core 9 included five segments although segment 1 did not have sufficient material for characterization. The five samplers were received from Westinghouse Hanford Company (WHC) on 11/21-22/89. Each segment was contained in a sampler and was enclosed in a shipping cask. The shipping cask was butted up to the 325-A hot cell and the sampler moved into the hot cell. The material in the sampler (i.e., the segment) was extruded from the sampler, limited physical characteristics assessed, and photographed. At this point samples were taken for particle size and volatile organic analyses. Each segment was then homogenized. Sub-samples were taken for required analyses as delineated in the appropriate Test Instruction. Table 1 includes sample numbers assigned to Core 9 segment materials being transferred from 325-A Hot Cell. Sample numbers 90-0298, 90-0299, 90-0302, and 90-0303 were included in Table 1 although no analyses were requested for these samples. Table 2 lists Core 9 sub-sample numbers per sample preparation method

  18. Research of documents pertaining to waste migration from leaking single-shell tanks

    Energy Technology Data Exchange (ETDEWEB)

    Consort, S.D. [ICF Kaiser Hanford Co., Richland, WA (United States)

    1994-09-30

    This report contains the results from an investigation of the literature concerning single-shell tank (SST) leaks on the Hanford Site. The purpose of the investigation is to determine if available data confirm or refute the assertion that leaked waste from the SSTs has reached ground water. There are 67 leaking single-shell tanks (SSTs) on the Hanford Site. Although the maximum volume of leaked waste is approximately 4,013,000 L (1,060,000 gal), it is not the only waste in the ground beneath the 200 Area. Before 1966, supernatant solution was intentionally discharged from the cascading SSTs to the ground. Other leaks from piping and surface spills contributed to the waste in the ground. The maximum estimated volume of unintentionally leaked waste from the tanks is less than 1% of the intentionally released liquid waste that was sent to the cribs and trenches from the SSTs. The volume does not include the liquid waste sent intentionally from other facilities directly to the cribs, trenches, and injection wells. The components and concentrations of the intentionally released waste were in compliance with applicable standards at the time of release.

  19. Construction Method Study For Installation Of A Large Riser In A Single-Shell Tank

    International Nuclear Information System (INIS)

    Adkisson, D.A.

    2010-01-01

    This study evaluates and identifies a construction method for cutting a hole in a single-shell tank dome. This study also identifies and evaluates vendors for performing the cut. Single-shell tanks (SST) in the 241-C tank farm are currently being retrieved using various retrieval technologies (e.g., modified sluicing). The Hanford Federal Facility Agreement and Consent Order require that the SSTs be retrieved to less than 360 cubic feet of radioactive waste. The current technologies identified and deployed for tank retrieval have not been able to retrieve waste in accordance with the Hanford Federal Facility Agreement and Consent Order. As such, alternative retrieval systems have been proposed and are currently under construction that will have the ability to retrieve waste to this defined level. The proposed retrieval systems will not fit down existing risers. New risers will need to be installed to provide the retrieval systems access to the inside of the SSTs. The purpose of this study is two-fold. The first objective is to identify multiple concrete cutting technologies and perform an initial pre-screening, evaluate the technologies identified for more in-depth analysis, and recommend a technology/methodology for cutting a hole in the tank dome. The identified/pre-screened methods will be evaluated based on the following criteria: (1) Maturity/complexity; (2) Waste generation; (3) Safety; (4) Cost; and (5) Schedule. Once the preferred method is identified to cut the hole in the tank dome, the second objective is to identify, evaluate, and recommend a vendor for the technology selected that will perform the cutting process.

  20. 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...

  1. Single-Shell Tank (SST) Retrieval Project Plan for Tank 241-C-104 Retrieval

    International Nuclear Information System (INIS)

    DEFIGH PRICE, C.

    2000-01-01

    In support of the SST Interim Closure Project, Project W-523 ''Tank 241-C-104 Waste Retrieval System'' will provide systems for retrieval and transfer of radioactive waste from tank 241-C-104 (C-104) to the DST staging tank 241-AY-101 (AY-101). At the conclusion of Project W-523, a retrieval system will have been designed and tested to meet the requirements for Acceptance of Beneficial Use and been turned over to operations. Completion of construction and operations of the C-104 retrieval system will meet the recently proposed near-term Tri-Party Agreement milestone, M-45-03F (Proposed Tri-Party Agreement change request M-45-00-01A, August, 30 2000) for demonstrating limits of retrieval technologies on sludge and hard heels in SSTs, reduce near-term storage risks associated with aging SSTs, and provide feed for the tank waste treatment plant. This Project Plan documents the methodology for managing Project W-523; formalizes responsibilities; identifies key interfaces required to complete the retrieval action; establishes the technical, cost, and schedule baselines; and identifies project organizational requirements pertaining to the engineering process such as environmental, safety, quality assurance, change control, design verification, testing, and operational turnover

  2. Process control plan for Single Shell Tank (SST) Saltcake Dissolution Proof of Concept

    International Nuclear Information System (INIS)

    ESTEY, S.D.

    2001-01-01

    This document describes the process controls for the tank 241-U-107 (U-107) saltcake dissolution proof-of-concept operations. Saltcake dissolution is defined as a method by which water-soluble salts will be retrieved from the Hanford Site radioactive waste tanks utilizing dissolution as the mobilizing mechanism. The proof-of-concept operations will monitor the retrieval process and transfer at least 100 kgal of fluid from tank U-107 to the double-shell tank (DST) system during the performance period. Tank U-107 has been identified as posing the highest long-term risk to the Columbia River of all single shell tanks (SSTs). This is because of the high content of mobile, long-lived radionuclides mostly in the saltcake waste in the tank. To meet current contractual and consent decree commitments, tank U-107 is being prepared for interim stabilization in August 2001. It is currently scheduled for saltcake retrieval in 2023, near the end of the SST retrieval campaign because of a lack of infrastructure in U-Farm. The proof-of-concept test will install a system to dissolve and retrieve a portion of the saltcake as part of, and operating in parallel with, the standard interim stabilization system to be installed on tank U-107. This proof-of-concept should provide key information on spray nozzle selection and effective spray patterns, leak detection, monitoring, and mitigation (LDMM) and in-tank saltcake solubility data that will help in the design of a full-tank retrieval demonstration system

  3. SAFETY EVALUATION OF OXALIC ACID WASTE RETRIEVAL IN SINGLE SHELL TANK (SST) 241-C-106

    International Nuclear Information System (INIS)

    SHULTZ, M.V.

    2003-01-01

    This report documents the safety evaluation of the process of retrieving sludge waste from single-shell tank 241-C-106 using oxalic acid. The results of the HAZOP, safety evaluation, and control allocation/decision are part of the report. This safety evaluation considers the use of oxalic acid to recover residual waste in single-shell tank (SST) 241-C-106. This is an activity not addressed in the current tank farm safety basis. This evaluation has five specific purposes: (1) Identifying the key configuration and operating assumptions needed to evaluate oxalic acid dissolution in SST 241-C-106. (2) Documenting the hazardous conditions identified during the oxalic acid dissolution hazard and operability study (HAZOP). (3) Documenting the comparison of the HAZOP results to the hazardous conditions and associated analyzed accident currently included in the safety basis, as documented in HNF-SD-WM-TI-764, Hazard Analysis Database Report. (4) Documenting the evaluation of the oxalic acid dissolution activity with respect to: (A) Accident analyses described in HNF-SD-WM-SAR-067, Tank Farms Final Safety Analysis Report (FSAR), and (B) Controls specified in HNF-SD-WM-TSR-006, Tank Farms Technical Safety Requirements (TSR). (5) Documenting the process and results of control decisions as well as the applicability of preventive and/or mitigative controls to each oxalic acid addition hazardous condition. This safety evaluation is not intended to be a request to authorize the activity. Authorization issues are addressed by the unreviewed safety question (USQ) evaluation process. This report constitutes an accident analysis

  4. Engineering evaluation of intrusion prevention strategies for single-shell tanks

    International Nuclear Information System (INIS)

    Jenkins, C.E.

    1994-01-01

    In this study, previously implemented actions to prevent liquid intrusion into out-of-service single-shell tanks (SSTs), i.e., interim isolation or partial interim isolation, are investigated and expanded to identify additional cost-effective intrusion prevention techniques that could be reasonably taken until SSTs are ready for waste retrieval. Possible precipitation, groundwater, and condensation pathways and internal tank connections that could provide possible pathways for liquids are examined. Techniques to block identified potential pathways are developed and costed to determine the potential benefit to costed trade-offs for implementing the techniques. (Note: Surveillance data show increased waste surface levels for several SSTs that indicate possible liquid intrusion despite interim isolation activities.)

  5. Functions and Requirements for Automated Liquid Level Gauge Instruments in Single-Shell and Double-Shell Tank Farms

    International Nuclear Information System (INIS)

    CARPENTER, K.E.

    1999-01-01

    This functions and requirements document defines the baseline requirements and criteria for the design, purchase, fabrication, construction, installation, and operation of automated liquid level gauge instruments in the Tank Farms. This document is intended to become the technical baseline for current and future installation, operation and maintenance of automated liquid level gauges in single-shell and double-shell tank farms

  6. Structural qualification of the multifunctional instrument tree for installation in double-shell and 100-series single-shell tanks

    International Nuclear Information System (INIS)

    Strohlow, J.P.

    1995-12-01

    This document provides the technical basis and methodology for qualifying the multifunctional instrument tree (MIT) structure for installation in double-shell and 100-series single-shell tanks. Structural qualification for MIT installations in specific tanks are also contained in this document

  7. Load requirements for maintaining structural integrity of Hanford single-shell tanks during waste feed delivery and retrieval activities

    International Nuclear Information System (INIS)

    JULYK, L.J.

    1999-01-01

    This document provides structural load requirements and their basis for maintaining the structural integrity of the Hanford Single-Shell Tanks during waste feed delivery and retrieval activities. The requirements are based on a review of previous requirements and their basis documents as well as load histories with particular emphasis on the proposed lead transfer feed tanks for the privatized vitrification plant

  8. Load requirements for maintaining structural integrity of Hanford single-shell tanks during waste feed delivery and retrieval activities

    Energy Technology Data Exchange (ETDEWEB)

    JULYK, L.J.

    1999-09-22

    This document provides structural load requirements and their basis for maintaining the structural integrity of the Hanford Single-Shell Tanks during waste feed delivery and retrieval activities. The requirements are based on a review of previous requirements and their basis documents as well as load histories with particular emphasis on the proposed lead transfer feed tanks for the privatized vitrification plant.

  9. 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

  10. 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

  11. First generation long-reach manipulator for retrieval of waste from Hanford single-shell tanks

    Energy Technology Data Exchange (ETDEWEB)

    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.

  12. Tank characterization report for single-shell tak 241-C-112. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.

    1997-06-11

    One major function of the Tank Waste Remediation System (IWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (CR). This report and its appendixes serve as the CR for single-shell tank 24 1 -C- 1 12. The objectives of this report are: 1) to use characterization data in response to technical issues associated with tank 24 1 -C- 1 12 waste, and 2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations regarding safety status and additional sampling needs. The appendixes contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-05 (Ecology et al. 1996).

  13. Regulatory Closure Options for the Residue in the Hanford Site Single-Shell Tanks

    International Nuclear Information System (INIS)

    Cochran, J.R.; Shyr, L.J.

    1998-01-01

    Liquid, mixed, high-level radioactive waste (HLW) has been stored in 149 single-shell tanks (SSTS) located in tank farms on the U.S. Department of Energy's (DOE's) Hanford Site. The DOE is developing technologies to retrieve as much remaining HLW as technically possible prior to physically closing the tank farms. In support of the Hanford Tanks Initiative, Sandia National Laboratories has addressed the requirements for the regulatory closure of the radioactive component of any SST residue that may remain after physical closure. There is significant uncertainty about the end state of each of the 149 SSTS; that is, the nature and amount of wastes remaining in the SSTS after retrieval is uncertain. As a means of proceeding in the face of these uncertainties, this report links possible end-states with associated closure options. Requirements for disposal of HLW and low-level radioactive waste (LLW) are reviewed in detail. Incidental waste, which is radioactive waste produced incidental to the further processing of HLW, is then discussed. If the low activity waste (LAW) fraction from the further processing of HLW is determined to be incidental waste, then DOE can dispose of that incidental waste onsite without a license from the U.S. Nuclear Regulatory Commissions (NRC). The NRC has proposed three Incidental Waste Criteria for determining if a LAW fraction is incidental waste. One of the three Criteria is that the LAW fraction should not exceed the NRC's Class C limits

  14. Functions and requirements for Hanford single-shell tank leakage detection and monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Cruse, J.M.; Ohl, P.C.

    1995-04-19

    This document provides the initial functions and requirements for leakage detection and monitoring applicable to past and potential future leakage from the Hanford Site`s 149 single-shell high-level waste tanks. This mission is a part of the overall mission of the Westinghouse Hanford Company Tank Waste Remediation System division to remediate the tank waste in a safe and acceptable manner. Systems engineering principles are being applied to this effort. This document reflects the an initial step in the systems engineering approach to decompose the mission into primary functions and requirements. The document is considered approximately 30% complete relative to the effort required to produce a final version that can be used to support demonstration and/or procurement of technologies. The functions and requirements in this document apply to detection and monitoring of below ground leaks from SST containment boundaries and the resulting soil contamination. Leakage detection and monitoring is invoked in the TWRS Program in three fourth level functions: (1) Store Waste, (2) Retrieve Waste, and (3) Disposition Excess Facilities (as identified in DOE/RL-92-60 Rev. 1, Tank Waste Remediation System Functions and Requirements).

  15. Regulatory Closure Options for the Residue in the Hanford Site Single-Shell Tanks

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, J.R. Shyr, L.J.

    1998-10-05

    Liquid, mixed, high-level radioactive waste (HLW) has been stored in 149 single-shell tanks (SSTS) located in tank farms on the U.S. Department of Energy's (DOE's) Hanford Site. The DOE is developing technologies to retrieve as much remaining HLW as technically possible prior to physically closing the tank farms. In support of the Hanford Tanks Initiative, Sandia National Laboratories has addressed the requirements for the regulatory closure of the radioactive component of any SST residue that may remain after physical closure. There is significant uncertainty about the end state of each of the 149 SSTS; that is, the nature and amount of wastes remaining in the SSTS after retrieval is uncertain. As a means of proceeding in the face of these uncertainties, this report links possible end-states with associated closure options. Requirements for disposal of HLW and low-level radioactive waste (LLW) are reviewed in detail. Incidental waste, which is radioactive waste produced incidental to the further processing of HLW, is then discussed. If the low activity waste (LAW) fraction from the further processing of HLW is determined to be incidental waste, then DOE can dispose of that incidental waste onsite without a license from the U.S. Nuclear Regulatory Commissions (NRC). The NRC has proposed three Incidental Waste Criteria for determining if a LAW fraction is incidental waste. One of the three Criteria is that the LAW fraction should not exceed the NRC's Class C limits.

  16. Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1

    International Nuclear Information System (INIS)

    Schlosser, R.L.

    1996-01-01

    This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade

  17. Preliminary performance assessment strategy for single-shell tank waste disposal

    International Nuclear Information System (INIS)

    Sonnichsen, J.C. Jr.

    1991-10-01

    The disposal of the waste stored in single-shell tanks at the Hanford Site is recognized as a major environmental concern. A comprehensive program has been initiated to evaluate the various alternatives available for disposal of these wastes. Theses wastes will be disposed of in a manner consistent with applicable laws and regulations. Long-term waste isolation is one measure of performance that will be used for purposes of selection. The performance of each disposal alternative will be simulated using numerical models. Contained herein is a discussion of the strategy that has and continues to evolve to establish a general analytical framework to evaluate this performance. This general framework will be used to construct individual models of each waste disposal alternative selected for purposes of evaluation. 30 refs., 3 figs

  18. Tank characterization report for single-shell tank 241-U-110

    International Nuclear Information System (INIS)

    Brown, T.M.; Jensen, L.

    1993-04-01

    This report investigates the nature of the waste in tank U-110 using historical and current information. When characterizing tank waste, several important properties are considered. First, the physical characteristics of the waste are presented, including waste appearance, density, and size of waste particles. The existence of any exotherms in the tank that may present a safety concern is investigated. Finally, the radiological and chemical composition of the tank are presented

  19. Tank characterization report for single-shell tank 241-U-110

    International Nuclear Information System (INIS)

    Brown, T.M.; Jensen, L.

    1993-09-01

    Tank 241-U-110 (U-110) is a Hanford Site waste tank that was;most recently sampled in November and December 1989. Analysis of the samples obtained from tank U-110 was conducted to support the characterization of the contents of this tank and to support Hanford Federal Facility Agreement and Consent Order milestone M-10-00 (Ecology, et al. 1992). Because of incomplete recovery of the waste during sampling, there may be bias in the results of this characterization report

  20. Tank characterization report for single-shell tank 241-U-110. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Brown, T.M.; Jensen, L.

    1993-09-01

    Tank 241-U-110 (U-110) is a Hanford Site waste tank that was ;most recently sampled in November and December 1989. Analysis of the samples obtained from tank U-110 was conducted to support the characterization of the contents of this tank and to support Hanford Federal Facility Agreement and Consent Order milestone M-10-00 (Ecology, et al. 1992). Because of incomplete recovery of the waste during sampling, there may be bias in the results of this characterization report.

  1. Performance and risk assessment of subsurface barriers for single-shell tank waste retrieval

    Energy Technology Data Exchange (ETDEWEB)

    Bazinet, G.D.; Cruse, J.M.; Hampsten, K.L. [Westinghouse Hanford Co., Richland, WA (United States); Treat, R.L.

    1995-02-01

    Subsurface barriers are among various alternatives under evaluation to mitigate the threat of leakage from the Hanford Site`s 149 single-shell high-level radioactive waste tanks. The Tank Waste Remediation System (TWRS) division of Westinghouse Hanford Company is conducting this evaluation of subsurface barriers and other alternatives, focusing on risk and cost as performance measures. A number of alternative retrieval/closure approaches were evaluated in terms of risks (carcinogenic and toxicological) to a postulated maximally exposed individual. In addition, worker and accident risks were evaluated and factors developed for each alternative on a relative basis. The work performed to date indicates the use of subsurface barriers may potentially reduce public risk by limiting contamination of groundwater below the Hanford Site; however, the cost in terms of actual funding and in elevated worker risk is significant. The analyses also assume certain performance levels for technologies that have not been demonstrated in field conditions similar to Hanford Site tank farms. The evaluations summarized herein are being used to support a decision by representatives of the US Department of Energy, Richland Operations Office, the Washington State Department of Ecology (Ecology), and the US Environmental Protection Agency (EPA) regarding potential further development of subsurface barrier technology.

  2. Performance and risk assessment of subsurface barriers for single-shell tank waste retrieval

    International Nuclear Information System (INIS)

    Bazinet, G.D.; Cruse, J.M.; Hampsten, K.L.; Treat, R.L.

    1995-02-01

    Subsurface barriers are among various alternatives under evaluation to mitigate the threat of leakage from the Hanford Site's 149 single-shell high-level radioactive waste tanks. The Tank Waste Remediation System (TWRS) division of Westinghouse Hanford Company is conducting this evaluation of subsurface barriers and other alternatives, focusing on risk and cost as performance measures. A number of alternative retrieval/closure approaches were evaluated in terms of risks (carcinogenic and toxicological) to a postulated maximally exposed individual. In addition, worker and accident risks were evaluated and factors developed for each alternative on a relative basis. The work performed to date indicates the use of subsurface barriers may potentially reduce public risk by limiting contamination of groundwater below the Hanford Site; however, the cost in terms of actual funding and in elevated worker risk is significant. The analyses also assume certain performance levels for technologies that have not been demonstrated in field conditions similar to Hanford Site tank farms. The evaluations summarized herein are being used to support a decision by representatives of the US Department of Energy, Richland Operations Office, the Washington State Department of Ecology (Ecology), and the US Environmental Protection Agency (EPA) regarding potential further development of subsurface barrier technology

  3. Tank characterization report for single-shell tank 241-BY-112

    International Nuclear Information System (INIS)

    Baldwin, J.H.

    1997-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-112. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10. (This tank has been designated a Ferrocyanide Watch List tank.)

  4. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    International Nuclear Information System (INIS)

    ROGERS, P.M.

    2000-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted

  5. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    ROGERS, P.M.

    2000-06-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted.

  6. Candidate reagents and procedures for the dissolution of Hanford Site single-shell tank sludges

    International Nuclear Information System (INIS)

    Schulz, W.W.; Kupfer, M.J.

    1991-10-01

    At least some of the waste in the 149 single-shell tanks (SST) at the US Department of Energy (DOE) Hanford Site will be retrieved, treated, and disposed of. Although the importance of devising efficient and cost-effective sludge dissolution procedures has long been recognized, a concerted bench-scale effort to devise and test such procedures with actual solids representative of those in Hanford Site SSTs has not been performed. Reagents that might be used, either individually or serially, to dissolve sludges include HNO 3 , HNO 3 -oxalic acid, and HNO 3 -HF. This report consolidates and updates perspectives and recommendations concerning reagents and procedures for dissolving Hanford Site SST and selected double-shell tank (DST) sludges. The principal objectives of this report are as follows: (1) Compile and review existing experimental data on dissolution of actual Hanford Site SST and DST sludges. (2) Further inform Hanford Site engineers and scientists concerning the utility of combinations of thermally unstable complexants (TUCS) reagents and various reducing agents for dissolving SST and DST sludges. (This latter technology has recently been explored at the Argonne National Laboratory.) (3) Provide guidance in laying out a comprehensive experimental program to develop technology for dissolving all types of Hanford Site SST and DST sludges. 6 refs., 1 fig., 4 tabs

  7. Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

    International Nuclear Information System (INIS)

    Stahl, S.M.

    1994-01-01

    This report provides results of a review of recently completed safety analyses related to hazards associated with Interim Stabilization of Single analyses related to hazards included oh the Hanford Site Waste Tank-Watch Shell Tanks (SSTs) that are included on the Hanford List. The purpose of the review was to identify and summarize conclusions regarding the safety of interim stabilization of Watch List SSTs, and to highlight applicable limitations, restrictions, and controls. The scope of this review was restricted to SSTs identified List in the categories of flammable gas ferrocyanide, and organic salts. High heat tanks were not included in the scope. A Watch List tank is defined as an underground storage tank containing waste that requires special safety precautions because it may have a serious potential for release of high level radioactive waste because of uncontrolled increases in temperature or pressure. Special restrictions have been placed on these tanks

  8. Tank characterization report for single-shell tank 241-B-109

    International Nuclear Information System (INIS)

    Benar, C.J.

    1997-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-109. This tank has been listed on the Organic Salts Watch List. This-report supports the requirements of the Tri-Party Agreement Milestone M 44-10

  9. Tank characterization report for single-shell tank 241-A-101

    International Nuclear Information System (INIS)

    Field, J.M.

    1997-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-A-101. This tank has been listed on the Hydrogen Watch List. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10

  10. Tank characterization report for single-shell tank 241-BX-107

    International Nuclear Information System (INIS)

    Raphael, G.F.

    1996-01-01

    This study examined and assessed the status, safety issues, composition, and distribution of the wastes contained in the tank 241-BX-107. Historical and most recent information, ranging from engineering structural assessment experiments, process history, monitoring and remediation activities, to analytical core sample data, were compiled and interpreted in an effort to develop a realistic, contemporary profile for the tank BX-107 contents

  11. Tank characterization report for single-shell tank 241-B-101

    International Nuclear Information System (INIS)

    Schreiber, R.D.

    1996-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in tank 241-B-101. This report supports the requirements of Tri-Party Agreement Milestone M-44-09

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

    Energy Technology Data Exchange (ETDEWEB)

    Conner, J.M., Fluor Daniel Hanford

    1997-02-03

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-201. This report supports the requirements of the Ri- Party Agreement Milestone M-44-05.

  13. Tank characterization report for single-shell tank 241-B-107

    International Nuclear Information System (INIS)

    Conner, J.M.

    1998-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-107. This report supports the requirements of the Tri-Party Agreement Milestone M-44-ISB

  14. Tank characterization report for single-shell tank 241-T-104

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, L.M., Fluor Daniel Hanford

    1997-02-04

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-104. This report supports the requirements of the Tri- Party Agreement Milestone M-44-05.

  15. Tank characterization report for single-shell tank 241-C-204

    International Nuclear Information System (INIS)

    Conner, J.M.

    1996-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-C-204. This report supports the requirements of Tri Party Agreement Milestone M 44 09

  16. Tank characterization report for single-shell tank 241-T-106

    International Nuclear Information System (INIS)

    Jo, J.

    1996-03-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-106. This report supports the requirements of Tri-Party Agreement Milestone M-44-09

  17. Tank characterization report for single-shell tank 241-T-108

    International Nuclear Information System (INIS)

    Baldwin, J.H.

    1996-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-108. This report supports the requirements of Tri-Party Agreement Milestone M-44-09

  18. RCRA Assessment Plan for Single-Shell Tank Waste Management Area TX-TY

    Energy Technology Data Exchange (ETDEWEB)

    Horton, Duane G.

    2007-03-26

    WMA TX-TY contains underground, single-shell tanks that were used to store liquid waste that contained chemicals and radionuclides. Most of the liquid has been removed, and the remaining waste is regulated under the RCRA as modi¬fied in 40 CFR Part 265, Subpart F and Washington State’s Hazardous Waste Management Act . WMA TX-TY was placed in assessment monitoring in 1993 because of elevated specific conductance. A groundwater quality assessment plan was written in 1993 describing the monitoring activities to be used in deciding whether WMA TX-TY had affected groundwater. That plan was updated in 2001 for continued RCRA groundwater quality assessment as required by 40 CFR 265.93 (d)(7). This document further updates the assessment plan for WMA TX-TY by including (1) information obtained from ten new wells installed at the WMA after 1999 and (2) information from routine quarterly groundwater monitoring during the last five years. Also, this plan describes activities for continuing the groundwater assessment at WMA TX TY.

  19. Tank characterization report for single-shell tank 241-BY-105

    Energy Technology Data Exchange (ETDEWEB)

    Field, J.G., Westinghouse Hanford

    1996-08-30

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-105. Sampling and analyses were completed to meet Safety Screening, Ferrocyanide and Historical Data Quality Objectives. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

  20. Tank characterization report for single-shell tank 241-BX-109

    Energy Technology Data Exchange (ETDEWEB)

    Field, J.G., Westinghouse Hanford

    1996-05-31

    This document summarizes information on historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BX-109. Sampling and analyses meet Safety Screening and Historical Data Quality Objectives. This report supports requirements of Tri-Party Agreement Milestone M-44-09.

  1. Tank characterization report for single-shell tank 241-BY-109

    International Nuclear Information System (INIS)

    Jo, J.

    1998-01-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-109. This report supports the requirements of the Tri-Party Agreement Milestone M-44-15B

  2. Development of a multi-functional scarifier dislodger with an integral pneumatic conveyance retrieval system for single-shell tank remediation. FY93 summary report

    International Nuclear Information System (INIS)

    Bamberger, J.A.; McKinnon, M.A.; Alberts, D.A.; Steele, D.E.; Crowe, C.T.

    1994-10-01

    The Underground Storage Tank Integrated Demonstration (UST-ID) is evaluating several hydraulic dislodger concepts and retrieval technologies to develop specifications for system that can retrieve wastes from single-shell tanks. Each of the dislodgers will be evaluated sequentially to determine its ability to fracture and dislodge various waste simulants such as salt cake, sludge, and viscous liquid. The retrieval methods will be evaluated to determine their ability to convey this dislodged material from the tank. This report describes on-going research that commenced in FY93 to develop specifications for a scarifier dislodger coupled with a pneumatic conveyance retrieval system. The scarifier development is described in Section 3; pneumatic conveyance development is described in Section 4. Preliminary system specifications are listed in Section 5. FY94 plans are summarized in Section 6

  3. Vapor and gas sampling of single-shell tank 241-U-104 using the in situ vapor sampling system

    International Nuclear Information System (INIS)

    Lockrem, L.L.

    1997-01-01

    The Vapor Issue.Resolution Program tasked the Vapor Team (VT) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-U-104. This document presents In Situ Vapor Sampling System (ISVS) data resulting from the July 16, 1996 sampling of SST 241-U-104. Analytical results will be presented in separate reports issued by the Pacific Northwest National Laboratory (PNNL) which supplied and analyzed the sample media

  4. Data Package for Past and Current Groundwater Flow and Contamination beneath Single-Shell Tank Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    Horton, Duane G.

    2007-03-16

    This appendix summarizes historic and recent groundwater data collected from the uppermost aquifer beneath the 200 East and 200 West Areas. Although the area of interest is the Hanford Site Central Plateau, most of the information discussed in this appendix is at the scale of individual single-shell tank waste management areas. This is because the geologic, and thus the hydraulic, properties and the geochemical properties (i.e., groundwater composition) are different in different parts of the Central Plateau.

  5. Vapor and gas sampling of single-shell tank 241-BX-110 using the in situ vapor sampling system

    International Nuclear Information System (INIS)

    Lockrem, L.L.

    1997-01-01

    The Vapor Issue Resolution Program tasked the Vapor Team (the team) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-BX-110. This document presents sampling data resulting from the April 30, 1996 sampling of SST 241-BX-110. Analytical results will be presented in a separate report issued by Pacific Northwest National Laboratory (PNNL), which supplied and analyzed the sampling media

  6. Vapor and gas sampling of single-shell tank 241-S-106 using the in situ vapor sampling system

    International Nuclear Information System (INIS)

    Lockrem, L.L.

    1997-01-01

    The Vapor Issue Resolution Program tasked the Vapor Team (VT) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-S-106. This document presents In Situ vapor Sampling System (ISVS) data resulting from the June 13, 1996 sampling of SST 241-S-106. Analytical results will be presented in separate reports issued by the Pacific Northwest National Laboratory (PNNL) which'supplied and analyzed the sample media

  7. Vapor and gas sampling of single-shell tank 241-S-103 using the in situ vapor sampling system

    International Nuclear Information System (INIS)

    Lockrem, L.L.

    1997-01-01

    The Vapor Issue Resolution Program tasked the Vapor Team (VT) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-S-103. This document presents In Situ Vapor Sampling System (ISVS) data resulting from the June 12, 1996 sampling of SST 241-S-103. Analytical results will be presented in separate reports issued by the Pacific Northwest National Laboratory (PNNL) which supplied and analyzed the sample media

  8. Proposed strategy for leak detection, monitoring, and mitigation (LDMM) during Hanford single-shell tank waste retrieval

    Energy Technology Data Exchange (ETDEWEB)

    Iwatate, D.F., Westinghouse Hanford

    1996-07-08

    This document proposes a strategy to address issues related to leakage from single-shell tanks (SSTs) during sluicing. A set of criteria are proposed to capture the relevant issues pertaining to leak detection, monitoring, and mitigation (LDMM), and allow DOE-RL, the Contractor, Ecology, and Hanford Stakeholders to reach consensus on allowable leakage volumes (ALVs). Technical studies and findings that support the proposed strategy, and ALV criteria, are summarized and referenced. This document specifically addresses LDMM for SSTs at Hanford, Washington.

  9. Statistical characterization report for Single-Shell Tank 241-T-107

    International Nuclear Information System (INIS)

    Cromar, R.D.; Wilmarth, S.R.; Jensen, L.

    1994-01-01

    This report contains the results of the statistical analysis of data from three core samples obtained from single-shell tank 241-T-107 (T-107). Four specific topics are addressed. They are summarized below. Section 3.0 contains mean concentration estimates of analytes found in T-107. The estimates of open-quotes errorclose quotes associated with the concentration estimates are given as 95% confidence intervals (CI) on the mean. The results given are based on three types of samples: core composite samples, core segment samples, and drainable liquid samples. Section 4.0 contains estimates of the spatial variability (variability between cores and between segments) and the analytical variability (variability between the primary and the duplicate analysis). Statistical tests were performed to test the hypothesis that the between cores and the between segments spatial variability is zero. The results of the tests are as follows. Based on the core composite data, the between cores variance is significantly different from zero for 35 out of 74 analytes; i.e., for 53% of the analytes there is no statistically significant difference between the concentration means for two cores. Based on core segment data, the between segments variance is significantly different from zero for 22 out of 24 analytes and the between cores variance is significantly different from zero for 4 out of 24 analytes; i.e., for 8% of the analytes there is no statistically significant difference between segment means and for 83% of the analytes there is no difference between the means from the three cores. Section 5.0 contains the results of the application of multiple comparison methods to the core composite data, the core segment data, and the drainable liquid data. Section 6.0 contains the results of a statistical test conducted to determine the 222-S Analytical Laboratory's ability to homogenize solid core segments

  10. Status report: Pretreatment chemistry evaluation FY1997 -- Wash and leach factors for the single-shell tank waste inventory

    Energy Technology Data Exchange (ETDEWEB)

    Colton, N.G.

    1997-08-01

    The wash factors will be used to partition the single-shell tank (SST) inventory into soluble and insoluble portions. The leach factors will be used to estimate the further removal of bulk analytes, such as chromium, aluminum, and phosphate, as well as minor components. Wash and leach factors are given here for 18 analytes, elements expected to drive the volume of material disposed of as high-level waste (HLW). These factors are determined by a weighting methodology developed earlier by this task. Tank-specific analyte inventory values depicted in Tank Waste Data Summary Worksheets, are calculated from concentrations obtained from characterization reports; the waste density; and the tank waste volume. The experimentally determined percentage of analytes removed by washing and leaching in a particular tank waste are translated into a mass (metric tons) in Experimental Washing and Leaching Data Summary Worksheets.

  11. 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

  12. Development and Deployment of the Extended Reach Sluicing System (ERSS) for Retrieval of Hanford Single Shell Tank Waste. Draft

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, Roger E.; Figley, Reed R.; Innes, A. G.

    2013-11-11

    A history of the evolution and the design development of Extended Reach Sluicer System (ERSS) is presented. Several challenges are described that had to be overcome to create a machine that went beyond the capabilities of prior generation sluicers to mobilize waste in Single Shell Tanks for pumping into Double Shell Tank receiver tanks. Off-the-shelf technology and traditional hydraulic fluid power systems were combined with the custom-engineered components to create the additional functionality of the ERSS, while still enabling it to fit within very tight entry envelope into the SST. Problems and challenges inevitably were encountered and overcome in ways that enhance the state of the art of fluid power applications in such constrained environments. Future enhancements to the ERSS design are explored for retrieval of tanks with different dimensions and internal obstacles.

  13. Development and Deployment of the Extended Reach Sluicing System (ERSS) for Retrieval of Hanford Single Shell Tank Waste. Draft

    International Nuclear Information System (INIS)

    Bauer, Roger E.; Figley, Reed R.; Innes, A. G.

    2013-01-01

    A history of the evolution and the design development of Extended Reach Sluicer System (ERSS) is presented. Several challenges are described that had to be overcome to create a machine that went beyond the capabilities of prior generation sluicers to mobilize waste in Single Shell Tanks for pumping into Double Shell Tank receiver tanks. Off-the-shelf technology and traditional hydraulic fluid power systems were combined with the custom-engineered components to create the additional functionality of the ERSS, while still enabling it to fit within very tight entry envelope into the SST. Problems and challenges inevitably were encountered and overcome in ways that enhance the state of the art of fluid power applications in such constrained environments. Future enhancements to the ERSS design are explored for retrieval of tanks with different dimensions and internal obstacles

  14. A safety equipment list for rotary mode core sampling systems operation in single shell flammable gas tanks

    International Nuclear Information System (INIS)

    SMALLEY, J.L.

    1999-01-01

    This document identifies all interim safety equipment to be used for rotary mode core sampling of single-shell flammable gas tanks utilizing Rotary Mode Core Sampling systems (RMCS). This document provides the safety equipment for RMCS trucks HO-68K-4600, HO-68K-4647, trucks three and four respectively, and associated equipment. It is not intended to replace or supersede WHC-SD-WM-SEL-023, (Kelly 1991), or WHC-SD-WM-SEL-032, (Corbett 1994), which classifies 80-68K-4344 and HO-68K-4345 respectively. The term ''safety equipment'' refers to safety class (SC) and safety significant (SS) equipment, where equipment refers to structures, systems and components (SSC's). The identification of safety equipment in this document is based on the credited design safety features and analysis contained in the Authorization Basis (AB) for rotary mode core sampling operations in single-shell flammable gas tanks. This is an interim safety classification since the AB is interim. This document will be updated to reflect the final RMCS equipment safety classification designations upon completion of a final AB which will be implemented with the release of the Final Safety Analysis Report (FSAR)

  15. Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for Single-Shell Tank (SST) Waste Management Areas

    International Nuclear Information System (INIS)

    MCCARTHY, M.M.

    1999-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly

  16. Status Report: Pretreatment chemistry evaluation-Wash and leach factors for the single-shell tank waste inventory

    Energy Technology Data Exchange (ETDEWEB)

    Colton, N.G.

    1996-09-01

    This report discusses a methodology developed to depict overall wash and leach factors for the Hanford single-shell tank (SST) inventory. The factors derived from this methodology, which is based on available partitioning data, are applicable to a composite SST inventory rather than only an assumed insoluble portion. The purpose of considering the entire inventory is to provide a more representative picture of the partitioning behavior of the analytes during envisioned waste retrieval and processing activities. The work described in this report was conducted by the Pretreatment Chemistry Evaluation task of the Tank Waste Remediation System (TWRS). The leach factors will be used to estimate the further removal of analytes, such as sodium, aluminum, phosphate, and other minor components. Wash and leach factors are given for elements expected to drive the volume of material disposed of as high-level waste (HLW).

  17. Phase 1 RCRA Facility Investigation & Corrective Measures Study Work Plan for Single Shell Tank (SST) Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    MCCARTHY, M.M.

    1999-08-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly.

  18. Underground Storage Tank (working)

    Data.gov (United States)

    Vermont Center for Geographic Information — Database contains information on ownership and system construction for underground storage tank facilities statewide. Database was developed in early 1990's for...

  19. Origin of Wastes in Single Shell Tanks [SST] 241-B-110 & 241B-111

    Energy Technology Data Exchange (ETDEWEB)

    JOHNSON, M.E.

    2003-05-02

    A review of waste transfer documents was conducted to identify the origin of wastes present in tanks B-110 and B-111. These tanks initially received second decontamination cycle (2C) waste from the 221-B Bismuth Phosphate Plant, which separated into 2C sludge and supernatant. The supernatant was discharged to cribs. 242-B Evaporator bottoms were briefly stored in these tanks. Later, these tanks received waste from fission product separations conducted at the 221-B Plant.

  20. 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

  1. Geochemical Processes Data Package for the Vadose Zone in the Single-Shell Tank Waste Management Areas at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Cantrell, Kirk J.; Zachara, John M.; Dresel, P. Evan; Krupka, Kenneth M.; Serne, R. Jeffrey

    2007-09-28

    This data package discusses the geochemistry of vadose zone sediments beneath the single-shell tank farms at the U.S. Department of Energy’s (DOE’s) Hanford Site. The purpose of the report is to provide a review of the most recent and relevant geochemical process information available for the vadose zone beneath the single-shell tank farms and the Integrated Disposal Facility. Two companion reports to this one were recently published which discuss the geology of the farms (Reidel and Chamness 2007) and groundwater flow and contamination beneath the farms (Horton 2007).

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-11

    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.

  5. 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

  6. Preliminary recommendations on the design of the characterization program for the Hanford Site single-shell tanks: A system analysis

    Energy Technology Data Exchange (ETDEWEB)

    Buck, J.W.; Peffers, M.S.; Hwang, S.T.

    1991-11-01

    The work described in this volume was conducted by Pacific Northwest Laboratory to provide preliminary recommendations on data quality objectives (DQOs) to support the Waste Characterization Plan (WCP) and closure decisions for the Hanford Site single-shell tanks (SSTs). The WCP describes the first of a two-phase characterization program that will obtain information to assess and implement disposal options for SSTs. This work was performed for the Westinghouse Hanford Company (WHC), the current operating contractor on the Hanford Site. The preliminary DQOs contained in this volume deal with the analysis of SST wastes in support of the WCP and final closure decisions. These DQOs include information on significant contributors and detection limit goals (DLGs) for SST analytes based on public health risk.

  7. Development and testing of single-shell tank waste retrieval technologies: Milestone M-45-01 summary report

    International Nuclear Information System (INIS)

    Shen, E.J.

    1994-08-01

    This report summarizes the activities undertaken to develop single-shell tank (SST) waste retrieval technology and complete scale-model testing. Completion of these activities fulfills the commitment of Milestone M-45-01 of the Hanford Federal Facility Agreement and Consent Order (the Tri-Party Agreement). Initial activities included engineering studies that compiled and evaluated data on all known retrieval technologies. Based on selection criteria incorporating regulatory, safety, and operational issues, several technologies were selected for further evaluation and testing. The testing ranged from small-scale, bench-top evaluations of individual technologies to full-scale integrated tests of multiple subsystems operating concurrently as a system using simulated wastes. The current baseline retrieval method for SSTs is hydraulic sluicing. This method has been used successfully in the past to recover waste from SSTs. Variations of this hydraulic or ''past practice'' sluicing may be used to retrieve the waste from the majority of the SSTs. To minimize the potential for releases to the soil, arm-based retrieval systems may be used to recover waste from tanks that are known or suspected to have leaked. Both hydraulic sluicing and arm-based retrieval will be demonstrated in the first SST. Hydraulic sluicing is expected to retrieve most of the waste, and arm-based retrieval will retrieve wastes that remain after sluicing. Subsequent tanks will be retrieved by either hydraulic sluicing or arm-based methods, but not both. The method will be determined by waste characterization, tank integrity (leak status), and presence of in-tank hardware. Currently, it is assumed that approximately 75% of all SSTs will be retrieved by hydraulic sluicing and the remaining tanks by arm-based methods

  8. Engineering evaluation of alternatives: Technologies for monitoring interstitial liquids in single-shell tanks

    Energy Technology Data Exchange (ETDEWEB)

    Brevick, C.H. [ICF Kaiser Hanford Co., Richland, WA (United States); Jenkins, C.E. [Westinghouse Hanford Co., Richland, WA (United States)

    1996-02-01

    A global search of mature, emerging, and conceptual tank liquid monitoring technologies, along with a historical review of Hanford tank farm waste monitoring instrumentation, was conducted to identify methods for gauging the quantity of interstitial waste liquids contained in Hanford SSTs. Upon completion of the search, an initial screening of alternatives was conducted to identify candidates which might be capable of monitoring interstitial tank liquids. The nine candidate technologies that were selected, evaluated, and ranked are summarized. Hydrostatic tank gauging (HTG) is the technology generally recommended for gauging the quantity of process materials contained in Hanford SSTs. HTG is a mass-based technique that has the capability for continuous remote monitoring. HTG has the advantages of no moving parts, intrinsic safety, and potentially gauging a one-million gal tank with a precision of approximately {+-}500 pounds (i.e., {+-}62 gal of water or {+-}0.02 in. of level in a 75 ft diameter tank). HTG is relatively inexpensive and probe design, construction, testing, installation, and operation should be straightforward. HTG should be configured as part of a hybrid tank gauging system. A hybrid system employs two or more independent measurement systems which function in concert to provide redundancy, improved accuracy, and maximum information at minimum cost. An excellent hybrid system choice for monitoring interstitial liquids in SSTs might be the combination of HTG with thermal differential technology.

  9. Engineering evaluation of alternatives: Technologies for monitoring interstitial liquids in single-shell tanks

    International Nuclear Information System (INIS)

    Brevick, C.H.; Jenkins, C.E.

    1996-02-01

    A global search of mature, emerging, and conceptual tank liquid monitoring technologies, along with a historical review of Hanford tank farm waste monitoring instrumentation, was conducted to identify methods for gauging the quantity of interstitial waste liquids contained in Hanford SSTs. Upon completion of the search, an initial screening of alternatives was conducted to identify candidates which might be capable of monitoring interstitial tank liquids. The nine candidate technologies that were selected, evaluated, and ranked are summarized. Hydrostatic tank gauging (HTG) is the technology generally recommended for gauging the quantity of process materials contained in Hanford SSTs. HTG is a mass-based technique that has the capability for continuous remote monitoring. HTG has the advantages of no moving parts, intrinsic safety, and potentially gauging a one-million gal tank with a precision of approximately ±500 pounds (i.e., ±62 gal of water or ±0.02 in. of level in a 75 ft diameter tank). HTG is relatively inexpensive and probe design, construction, testing, installation, and operation should be straightforward. HTG should be configured as part of a hybrid tank gauging system. A hybrid system employs two or more independent measurement systems which function in concert to provide redundancy, improved accuracy, and maximum information at minimum cost. An excellent hybrid system choice for monitoring interstitial liquids in SSTs might be the combination of HTG with thermal differential technology

  10. 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.

  11. 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.

    2013-11-19

    This document identifies 241-BY Tank Farm (BY Farm) and 241-TY Tank Farm (TY Farm) leak 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 Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  12. Systems Engineering Implementation Plan for Single-Shell Tanks (SST) Retrieval Projects

    International Nuclear Information System (INIS)

    LEONARD, M.W.; HOFFERBER, G.A.

    2000-01-01

    This document communicates the planned implementation of the Systems Engineering processes and products for the SST retrieval projects as defined in the Systems Engineering Management Plan for the Tank Farm Contractor

  13. Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

    Energy Technology Data Exchange (ETDEWEB)

    Stahl, S.M.

    1994-12-30

    The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts.

  14. Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

    International Nuclear Information System (INIS)

    Stahl, S.M.

    1994-01-01

    The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts

  15. Hanford Single-Shell Tank Leak Causes and Locations - 241-T Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2014-05-15

    This document identifies 241-T Tank Farm (T Farm) leak causes and locations for the 100 series leaking tanks (241-T-106 and 241-T-111) identified in RPP-RPT-55084, Rev. 0, Hanford 241-T Farm Leak Inventory Assessment Report. This document satisfies the T Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

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

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-12-02

    This document identifies 241-U Tank Farm (U Farm) leak causes and locations for the 100 series leaking tanks (241-U-104, 241-U-110, and 241-U-112) identified in RPP-RPT-50097, Rev. 0, Hanford 241-U Farm Leak Inventory Assessment Report. This document satisfies the U-Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. Tank characterization report for single-shell tanks 241-T-201, 241-T-202, 241-T-203, and 241-T-204

    International Nuclear Information System (INIS)

    Simpson, B.C.

    1998-01-01

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, in addition to other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for the single-shell tank series consisting of 241-T-201, -T-202, -T-203, and -T-204. The objectives of this report are: (1) to use characterization data in response to technical issues associated with T-200 series tank waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. Appendix A contains historical information for 241-T-201 to T-204, including surveillance information, records pertaining to waste transfers and tank operations, and expected tank contents derived from a process knowledge-based computer program. Appendix B summarizes sampling events, sample data obtained before 1989, and the most current sampling results. Appendix C reports the statistical analysis and numerical manipulation of data used in issue resolution. Appendix D contains the evaluation to establish the best-basis for the inventory estimate and the statistical analysis performed for this evaluation. Appendix E is a bibliography that resulted from an in-depth literature search of all known information sources applicable to tanks 241-T-201, -T-202, -T-203, and -T-204. The reports listed in Appendix E are available in the Tank Characterization and Safety Resource Center

  2. Recharge Data Package for Hanford Single-Shell Tank Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    Fayer, Michael J.; Keller, Jason M.

    2007-09-24

    Pacific Northwest National Laboratory (PNNL) assists CH2M HILL Hanford Group, Inc., in its preparation of the Resource Conservation and Recovery Act (RCRA) Facility Investigation report. One of the PNNL tasks is to use existing information to estimate recharge rates for past and current conditions as well as future scenarios involving cleanup and closure of tank farms. The existing information includes recharge-relevant data collected during activities associated with a host of projects, including those of RCRA, the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), the CH2M HILL Tank Farm Vadose Zone Project, and the PNNL Remediation and Closure Science Project. As new information is published, the report contents can be updated. The objective of this data package was to use published data to provide recharge estimates for the scenarios being considered in the RCRA Facility Investigation. Recharge rates were estimated for areas that remain natural and undisturbed, areas where the vegetation has been disturbed, areas where both the vegetation and the soil have been disturbed, and areas that are engineered (e.g., surface barrier). The recharge estimates supplement the estimates provided by PNNL researchers in 2006 for the Hanford Site using additional field measurements and model analysis using weather data through 2006.

  3. IMPROVED EX-TANK LEAK DETECTION and MONITORING TECHNOLOGY DEMONSTRATIONS IN SUPPORT OF SINGLE SHELL TANK (SST) WASTE RETRIEVAL AT HANFORD SITE

    International Nuclear Information System (INIS)

    ROGER, R.M.; CAMMANN, J.W.

    2002-01-01

    Led by the United States Department of Energy Office of River Protection (DOE-ORP) and CH2M HILL Hanford Group, Inc. (CHG), a team of experts from other facilities have been working together to narrow the field of new external tank leak detection technologies. The ability to detect and assess potential leaks more quickly will help reduce potential risks to public health and the environment during efforts to retrieve millions of gallons of waste from Hanford's older single-shell tanks (SST's). A method for early and reliable detection of leaks around and below the entire 75-foot diameter bottom of a SST is needed. ''Proof-of-concept'' testing of six ex-tank leak detection and monitoring technologies was conducted at Hanford's 105-A Mock Tank Site in August 2001. A workshop was conducted in January, 2002 to review the results and select the best of the methods tested for further testing and demonstration in support of an SST retrieval. Three methods were selected: High Resolution Resistivity; Electrical Resistance Tomography--Long Electrodes; and Electrical Resistance Tomography--Point Electrode Arrays. Planned development activity includes performance evaluation tests to determine probability of detection and the probability of false alarm for each technology and deployability tests in an actual Hanford tank farm environment

  4. 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

  5. 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.

  6. 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

  7. 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

  8. A safety assessment of rotary mode core sampling in flammable gas single shell tanks: Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Raymond, R.E.

    1996-04-15

    This safety assessment (SA) addresses each of the required elements associated with the installation, operation, and removal of a rotary-mode core sampling (RMCS) device in flammable-gas single-shell tanks (SSTs). The RMCS operations are needed in order to retrieve waste samples from SSTs with hard layers of waste for which push-mode sampling is not adequate for sampling. In this SA, potential hazards associated with the proposed action were identified and evaluated systematically. Several potential accident cases that could result in radiological or toxicological gas releases were identified and analyzed and their consequences assessed. Administrative controls, procedures and design changes required to eliminate or reduce the potential of hazards were identified. The accidents were analyzed under nine categories, four of which were burn scenarios. In SSTS, burn accidents result in unacceptable consequences because of a potential dome collapse. The accidents in which an aboveground burn propagates into the dome space were shown to be in the ``beyond extremely unlikely`` frequency category. Given the unknown nature of the gas-release behavior in the SSTS, a number of design changes and administrative controls were implemented to achieve these low frequencies. Likewise, drill string fires and dome space fires were shown to be very low frequency accidents by taking credit for the design changes, controls, and available experimental and analytical data. However, a number of Bureau of Mines (BOM) tests must be completed before some of the burn accidents can be dismissed with high confidence. Under the category of waste fires, the possibility of igniting the entrapped gases and the waste itself were analyzed. Experiments are being conducted at the BOM to demonstrate that the drill bit is not capable of igniting the trapped gas in the waste. Laboratory testing and thermal analysis demonstrated that, under normal operating conditions, the drill bit will not create high

  9. A safety assessment of rotary mode core sampling in flammable gas single shell tanks: Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    Raymond, R.E.

    1996-01-01

    This safety assessment (SA) addresses each of the required elements associated with the installation, operation, and removal of a rotary-mode core sampling (RMCS) device in flammable-gas single-shell tanks (SSTs). The RMCS operations are needed in order to retrieve waste samples from SSTs with hard layers of waste for which push-mode sampling is not adequate for sampling. In this SA, potential hazards associated with the proposed action were identified and evaluated systematically. Several potential accident cases that could result in radiological or toxicological gas releases were identified and analyzed and their consequences assessed. Administrative controls, procedures and design changes required to eliminate or reduce the potential of hazards were identified. The accidents were analyzed under nine categories, four of which were burn scenarios. In SSTS, burn accidents result in unacceptable consequences because of a potential dome collapse. The accidents in which an aboveground burn propagates into the dome space were shown to be in the ''beyond extremely unlikely'' frequency category. Given the unknown nature of the gas-release behavior in the SSTS, a number of design changes and administrative controls were implemented to achieve these low frequencies. Likewise, drill string fires and dome space fires were shown to be very low frequency accidents by taking credit for the design changes, controls, and available experimental and analytical data. However, a number of Bureau of Mines (BOM) tests must be completed before some of the burn accidents can be dismissed with high confidence. Under the category of waste fires, the possibility of igniting the entrapped gases and the waste itself were analyzed. Experiments are being conducted at the BOM to demonstrate that the drill bit is not capable of igniting the trapped gas in the waste. Laboratory testing and thermal analysis demonstrated that, under normal operating conditions, the drill bit will not create high

  10. Borehole Data Package for Calendar Year 2000 - 2001 RCRA Wells at Single-Shell Tank Waste Management Area S-SX

    Energy Technology Data Exchange (ETDEWEB)

    Horton, Duane G.; Johnson, Vernon G.

    2001-08-15

    Six new resource conservation and Recovery Act (RCRA) groundwater monitoring wells were installed at the single-shell tank farm Waste Management Area S-SX in July 2000 through March 2001 in partial fulfillment of Tri-Party Agreement milestones M-24-00L and M-24-00M. This document describes the drilling, construction, sampling and analyses of samples from the wells.

  11. Results of phase 1 groundwater quality assessment for Single-Shell Tank Waste Management Areas B-BX-BY at the Hanford Site

    International Nuclear Information System (INIS)

    Narbutovskih, S.M.

    1998-02-01

    Pacific Northwest National Laboratory conducted a Phase 1 (or first determination) groundwater quality assessment for the US Department of Energy, Richland Operations Office, in accordance with the Federal Facility Compliance Agreement. The purpose of the assessment was to determine if the Single-Shell Tank Waste Management Area (WMA) B-BX-BY has impacted groundwater quality. This report will document the evidence demonstrating that the WMA has impacted groundwater quality

  12. Results of phase 1 groundwater quality assessment for Single-Shell Tank Waste Management Areas B-BX-BY at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Narbutovskih, S.M.

    1998-02-01

    Pacific Northwest National Laboratory conducted a Phase 1 (or first determination) groundwater quality assessment for the US Department of Energy, Richland Operations Office, in accordance with the Federal Facility Compliance Agreement. The purpose of the assessment was to determine if the Single-Shell Tank Waste Management Area (WMA) B-BX-BY has impacted groundwater quality. This report will document the evidence demonstrating that the WMA has impacted groundwater quality.

  13. 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

  14. 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

  15. 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

  16. 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...

  17. Trade study of leakage detection, monitoring, and mitigation technologies to support Hanford single-shell waste retrieval

    International Nuclear Information System (INIS)

    Hertzel, J.S.

    1996-03-01

    The U.S. Department of Energy has established the Tank Waste Remediation System to safely manage and dispose of low-level, high-level, and transuranic wastes currently stored in underground storage tanks at the Hanford Site in Eastern Washington. This report supports the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone No. M-45-08-T01 and addresses additional issues regarding single-shell tank leakage detection, monitoring, and mitigation technologies and provide an indication of the scope of leakage detection, monitoring, and mitigation activities necessary to support the Tank Waste Remedial System Initial Single-shell Tank Retrieval System project

  18. Sample preparation for semivolatile organics analysis of Hanford single-shell tank waste with high nitrate/nitrite and water content

    International Nuclear Information System (INIS)

    Stromatt, R.W.; Hoppe, E.W.; Steele, M.J.

    1993-11-01

    This report describes research work carried out to solve sample preparation problems associated with applying gas chromatography with mass spectrometric detection (GC/MS) to the analysis of single shell tank (SST) samples from Hanford for semivolatile organic compounds. Poor performance was found when applying the procedures based on the U.S. Environmental Protection Agency (EPA), Contract Laboratory Program, Statement of Work (CLP SOW). Analysis work was carried out on simulated drainable liquid modeled after the SST core samples which had evidenced analysis problems. Some work was also conducted on true SST samples. It was found that the pH range was too broad in the original procedure. It was also found that by decreasing the amount of methanol used in the extraction process, problems associated with the formation of an azeotrope phase could be avoided. The authors suggest a new procedure, whose eventual application to a wide array of SST samples will lend itself to better quality control limits

  19. 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

  20. The Sort on Radioactive Waste Type model: A method to sort single-shell tanks into characteristic groups. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Hill, J.G.; Anderson, G.S. [Pacific Northwest Lab., Richland, WA (United States); Simpson, B.C. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-03-01

    The SORWT model presents a methodology to group SSTs that is both simple to understand and logical in its assumptions and construction. The SORWT model has predicted the existence of 24 groups of SSTs ranging from 22 tanks per group to two tanks per group. These 24 groups encompass 133 tanks and 93% of the total waste contained in SSTs. The first 14 groups (i.e., those that contain four tanks per group or more) represent 109 tanks and 83% of the total waste volume. This demonstrates the potential for using the SORWT model to efficiently allocate resources and to maximize characterization information gained by a minimum number of sampling events. The verification study has shown that the SST groups predicted by the SORWT model are statistically significant and reduce the variability in the concentrations for all analytes examined. The SORWT model organizes a vast amount of information and presents clear options on which SSTs are more desirable to sample. The model is also simple and flexible in its ability to incorporate new parameters such as new SST analytical data, shifting programmatic needs, and/or risk assessment-oriented criteria. This report presents the nominal composition, inventory, and uncertainty for five of the 24 SORWT groups, representing 28 tanks, 10% of the total waste volume, and 29% of the total sludge volume in SSTs. Consequently, this document provides a logical beginning framework for tank waste characterization until further information becomes available or different programmatic needs are identified.

  1. Borehole data package for well 299-W15-41 at single-shell tank waste management Area TX-TY

    International Nuclear Information System (INIS)

    Horton, D.G.; Hodges, F.N.

    2000-01-01

    One new Resource Conservation and Recovery Act (RCRA) groundwater monitoring well was installed at the single-shell tank farm Waste Management Area (WMA) TX-TY during December 1999 and January 2000 in fulfillment of Tri-Party Agreement (Ecology 1996) milestone M-24-43. The well is 299-W15-41 and is located south of the 241-TX tank farm and south of 20th Street in the 200 West Area. A figure shows the locations of all wells in the WMA TX-TY monitoring network. The new well was constructed to the specifications and requirements described in Washington Administrative Code (WAC) 173-160 and WAC 173-303, the groundwater monitoring plan for WMA TX-TY (Caggiano and Goodwin 1991), the assessment plan for WMA TX-TY (Caggiano and Chou 1993), and the description of work for well drilling and installation. This document compiles information on the drilling and construction, well development, pump installation, and sediment testing applicable to well 299-W1 5-41. Appendix A contains the geologist's log, the Well Construction Summary Report, and Well Summary Sheet (as-built diagram) and Appendix B contains borehole geophysical logs. Additional documentation concerning well construction is on file with Bechtel Hanford, Inc., Richland, Washington

  2. Radioactive air emissions notice of construction use of a portable exhauster on single-shell tanks during salt well pumping and other activities

    International Nuclear Information System (INIS)

    Hays, C.B.

    1997-01-01

    This document serves as a notice of construction (NOC), pursuant to the requirements of Washington Administrative Code (WAC) 246-247-060, and as a request for approval to construct, pursuant to 40 Code of Federal Regulations (CFR) 61.96, portable exhausters for use on single-shell tanks (SSTs) during salt well pumping and other activities. The reference to 'other activities' throughout this NOC means those activities described in Appendix A. The use of portable exhausters represents a cost savings feature because one portable exhauster can be moved back and forth between SSTS as schedules for salt well pumping or other activities dictate. A portable exhauster also could be used to simultaneously exhaust more than one SST during salt well pumping or during performance of other activities. The primary objective of providing active ventilation to these SSTS is to reduce the risk of postulated accidents to remain within risk guidelines. It is anticipated that salt well pumping will release gases entrapped within the waste as the liquid level is lowered, because of less hydrostatic force keeping the gases in place. Other activities also have the potential to release trapped gases by interrupting gas pockets within the waste. Hanford Site waste tanks must comply with the Tank Farms Safety Basis (OESH 1997) which requires that the flammable gas concentration be less than 25 percent of the lower flammability limit (LFL). The Los Alamos National Laboratory (LANL) safety analysis indicates that the LFL might be exceeded in some tanks during certain postulated accident scenarios. Also, the potential for electrical (pump motor, heat tracing) and mechanical (equipment installation) spark sources exist. Therefore, because of the presence of ignition sources and the potential for released flammable gases, active ventilation might be required in some SSTS to reduce the 'time at risk' while salt well pumping or performing other activities. Thirty tanks remain to be salt well pumped

  3. Survey package: Technical and contracting strategies for single-shell tank waste retrieval on the Hanford Site

    International Nuclear Information System (INIS)

    Ramsower, D.C.

    1995-01-01

    Westinghouse Hanford Company is interested in innovative, commercially available or adaptable retrieval system equipment, concepts, and contracting strategies that will ad to existing Hanford Site technology and significantly reduce cost and/or risk from the baseline retrieval approach of sluicing (hydraulically mining) the waste from the SSTs onsite. The objective of this request is to gather information from industry to identify and summarize a suite of retrieval-related components, systems, and contracting approaches. This information will be used to ensure that WHC understands the various waste retrieval alternative approaches, their risks, and their application on the Hanford Site tanks for those occasions when sluicing is not sufficiently effective, appropriate, or cost-effective. An additional objective is to facilitate industry's understanding of the tank and site interface requirements for SST waste retrieval and the complex statutory, legal, regulatory, labor, and other institutional standards being applied to the Hanford Site. This effort will identify and summarize retrieval solutions by the end of September 1996 so that a clear basis for future retrieval program decisions can be established

  4. 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

  5. Integral Radiator and Storage Tank

    Science.gov (United States)

    Burke, Kenneth A.; Miller, John R.; Jakupca, Ian; Sargi,Scott

    2007-01-01

    A simplified, lightweight system for dissipating heat of a regenerative fuel- cell system would include a heat pipe with its evaporator end placed at the heat source and its condenser end integrated into the wall of the regenerative fuel cell system gas-storage tanks. The tank walls act as heat-radiating surfaces for cooling the regenerative fuel cell system. The system was conceived for use in outer space, where radiation is the only physical mechanism available for transferring heat to the environment. The system could also be adapted for use on propellant tanks or other large-surface-area structures to convert them to space heat-radiating structures. Typically for a regenerative fuel cell system, the radiator is separate from the gas-storage tanks. By using each tank s surface as a heat-radiating surface, the need for a separate, potentially massive radiator structure is eliminated. In addition to the mass savings, overall volume is reduced because a more compact packaging scheme is possible. The underlying tank wall structure provides ample support for heat pipes that help to distribute the heat over the entire tank surface. The heat pipes are attached to the outer surface of each gas-storage tank by use of a high-thermal conductance, carbon-fiber composite-material wrap. Through proper choice of the composite layup, it is possible to exploit the high longitudinal conductivity of the carbon fibers (greater than the thermal conductivity of copper) to minimize the unevenness of the temperature distribution over the tank surface, thereby helping to maximize the overall heat-transfer efficiency. In a prototype of the system, the heat pipe and the composite wrap contribute an average mass of 340 g/sq m of radiator area. Lightweight space radiator panels have a mass of about 3,000 g/sq m of radiator area, so this technique saves almost 90 percent of the mass of separate radiator panels. In tests, the modified surface of the tank was found to have an emissivity of 0

  6. Groundwater quality assessment plan for single-shell tank waste management Area U at the Hanford Site

    International Nuclear Information System (INIS)

    FN Hodges; CJ Chou

    2000-01-01

    Waste Management Area U (WMA U) includes the U Tank Farm, is currently regulated under RCRA interim-status regulations, and is scheduled for closure probably post-2030. Groundwater monitoring has been under an evaluation program that compared general contaminant indicator parameters from downgradient wells to background values established from upgradient wells. One of the indicator parameters, specific conductance, exceeded its background value in one downgradient well triggering a change from detection monitoring to a groundwater quality assessment program. The objective of the first phase of this assessment program is to determine whether the increased concentrations of nitrate and chromium in groundwater are from WMA U or from an upgradient source. Based on the results of the first determination, if WMA U is not the source of contamination, then the site will revert to detection monitoring. If WMA U is the source, then a second part of the groundwater quality assessment plan will be prepared to define the rate and extent of migration of contaminants in the groundwater and their concentrations

  7. Results of Phase I groundwater quality assessment for single-shell tank waste management areas T and TX-TY at the Hanford Site

    International Nuclear Information System (INIS)

    Hodges, F.N.

    1998-01-01

    Pacific Northwest National Laboratory (PNNL) conducted a Phase I, Resource Conservation and Recovery Act of 1976 (RCRA) groundwater quality assessment for the Richland Field Office of the U.S. Department of Energy (DOE-RL) under the requirements of the Federal Facility Compliance Agreement. The purpose of the investigation was to determine if the Single-Shell Tank Waste Management Areas (WMAs) T and TX-TY have impacted groundwater quality. Waste Management Areas T and TX-TY, located in the northern part of the 200 West Area of the Hanford Site, contain the 241-T, 241-TX, and 241-TY tank farms and ancillary waste systems. These two units are regulated under RCRA interim-status regulations (under 40 CFR 265.93) and were placed in assessment groundwater monitoring because of elevated specific conductance in downgradient wells. Anomalous concentrations of technetium-99, chromium, nitrate, iodine-129, and cobalt-60 also were observed in some downgradient wells. Phase I assessment, allowed under 40 CFR 265, provides the owner-operator of a facility with the opportunity to show that the observed contamination has a source other than the regulated unit. For this Phase I assessment, PNNL evaluated available information on groundwater chemistry and past waste management practices in the vicinity of WMAs T and TX-TY. Background contaminant concentrations in the vicinity of WMAs T and TX-TY are the result of several overlapping contaminant plumes resulting from past-practice waste disposal operations. This background has been used as baseline for determining potential WMA impacts on groundwater

  8. Addendum to the RCRA Assessment Report for Single-Shell Tank Waste Management Area S-SX at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Chou, C.J.; Johnson, V.G.

    1999-10-07

    The initial Resource Conservation and Recovery Act (RCRA) groundwater quality assessment report for Waste Management Area S-SX (PNNL-11810) was issued in January 1998. The report stated a plan for conducting continued assessment would be developed after addressing Washington State Department of Ecology (Ecology) comments on initial findings in PNNL-11810. Comments from Ecology were received by US Department of Energy, Richland Operations Office (DOE-RL) on September 24, 1998. Shortly thereafter, Ecology and DOE began dispute resolution and related negotiations about tank farm vadose issues. This led to proposed new Tri-Party Agreement milestones covering a RCRA Facility Investigation-Corrective Measures Study (RFI/CMS) of the four single-shell tank farm waste management areas that were in assessment status (Waste Management Areas B-BX-BY, S-SX, T and TX-TY). The RCRA Facility Investigation includes both subsurface (vadose zone and groundwater) and surface (waste handling facilities and grounds) characterization. Many of the Ecology comments on PNNL-11810 are more appropriate for, and in many cases are superseded by, the RFI/CMS at Waste Management Area S-SX. The proposed Tri-Party Agreement milestone changes that specify the scope and schedule for the RFI/CMS work plans (Tri-Party Agreement change number M-45-98-0) were issued for public comment in February 1999. The Tri-Party Agreement narrative indicates the ongoing groundwater assessments will be integrated with the RFI/CMS work plans. This addendum documents the disposition of the Ecology comments on PNNL-11810 and identifies which comments were more appropriate for the RFI/CMS work plan.

  9. Status of containment integrity studies for continued in-tank storage of Hanford defense high-level waste

    International Nuclear Information System (INIS)

    Baca, R.G.; Beitel, G.A.; Mercier, P.F.; Moore, E.L.; Vollert, F.R.

    1978-09-01

    Information is provided on the technical studies that have been implemented for evaluating the containment integrity of the single-shell waste storage tanks. The major areas of study are an analysis of storage tank integrity, a failure mode analysis, and storage tank improvements. Evaluations of tank structural integrity include theoretical studies on static and dynamic load responses, laboratory studies on concrete durability, and experimental studies on the potential for exothermic reactions of salt cake. The structural analyses completed to date show that the tanks are in good condition and have a safety margin against overload. Environmental conditions that could cause a loss of durability are limited to the waste chemicals stored (which do not have access to the concrete). Concern that a salt cake exothermic reaction may initiate a loss of containment is not justifiable based on extensive testing completed. A failure mode analysis of a tank liner failure, a sidewall failure, and a dome collapse shows that no radiologic hazard to man results. Storage tank improvement studies completed show that support of a tank dome is achievable. Secondary containment provided by chemical grouts and bentonite clay slurry walls does not appear promising. It is now estimated that the single-shell tanks will be serviceable for the storage of salt cake waste for decades under currently established operating temperature and load limits

  10. A low-temperature process for the denitration of Hanford single-shell tank, nitrate-based waste utilizing the nitrate to ammonia and ceramic (NAC) process

    International Nuclear Information System (INIS)

    Mattus, A.J.; Lee, D.D.; Dillow, T.A.; Farr, L.L.; Loghry, S.L.; Pitt, W.W.; Gibson, M.R.

    1994-12-01

    Bench-top feasibility studies with Hanford single-shell tank (SST) simulants, using a new, low-temperature (50 to 60C) process for converting nitrate to ammonia and ceramic (NAC), have conclusively shown that between 85 to 99% of the nitrate can be readily converted. In this process, aluminum powders or shot can be used to convert alkaline, nitrate-based supernate to ammonia and an aluminum oxide-sodium aluminate-based solid which might function as its own waste form. The process may actually be able to utilize already contaminated aluminum scrap metal from various DOE sites to effect the conversion. The final, nearly nitrate-free ceramic-like product can be pressed and sintered like other ceramics. Based upon the starting volumes of 6.2 and 3.1 M sodium nitrate solution, volume reductions of 50 to 55% were obtained for the waste form produced, compared to an expected 35 to 50% volume increase if the Hanford supernate were grouted. Engineering data extracted from bench-top studies indicate that the process will be very economical to operate, and data were used to cost a batch, 1,200-kg NO 3 /h plant for working off Hanford SST waste over 20 years. Their total process cost analysis presented in the appendix, indicates that between $2.01 to 2.66 per kilogram of nitrate converted will be required. Additionally, data on the fate of select radioelements present in solution are presented in this report as well as kinetic, operational, and control data for a number of experiments. Additionally, if the ceramic product functions as its own waste form, it too will offer other cost savings associated with having a smaller volume of waste form as well as eliminating other process steps such as grouting

  11. A low-temperature process for the denitration of Hanford single-shell tank, nitrate-based waste utilizing the nitrate to ammonia and ceramic (NAC) or nitrate to ammonia and glass (NAG) process: Phase 2 report

    International Nuclear Information System (INIS)

    Mattus, A.J.; Walker, J.F. Jr.; Youngblood, E.L.; Farr, L.L.; Lee, D.D.; Dillow, T.A.; Tiegs, T.N.

    1994-12-01

    Continuing benchtop studies using Hanford single-shell tank (SST) simulants and actual Oak Ridge National Laboratory (ORNL) low-level waste (LLW), employing a new denitration process for converting nitrate to ammonia and ceramic (NAC), have conclusively shown that between 85 and 99% of the nitrate can be readily converted to gaseous ammonia. In this process, aluminum powders can be used to convert alkaline, nitrate-based supernate to ammonia and an aluminum oxide-sodium aluminate-based solid. The process may be able to use contaminated aluminum scrap metal from DOE sites to effect the conversion. The final, nitrate-free ceramic product can be pressed and sintered like other ceramics or silica and/or fluxing agents can be added to form a glassy ceramic or a flowable glass product. Based upon the starting volumes of 6.2 and 3.1 M sodium nitrate solution, volume reductions of 50 to 70% were obtained for the waste form produced. Sintered pellets produced from supernate from Melton Valley Storage Tanks (MVSTs) have been leached in accordance with the 16.1 leach test for the radioelements 85 Sr and 137 Cs. Despite lengthy counting times, 85 Sr could not be detected in the leachates. 137 Cs was only slightly above background and corresponded to a leach index of 12.2 to 13.7 after 8 months of leaching. Leach testing of unsintered and sintered reactor product spiked with hazardous metals proved that both sintered and unsintered product passed the Toxicity Characteristic Leaching Procedure (TCLP) test. Design of the equipment and flowsheet for a pilot demonstration-scale system to prove the nitrate destruction portion of the NAC process and product formation is under way

  12. Mechanisms of gas bubble retention and release: results for Hanford Waste Tanks 241-S-102 and 241-SY-103 and single-shell tank simulants

    Energy Technology Data Exchange (ETDEWEB)

    Gauglitz, P.A.; Rassat, S.D.; Bredt, P.R.; Konynenbelt, J.H.; Tingey, S.M.; Mendoza, D.P.

    1996-09-01

    Research at Pacific Northwest National Laboratory (PNNL) has probed the physical mechanisms and waste properties that contribute to the retention and release of flammable gases from radioactive waste stored in underground tanks at Hanford. This study was conducted for Westinghouse Hanford Company as part of the PNNL Flammable Gas Project. The wastes contained in the tanks are mixes of radioactive and chemical products, and some of these wastes are known to generate mixtures of flammable gases, including hydrogen, nitrous oxide, and ammonia. Because these gases are flammable, their retention and episodic release pose a number of safety concerns.

  13. Mechanisms of gas bubble retention and release: results for Hanford Waste Tanks 241-S-102 and 241-SY-103 and single-shell tank simulants

    International Nuclear Information System (INIS)

    Gauglitz, P.A.; Rassat, S.D.; Bredt, P.R.; Konynenbelt, J.H.; Tingey, S.M.; Mendoza, D.P.

    1996-09-01

    Research at Pacific Northwest National Laboratory (PNNL) has probed the physical mechanisms and waste properties that contribute to the retention and release of flammable gases from radioactive waste stored in underground tanks at Hanford. This study was conducted for Westinghouse Hanford Company as part of the PNNL Flammable Gas Project. The wastes contained in the tanks are mixes of radioactive and chemical products, and some of these wastes are known to generate mixtures of flammable gases, including hydrogen, nitrous oxide, and ammonia. Because these gases are flammable, their retention and episodic release pose a number of safety concerns

  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. Hanford Tank Cleanup Update

    International Nuclear Information System (INIS)

    Berriochoa, M.V.

    2011-01-01

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

  16. Liquid storage tanks under vertical excitation

    International Nuclear Information System (INIS)

    Philippacopoulos, A.J.

    1985-01-01

    Until recently, the hydrodynamic effects on liquid storage tanks induced by an earthquake excitation were basically treated for the horizontal component of the earthquake. Recent studies, however, showed that the hydrodynamic effects due to the vertical component of an earthquake may be significant. In these studies the tank is assumed to be fixed at the bottom. This paper is concerned with the hydrodynamic behavior of liquid storage tanks induced by vertical earthquake input excitation. First, the fluid-tank system is treated as a fixed-base system and a simple formula is obtained for the coupled fluid-structure natural frequency. Second, additional interaction effects due to the foundation flexibility on the fluid-tank system are investigated. It is concluded that the foundation flexibility may have a significant effect on the hydrodynamic behavior of the liquid storage tanks under a vertical ground shaking

  17. 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.

  18. 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

  19. 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...

  20. 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.

  1. 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...

  2. 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

  3. Preliminary recommendations on the design of the characterization program for the Hanford Site single-shell tanks: A system analysis. Volume 2, Closure-related analyte priorities, concentration thresholds, and detection limit goals based on public health concerns

    Energy Technology Data Exchange (ETDEWEB)

    Buck, J.W.; Peffers, M.S.; Hwang, S.T.

    1991-11-01

    The work described in this volume was conducted by Pacific Northwest Laboratory to provide preliminary recommendations on data quality objectives (DQOs) to support the Waste Characterization Plan (WCP) and closure decisions for the Hanford Site single-shell tanks (SSTs). The WCP describes the first of a two-phase characterization program that will obtain information to assess and implement disposal options for SSTs. This work was performed for the Westinghouse Hanford Company (WHC), the current operating contractor on the Hanford Site. The preliminary DQOs contained in this volume deal with the analysis of SST wastes in support of the WCP and final closure decisions. These DQOs include information on significant contributors and detection limit goals (DLGs) for SST analytes based on public health risk.

  4. Liquid storage tanks under seismic excitations

    International Nuclear Information System (INIS)

    Tang, Y.; Aziz Uras, R.; Chang, Y.W.

    1993-01-01

    A nuclear power plant has to be designed to withstand any earthquakes that may occur at its location. Since a nuclear power plant has many liquid storage tanks, the dynamic response of these tanks under seismic excitations must be properly analyzed in order to design these tanks to survive the earthquakes to which they may be subjected. The dynamic response of liquid-storage tanks subjected to ground excitations has been the subject of numerous studies in the past thirty years. However, most of the studies were focused on the responses of the tanks such that the contained liquid can be considered to be incompressible and inviscid. Thus, the effect of liquid viscosity on the dynamic response of the liquid-tank system is often ignored. This is justified for water-storage tanks because water has a very small viscosity. However, there are cases where the liquid viscosity is not small in comparison with that of water. For such cases the designs of these tanks based on the inviscid assumption become questionable, and the effect of viscosity on the dynamic response needs to be assessed. To the best of our knowledge, due to the complexity of the problem, the effect of viscosity has not been studied satisfactorily to date. Since the governing equations are very complicated if viscosity is included in the analysis, the closed form solutions in most cases are unattainable. Therefore, it is necessary to use a computer code to solve the equations numerically. The computer code used in this study is the finite element code, FLUSTR-ANL (FLUid-STRucture interaction code developed at Argonne National Laboratory). In this study, the tanks are assumed to be rigid and rigidly supported on their bases, and the responses are considered to be linear

  5. Liquid storage tanks under seismic excitations

    Energy Technology Data Exchange (ETDEWEB)

    Tang, Yu; Uras, R.A.; Chang, Yao W.

    1993-08-01

    The safety and reliable performance of nuclear power plants is of great concern to both the nuclear community and the general public. A nuclear power plant has to be designed to withstand any earthquakes that may occur at its location. Since a nuclear power plant has many liquid storage tanks, the dynamic response of these tanks under seismic excitations must properly analyzed in order to design these tanks to survive the earthquakes to which they may be subjected. The dynamic response of liquid-storage tanks subjected to ground excitations has been the subject of numerous studies in the past thirty years. However, most of the studies were focused on the responses of the tanks such that the contained liquid can be considered to be incompressible and inviscid. Thus, the effect of liquid viscosity on the dynamic response of the liquid-tank system is often ignored. This is justified for water-storage tanks because water has a very small viscosity. However, there are cases where the liquid viscosity is not small in comparison with that of water. For such cases the designs of these tanks based on the inviscid assumption become questionable, and the effect of viscosity on the dynamic response needs to be assessed. To the best of our knowledge, due to the complexity of the problem, the effect of viscosity has not been studied satisfactorily to date. Since the governing equations are very complicated if viscosity is included in the analysis, the closed form solutions in most cases are unattainable. Therefore, it is necessary to use a computer code to solve the equations-numerically. The computer code used in this study is the finite element code, FLUSTR-ANL(FLUid-STRucture interaction code developed at Argonne National Laboratory) (Chang et al.1988). In this study, the tanks are assumed to be rigid and rigidly supported on their bases, and the responses are considered to be linear.

  6. Improved Polyurethane Storage Tank Performance

    Science.gov (United States)

    2014-06-30

    exactly in a 10-inch by 10- inch perfect square, translated directly from the AutoCAD design. Since the pen line was ¼ inch wide and stretch...horizontal and vertical long axis of the tank. Pictures from JUN 2012 and JAN 2014 were compared and analyzed to scale as imported images in AutoCAD

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

    Energy Technology Data Exchange (ETDEWEB)

    BARKER, S.A.

    2006-07-27

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

  8. 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

  9. 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.

  10. Secondary containment large fertilizer storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Waddell, E.L.; Broder, M.F.

    1991-12-31

    The large quantities of fertilizer and pesticide, which are handled by retail facilities, have made these operations the target of regulations aimed at protecting water supplies. These regulations and dealers` desire to protect water supplies have made environmental protection a primary concern. Currently, nine states have adopted regulations which require secondary containment of fertilizers and agrichemicals. An additional seven states are developing regulations. Volume requirements and performance specifications of secondary containment structures for fertilizer storage tanks are included in all regulations. Among the different containment problems presented by retail sites, the large tanks (tanks with capacities greater than 100,000 gallons) present the greatest challenge for design and cost evaluation to determine the most effective containment system. The objective of this paper is to provide secondary containment designs for large fertilizer tanks using readily available construction materials. These designs may be innovative to some extent, but they must incorporate field experience and knowledge from trials, errors, and successful installations for existing and newly constructed fertilizer storage tanks. Case studies are presented to indicate projected costs for these alternatives.

  11. Secondary containment large fertilizer storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Waddell, E.L.; Broder, M.F.

    1991-01-01

    The large quantities of fertilizer and pesticide, which are handled by retail facilities, have made these operations the target of regulations aimed at protecting water supplies. These regulations and dealers' desire to protect water supplies have made environmental protection a primary concern. Currently, nine states have adopted regulations which require secondary containment of fertilizers and agrichemicals. An additional seven states are developing regulations. Volume requirements and performance specifications of secondary containment structures for fertilizer storage tanks are included in all regulations. Among the different containment problems presented by retail sites, the large tanks (tanks with capacities greater than 100,000 gallons) present the greatest challenge for design and cost evaluation to determine the most effective containment system. The objective of this paper is to provide secondary containment designs for large fertilizer tanks using readily available construction materials. These designs may be innovative to some extent, but they must incorporate field experience and knowledge from trials, errors, and successful installations for existing and newly constructed fertilizer storage tanks. Case studies are presented to indicate projected costs for these alternatives.

  12. 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

  13. 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

  14. First cloud-based service for analyzing storage tank data

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2010-01-15

    Most commercial storage tanks are unmonitored and require manual processes to verify conditions, remediate issues or request servicing. New Boundary Technologies has developed an off-the-shelf solution that eliminates several manual processes. Its TankVista Internet service was launched as the first cloud-based service for continuously monitoring and analyzing the conditions and storage levels of commercial storage tanks, bins, silos and other containers. TankVista takes data from storage tank sensors and translates it into graphics and maps that industry can use to drive new efficiencies in storage tank management. A bulk oil distributor can leverage TankVista to remotely and continuously monitor its own storage tanks as well as those of its clients. TankVista monitors tank level, temperature, pressure, humidity and other storage criteria in order to know exactly when and where to replenish supplies. Rather than re-filling tanks at about 50 per cent capacity, a bulk oil distributor can wait until usage levels dictate more efficient re-filling. The monitoring takes place without manual intervention. TankVista complements the iDigi Tank, which has the unique ability to wirelessly connect dispersed and remote tank assets, and get this information through drop-in wireless mesh technology to the cloud without requiring onsite Internet access. 1 fig.

  15. 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

  16. 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

  17. Computer modeling of ORNL storage tank sludge mobilization and mixing

    Energy Technology Data Exchange (ETDEWEB)

    Terrones, G.; Eyler, L.L.

    1993-09-01

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

  18. Computer modeling of ORNL storage tank sludge mobilization and mixing

    International Nuclear Information System (INIS)

    Terrones, G.; Eyler, L.L.

    1993-09-01

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

  19. Borehole data package for wells 299-W22-48, 299-W22-49, and 299-W22-50 at single-shell tank waste management Area S-SX

    International Nuclear Information System (INIS)

    Horton, D.G.; Johnson, V.G.

    2000-01-01

    Three new Resource Conservation and Recovery Act (RCRA) groundwater monitoring wells were installed at the single-shell tank farm Waste Management Area (WMA) S-SX in October 1999 through February 2000 in fulfillment of Tri-Party Agreement (Ecology 1996) milestone M-24-41. The wells are 299-W22-48, 299-W22-49, and 299-W22-50. Well 299-W22-48 is located east of the southeast corner of 241-S tank farm and is a new downgradient well in the monitoring network. Well 299-W22-49 is located on the east side of the 241-SX tank farm, adjacent to well 299-W22-39, which it replaces in the monitoring network. Well 299-W22-50 is located at the southeast corner of the 241-SX tank farm and is a replacement for downgradient monitoring well 299-W22-46, which is going dry. The original assessment monitoring plan for WMA S-SX was issued in 1996 (Caggiano 1996). That plan was updated for the continued assessment at WMA S-SX in 1999 (Johnson and Chou 1999). The updated plan provides justification for the new wells. The new wells were constructed to the specifications and requirements described in Washington Administrative Code (WAC) 173-160 and WAC 173-303, the updated assessment plan for WMA S-SX (Johnson and Chou 1999), and the description of work for well drilling and construction. This document compiles information on the drilling and construction, well development, pump installation, and sediment and groundwater sampling applicable to the installation of wells 299-W22-48, 299-W22-49 and 299-W22-50. Appendix A contains the Well Summary Sheets (as-built diagrams), the Well Construction Summary Reports, and the geologist's logs. Appendix B contains results of laboratory analyses of the physical properties of sediment samples obtained during drilling. Appendix C contains borehole geophysical logs, and Appendix D contains the analytical results from groundwater samples obtained during well drilling and construction

  20. Borehole data package for wells 299-W22-48, 299-W22-49, and 299-W22-50 at single-shell tank waste management Area S-SX

    Energy Technology Data Exchange (ETDEWEB)

    DG Horton; VG Johnson

    2000-05-18

    Three new Resource Conservation and Recovery Act (RCRA) groundwater monitoring wells were installed at the single-shell tank farm Waste Management Area (WMA) S-SX in October 1999 through February 2000 in fulfillment of Tri-Party Agreement (Ecology 1996) milestone M-24-41. The wells are 299-W22-48, 299-W22-49, and 299-W22-50. Well 299-W22-48 is located east of the southeast corner of 241-S tank farm and is a new downgradient well in the monitoring network. Well 299-W22-49 is located on the east side of the 241-SX tank farm, adjacent to well 299-W22-39, which it replaces in the monitoring network. Well 299-W22-50 is located at the southeast corner of the 241-SX tank farm and is a replacement for downgradient monitoring well 299-W22-46, which is going dry. The original assessment monitoring plan for WMA S-SX was issued in 1996 (Caggiano 1996). That plan was updated for the continued assessment at WMA S-SX in 1999 (Johnson and Chou 1999). The updated plan provides justification for the new wells. The new wells were constructed to the specifications and requirements described in Washington Administrative Code (WAC) 173-160 and WAC 173-303, the updated assessment plan for WMA S-SX (Johnson and Chou 1999), and the description of work for well drilling and construction. This document compiles information on the drilling and construction, well development, pump installation, and sediment and groundwater sampling applicable to the installation of wells 299-W22-48, 299-W22-49 and 299-W22-50. Appendix A contains the Well Summary Sheets (as-built diagrams), the Well Construction Summary Reports, and the geologist's logs. Appendix B contains results of laboratory analyses of the physical properties of sediment samples obtained during drilling. Appendix C contains borehole geophysical logs, and Appendix D contains the analytical results from groundwater samples obtained during well drilling and construction.

  1. Progress in evaluating the hazard of ferrocyanide waste storage tanks

    International Nuclear Information System (INIS)

    Babad, Harry; Cash, Robert J.; Postma, Arlin

    1992-01-01

    There are 177 high-level waste tanks on the Hanford site. Twenty-four single-shell tanks are identified as potential safety issues. These tanks contain quantities of ferrocyanide, nitrate, and nitrite salts that potentially could explode under certain conditions. Efforts were initiated in September 1990 to determine the reactive properties of the ferrocyanide waste and to define the criteria necessary to ensure tank safety until mitigation or remediation actions, if required, could be implemented. This paper describes the results of recent chemical and physical studies on synthetic ferrocyanide waste mixtures. Data obtained from monitoring, tank behavior modeling, and research studies on waste have provided sufficient understanding of the tank behavior. The Waste Tank Safety Program is exploring whether the waste in many of the ferrocyanide tanks actually represents an unreviewed safety question. The General Accounting Office (GAO) in October 1990 suggested that ferrocyanide tank accident scenarios exceed the bounds of the Hanford Environmental Impact Statement. Using the same assumptions Westinghouse Hanford Company (WHC) staff confirmed the consistency of the GAO report calculations. The hypothetical accident scenario in the GAO report, and in the EIS, are based on several assumptions that may, or may not reflect actual tank conditions. The Ferrocyanide Stabilization Program at Westinghouse Hanford (summarized in this paper) will provide updated and new data using scientific research with synthetic wastes and characterization of actual tank samples. This new information will replace the assumptions on tank waste chemical and physical properties allowing an improved recalculation of current safety and future risk associated with these tanks. (author)

  2. Progress in evaluating the hazards of ferrocyanide waste storage tanks

    International Nuclear Information System (INIS)

    Babad, H.; Cash, R.; Postma, A.

    1992-03-01

    There are 177 high-level waste tanks on the Hanford site. Twenty-four single-shell tanks are identified as potential safety issues. These tanks contain quantities of ferrocyanide, nitrate, and nitrite salts that potentially could explode under certain conditions. Efforts were initiated in September 1990 to determine the reactive properties of the ferrocyanide waste and to define the criteria necessary to ensure tank safety until mitigation or remediation actions, if required, could be implemented. This paper describes the results of recent chemical and physical studies on synthetic ferrocyanide waste mixtures. Data obtained from monitoring, tank behavior modeling, and research studies on waste have provided sufficient understanding of the tank behavior. The Waste Tank Safety Program is exploring to determine whether the waste in many of the ferrocyanide tanks actually represents an unreviewed safety question. The General Accounting Office (GAO) in October 1990 (1) suggested that ferrocyanide-tanks accident scenarios exceed the bounds of the Hanford Environmental Impact Statement (2). Using the same assumptions Westinghouse Hanford Company (WHC) staff confirmed the consistency of the GAO report calculations. The hypothetical accident scenario in the GAO report, and in the EIS, are based on several assumptions that may, or may not reflect actual tank conditions. The Ferrocyanide Stabilization Program at Westinghouse Hanford (summarized in this paper) will provide updated and new data using scientific research with synthetic and actual waste tank characterization. This new information will replace the assumptions on tank waste chemical and physical properties allowing an improved recalculation of current safety and future risk associated with these tanks

  3. 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.

  4. 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

  5. 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).

  6. 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

  7. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4

    International Nuclear Information System (INIS)

    1994-04-01

    Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms

  8. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms.

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

    Energy Technology Data Exchange (ETDEWEB)

    TU, T.A.

    2007-01-04

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

  10. 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...

  11. Implementation plan for underground waste storage tank surveillance and stabilization improvements

    Energy Technology Data Exchange (ETDEWEB)

    Dukelow, G.T.; Maupin, V.D.; Mihalik, L.A.; Washenfelder, D.J.

    1989-04-01

    Several studies have addressed the need to upgrade the methods currently used for surveillance of underground waste storage tanks, particularly single-shell tanks (SST), which are susceptible to leaks and intrusions. Fifty tasks were proposed to enhance the existing surveillance program; however, prudent budget management dictates that only the tasks with the highest potential for success be selected and funded. This plan identifies fourteen inexpensive improvements that may be implemented in less than two years. Recent developments stress the need to complete interim stabilization of these tanks more quickly than now budgeted and to identify methods to salvage or eliminate the interstitial liquid left behind after saltwell jet-pumping. The plan calls for the use of available resources to remove saltwell liquid from SSTs as rapidly as possible rather than committing to new surveillance technologies that might not lead to near-term improvements. This plan describes the selection criteria and provides cost estimates and schedules for implementing the recommendations of the task forces. The proposed improvements result in completion of jet-pumping in FY 1994, two years ahead of the current FY 1996 milestone. While the accelerated plan requires more funding in the early years, the total cost will be the same as completing the work in FY 1996.

  12. Improvements of floating roof tanks, more particularly, of storage tanks in a nuclear power plant

    International Nuclear Information System (INIS)

    Marquet, A.

    1983-01-01

    The roof is in contact with the liquid of the tank by a spherical dome of which convexity is up. The invention applies to the roofs which are tighly bound to the tank wall which surrounds it by a non-rigid membrane, more particularly for a storage tank in a nuclear power plants [fr

  13. 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.'

  14. 40 CFR 52.1931 - Petroleum storage tank controls.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 4 2010-07-01 2010-07-01 false Petroleum storage tank controls. 52... (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) Oklahoma § 52.1931 Petroleum... plan, the petroleum storage tanks listed in paragraphs (b) through (e) of this section shall be subject...

  15. Free vibration analysis of partially filled liquid storage tanks

    International Nuclear Information System (INIS)

    Tang, Y.; Chang, Y.W.

    1994-01-01

    A study on the free vibration analysis of partially filled liquid storage tanks is presented. The tanks considered are the upright circular cylindrical tanks that are rigidly supported at the base. The top of the tanks are either free or constrained. Two types of constraints are considered, namely, hinged and roller support. The governing differential equations for the tank-liquid system are obtained by application of the Rayleigh-Ritz procedure in combination with Lagrange's equation. The response functions examined include the frequency of the fundamental mode of vibration of the tank-liquid system and the associated modal pressure

  16. 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.

  17. Structural acceptance criteria for the evaulation of existing double-shell waste storage tanks located at the Hanford site, Richland, Washington

    International Nuclear Information System (INIS)

    Julyk, L.J.; Day, A.D.; Dyrness, A.D.; Moore, C.J.; Peterson, W.S.; Scott, M.A.; Shrivastava, H.P.; Sholman, J.S.; Watts, T.N.

    1995-09-01

    The structural acceptance criteria contained herein for the evaluation of existing underground double-shell waste storage tanks located at the Hanford Site is part of the Life Management/Aging Management Program of the Tank Waste Remediation System. The purpose of the overall life management program is to ensure that confinement of the waste is maintained over the required service life of the tanks. Characterization of the present condition of the tanks, understanding and characterization of potential degradation mechanisms, and development of tank structural acceptance criteria based on previous service and projected use are prerequisites to assessing tank integrity, to projecting the length of tank service, and to developing and applying prudent fixes or repairs. The criteria provided herein summarize the requirements for the analysis and structural qualification of the existing double-shell tanks for continued operation. Code reconciliation issues and material degradation under aging conditions are addressed. Although the criteria were developed for double-shell tanks, many of the provisions are equally applicable to single-shell tanks. However, the criteria do not apply to the evaluation of tank appurtenances and buried piping

  18. Hanford Waste Tank Bump Accident and Consequence Analysis

    Energy Technology Data Exchange (ETDEWEB)

    BRATZEL, D.R.

    2000-06-20

    This report provides a new evaluation of the Hanford tank bump accident analysis and consequences for incorporation into the Authorization Basis. The analysis scope is for the safe storage of waste in its current configuration in single-shell and double-shell tanks.

  19. 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

  20. TANK SPACE OPTIONS REPORT

    Energy Technology Data Exchange (ETDEWEB)

    WILLIS WL; AHRENDT MR

    2009-08-11

    Since this report was originally issued in 2001, several options proposed for increasing double-shell tank (DST) storage space were implemented or are in the process of implementation. Changes to the single-shell tank (SST) waste retrieval schedule, completion of DST space saving options, and the DST space saving options in progress have delayed the projected shortfall of DST storage space from the 2007-2011 to the 2018-2025 timeframe (ORP-11242, River Protection Project System Plan). This report reevaluates options from Rev. 0 and includes evaluations of new options for alleviating projected restrictions on SST waste retrieval beginning in 2018 because of the lack of DST storage space.

  1. Nondestructive assay of plutonium residue in horizontal storage tanks

    International Nuclear Information System (INIS)

    Marsh, S.F.

    1985-01-01

    Aqueous plutonium recovery and purification processes often involve the temporary storage of plutonium solutions in holding tanks. Because plutonium is known to precipitate from aqueous solutions under certain conditions, there is a continuing need to assay emptied tanks for plutonium residue. A portable gamma spectrometer system, specifically designed for this purpose, provides rapid assay of such plutonium residues in horizontal storage tanks. A means is thus available for the nondestructive analysis of these tanks on a regular schedule to ensure that significant deposits of plutonium are not allowed to accumulate. 5 figs

  2. 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

  3. 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

  4. Position paper, need for additional waste storage capacity and recommended path forward for project W-236a, Multi-function Waste Tank Facility

    International Nuclear Information System (INIS)

    Awadalla, N.G.

    1994-01-01

    Project W-236a, Multi-function waste Tank Facility (MWTF), was initiated to increase the safe waste storage capacity for the Tank Waste Remediation System (TWRS) by building two new one million gallon underground storage tanks in the 200 West Area and four tanks in the 200 East Area. Construction of the tanks was scheduled to begin in September 1994 with operations beginning in calendar year (CY) 1998. However, recent reviews have raised several issues regarding the mission, scope, and schedule of the MWTF. The decision to build new tanks must consider several elements, such as: Operational risk and needs -- Operational risk and flexibility must be managed such that any identified risk is reduced as soon as practicable; The amount of waste that will be generated in the future -- Additional needed tank capacity must be made available to support operations and maintain currently planned safety improvement activities; Safety issues -- The retrieval of waste from single-shell tanks (SSTs) and watch list tanks will add to the total amount of waste that must be stored in a double-shell tank (DST); Availability of existing DSTs -- The integrity of the 28 existing DSTs must be continuously managed; and Affect on other projects and programs -- Because MWTF systems have been integrated with other projects, a decision on one project will affect another. In addition the W-236a schedule is logically tied to support retrieval and safety program plans. Based on the above, two new tanks are needed for safe waste storage in the 200 West Area, and they need to be built as soon as practicable. Design should continue for the tanks in the 200 East Area with a decision made by September, on whether to construct them. Construction of the cross-site transfer line should proceed as scheduled. To implement this recommendation several actions need to be implemented

  5. Maintaining of the demineralized water quality in storage tanks

    International Nuclear Information System (INIS)

    Hochmueller, K.; Wandelt, E.

    1981-03-01

    Two processes for maintaining the quality of the mineralized water in storage tanks are considered. A slight overpressure of nitrogen can be created above the water, or the air flowing in the tank can be cleaned by passing it through a soda-containing lime filter [fr

  6. Underground storage tank 511-D1U1 closure plan

    Energy Technology Data Exchange (ETDEWEB)

    Mancieri, S.; Giuntoli, N.

    1993-09-01

    This document contains the closure plan for diesel fuel underground storage tank 511-D1U1 and appendices containing supplemental information such as staff training certification and task summaries. Precision tank test data, a site health and safety plan, and material safety data sheets are also included.

  7. Underside corrosion of above ground storage tanks (ASTs) | Rim ...

    African Journals Online (AJOL)

    Underside corrosion of a failed above ground storage tank (AST) was investigated by the physio-chemical analysis of water sample that was ingress between the tank bottom plate and the concrete foundation. The results of the water sample analysis showed pH (5.8), temperature (30°C), Conductivity (4800 μs/cm), ...

  8. Leakage detection system for radioactive waste storage tanks

    International Nuclear Information System (INIS)

    Woods, W.W.; Eul, W.A.

    1979-01-01

    The patent describes a combination of elements for detecting leakage of electrically conductive fluids from tanks, including a reference electrode, an AC generator connected between the tank and the reference electrode, and one or more sensing electrodes positioned between the tank and the reference electrode. The storage tank and reference electrode are in contact with the ground. When the AC generator is energized, current flows in the circuit, and creates an electric field in the ground between the tank and the reference electrode. The sensing electrodes are positioned so that they are within the electric field when the AC generator is energized. An electric potential measuring device, such as a voltmeter, is used to measure the electric potential at the sensing electrodes relative to the tank. A significant change in the electric potential at any one or more of the sensing electrodes is an indication that a leak has occurred in the tank

  9. 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

  10. Cathodic Protection Design Algorithms for Refineries Aboveground Storage Tanks

    Directory of Open Access Journals (Sweden)

    Kosay Abdul sattar Majbor

    2017-12-01

    Full Text Available Storage tanks condition and integrity is maintained by joint application of coating and cathodic protection. Iraq southern region rich in oil and petroleum product refineries need and use plenty of aboveground storage tanks. Iraq went through conflicts over the past thirty five years resulting in holding the oil industry infrastructure behind regarding maintenance and modernization. The primary concern in this work is the design and implementation of cathodic protection systems for the aboveground storage tanks farm in the oil industry. Storage tank external base area and tank internal surface area are to be protected against corrosion using impressed current and sacrificial anode cathodic protection systems. Interactive versatile computer programs are developed to provide the necessary system parameters data including the anode requirements, composition, rating, configuration, etc. Microsoft-Excel datasheet and Visual Basic.Net developed software were used throughout the study in the design of both cathodic protection systems. The case study considered in this work is the eleven aboveground storage tanks farm situated in al-Shauiba refinery in southern IRAQ. The designed cathodic protection systems are to be installed and monitored realistically in the near future. Both systems were designed for a life span of (15-30 years, and all their parameters were within the internationally accepted standards.

  11. Analysis of thermal stratified storage tank

    Directory of Open Access Journals (Sweden)

    Smusz Robert

    2017-09-01

    Full Text Available The basic aim of the task is to compile a temperature stratification system in an accumulation tank. The range of the thesis concerns the shape and dimensions of a stratification system for an accumulation tank. Thermal stratification is a process that comprises the maintaining of temperature stratification at different levels of an accumulation tank which reduce to a minimum the process of temperature equalization. It results from the fact that the thermal stratification in a tank significantly increases the installation efficiency and improves the process of energy storing. It is connected with a thermodynamic element quality, that is the higher the temperature, the higher the energy, and, thus, the thermos-dynamic element quality. In this phenomenon, thanks to the same amount of accumulated thermal energy and average temperature, as in a fully mixed tank, the user has a higher temperature in the upper part of the tank at his disposal. It has significant importance in the case when there is a low-temperature heating medium that transfers heat to the accumulation tank. Such a situation occurs when heat is absorbed from synthetic freons used in cooling and air-conditioning systems.

  12. 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

  13. Sloshing analysis of viscous liquid storage tanks

    International Nuclear Information System (INIS)

    Uras, R.Z.

    1995-01-01

    The effect of viscosity on the sloshing response of tanks containing viscous liquids is studied using the in-house finite element computer code, FLUSTR-ANL. Two different tank sizes each filled at two levels, are modeled, and their dynamic responses under harmonic and seismic ground motions are simulated. The results are presented in terms of the wave height, and pressures at selected nodes and elements in the finite element mesh. The viscosity manifests itself as a damping effect, reducing the amplitudes. Under harmonic excitation, the dynamic response reaches the steady-state faster as the viscosity value becomes larger. The fundamental sloshing frequency for each study case stays virtually unaffected by an increase in viscosity. For the small tank case, a 5% difference is observed in the fundamental frequency of the smallest (1 cP) and the highest (1000 cP) viscosity cases considered in this study. The fundamental frequencies of the large tank are even less sensitive

  14. 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

  15. Underground storage tank waste retrieval strategies using a high-pressure waterjet scarifier

    International Nuclear Information System (INIS)

    Hatchell, B.K.; Smalley, J.T.

    1996-01-01

    The Retrieval Process Development and Enhancements Program (RPD ampersand E) is sponsored by the U.S. Department of Energy Office of Science and Technology 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. Simulant materials representative of tank waste have been used to test the performance of the scarifier over a wide range of waste types. This technology has been shown to mobilize and convey the waste simulants at desired retrieval rates while operating within the space envelope and the dynamic loading constraints of proposed deployment devices. A testing program has been initiated to investigate system deployment techniques to determine appropriate mining strategies, level of control, sensor requirements, and address integration issues associated with deploying the scarifier by a long robotic manipulator arm. A test facility denoted the Hydraulics Testbed (HTB) is being constructed to achieve these objectives and to allow longer-duration, multiple-pass tests on large waste fields using a versatile gantry-style manipulator. Mining strategy tests with materials simulating salt cake and sludge waste forms will be conducted. This paper will describe the testbed facility and testing program and present initial test results to date

  16. Tank Space Options Report

    International Nuclear Information System (INIS)

    BOYLES, V.C.

    2001-01-01

    A risk-based priority for the retrieval of Hanford Site waste from the 149 single-shell tanks (SSTs) has been adopted as a result of changes to the Hanford Federal Facility Agreement and Consent Order (HFFACO) (Ecology et al. 1997) negotiated in 2000. Retrieval of the first three tanks in the retrieval sequence fills available capacity in the double-shell tanks (DSTs) by 2007. As a result, the HFFACO change established a milestone (M-45-12-TO1) requiring the determination of options that could increase waste storage capacity for single-shell tank waste retrieval. The information will be considered in future negotiations. This document fulfills the milestone requirement. This study presents options that were reviewed for the purpose of increasing waste storage capacity. Eight options are identified that have the potential for increasing capacity from 5 to 10 million gallons, thus allowing uninterrupted single-shell tank retrieval until the planned Waste Treatment Plant begins processing substantial volumes of waste from the double-shell tanks in 2009. The cost of implementing these options is estimated to range from less than $1 per gallon to more than $14 per gallon. Construction of new double-shell tanks is estimated to cost about $63 per gallon. Providing 5 to 10 million gallons of available double-shell tank space could enable early retrieval of 5 to 9 high-risk single-shell tanks beyond those identified for retrieval by 2007. These tanks are A-101, AX-101, AX-103, BY-102, C-107, S-105, S-106, S-108, and S-109 (Garfield et al. 2000). This represents a potential to retrieve approximately 14 million total curies, including 3,200 curies of long-lived mobile radionuclides. The results of the study reflect qualitative analyses conducted to identify promising options. The estimated costs are rough-order-of magnitude and, therefore, subject to change. Implementing some of the options would represent a departure from the current baseline and may adversely impact the

  17. 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

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Ownership of an underground storage... underground storage tank system is located. 280.220 Section 280.220 Protection of Environment ENVIRONMENTAL... as defined in § 280.210; and (b) Does not engage in petroleum production, refining, and marketing as...

  18. Solar Storage Tank Insulation Influence on the Solar Systems Efficiency

    Directory of Open Access Journals (Sweden)

    Negoitescu Arina

    2012-09-01

    Full Text Available For the storage tank of a solar system for domestic hot water production was analyzed the insulation thickness and material influence. To this end, it was considered a private house, occupied by 3 persons, located in zone I of thermal radiation, for which has been simulated the domestic hot water production process. The tank outlet hot water temperature was considered of 45°C. For simulation purposes, as insulation materials for the storage tank were taking into account glass wool and polyurethane with various thicknesses. Finally, was carried out the comparative analysis of two types of tanks, in terms of the insulation thickness influence on the solar fraction, annual solar contribution and solar annual productivity. It resulted that polyurethane is the most advantageous from all points of view.

  19. TANK FARM REMEDIATION TECHNOLOGY DEVELOPMENT PROJECT AN EXERCISE IN TECHNICAL & REGULATORY COLLABORATION

    Energy Technology Data Exchange (ETDEWEB)

    JARAYSI, M.N.

    2007-01-08

    The Tank Farm Remediation Technology Development Project at the Hanford Site focuses on waste storage tanks, pipelines and associated ancillary equipment that are part of the C-200 single-shell tank (SST) farm system located in the C Tank Farm. The purpose of the project is to obtain information on the implementation of a variety of closure activities and to answer questions on technical, operational and regulatory issues associated with closure.

  20. TANK FARM REMEDIATION TECHNOLOGY DEVELOPMENT PROJECT AN EXERCISE IN TECHNICAL and REGULATORY COLLABORATION

    International Nuclear Information System (INIS)

    JARAYSI, M.N.

    2007-01-01

    The Tank Farm Remediation Technology Development Project at the Hanford Site focuses on waste storage tanks, pipelines and associated ancillary equipment that are part of the C-200 single-shell tank (SST) farm system located in the C Tank Farm. The purpose of the project is to obtain information on the implementation of a variety of closure activities and to answer questions on technical, operational and regulatory issues associated with closure

  1. Dynamic modeling of stratification for chilled water storage tank

    International Nuclear Information System (INIS)

    Osman, Kahar; Al Khaireed, Syed Muhammad Nasrul; Ariffin, Mohd Kamal; Senawi, Mohd Yusoff

    2008-01-01

    Air conditioning of buildings can be costly and energy consuming. Application of thermal energy storage (TES) reduces cost and energy consumption. The efficiency of the overall operation is affected by storage tank sizing design, which affects thermal stratification of water during charging and discharging processes in TES system. In this study, numerical simulation is used to determine the relationship between tank size and good thermal stratification. Three dimensional simulations with different tank height-to-diameter ratio (HD) and inlet Reynolds number (Re) are investigated. The effect of the number of diffuser holes is also studied. For shallow tanks (low HD) simulations, no acceptable thermocline thickness can be seen for all Re experimented. Partial mixing is observed throughout the process. Medium HD tanks simulations show good thermocline behavior and clear distinction between warm and cold water can be seen. Finally, deep tanks (high HD) show less acceptable thermocline thickness as compared to that of medium HD tanks. From this study, doubling and halving the number of diffuser holes show no significant effect on the thermocline behavior

  2. RCRA closure plan for underground storage tank 105-C

    International Nuclear Information System (INIS)

    Miles, W.C. Jr.

    1990-01-01

    A Reactor Department program for repairing heat exchangers created a low level radioactive waste, which was held in underground storage tank (UST) 105-C, hereafter referred to as the tank. According to Procedures used at the facility, the waste's pH was adjusted to the 8.0--12.0 range before shipping it to the SRS Waste Management Department. For this reason, area personnel did not anticipate that the waste which is currently contained in the tank would have corrosive hazardous characteristic. However, recent analysis indicates that waste contained in the tank has a pH of greater than 12.5, thereby constituting a hazardous waste. Because the Department of Energy-Savannah River Office (DOE-SR) could not prove that the hazardous waste had been stored in the tank for less than 90 days, the State of South Carolina Department of Health and Environmental Control (SCDHEC) alleged that DOE-SR was in violation of the 1976 Code of Laws of South Carolina. As agreed in Settlement Agreement 90-74-SW between the DOE and SCDHEC, this is the required closure plan for Tank 105-C. The purpose of this document is to present SCDHEC with an official plan for closing the underground storage tank. Upon approval by SCDHEC, the schedule for closure will be an enforceable portion of this agreement

  3. Dynamic modeling of stratification for chilled water storage tank

    Energy Technology Data Exchange (ETDEWEB)

    Osman, Kahar; Al Khaireed, Syed Muhammad Nasrul; Ariffin, Mohd Kamal; Senawi, Mohd Yusoff [Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia)

    2008-11-15

    Air conditioning of buildings can be costly and energy consuming. Application of thermal energy storage (TES) reduces cost and energy consumption. The efficiency of the overall operation is affected by storage tank sizing design, which affects thermal stratification of water during charging and discharging processes in TES system. In this study, numerical simulation is used to determine the relationship between tank size and good thermal stratification. Three dimensional simulations with different tank height-to-diameter ratio (HD) and inlet Reynolds number (Re) are investigated. The effect of the number of diffuser holes is also studied. For shallow tanks (low HD) simulations, no acceptable thermocline thickness can be seen for all Re experimented. Partial mixing is observed throughout the process. Medium HD tanks simulations show good thermocline behavior and clear distinction between warm and cold water can be seen. Finally, deep tanks (high HD) show less acceptable thermocline thickness as compared to that of medium HD tanks. From this study, doubling and halving the number of diffuser holes show no significant effect on the thermocline behavior. (author)

  4. Design of crude oil storage tank for acoustic emission testing

    International Nuclear Information System (INIS)

    Shukri Mohd; Masrul Nizam Salleh; Abd Razak Hamzah; Norasiah Abd Kasim

    2005-01-01

    The integrity of crude oil storage tank needs to be well managed because they can contain a large inventory of hazardous material and because of the high cost such as cleaning and waste disposal prior to disposal and maintenance. Costs involved in cleaning and inspection can be up to several hundreds thousand Malaysian Ranting. If the floor then proves to be in good condition, these costs have been wasted. Acoustic Emission (AE) is proposed to be use for monitoring the floor of the storage tank on line without doing cleaning and waste disposal. A storage tank will be fabricated for storing the crude oil and then the corrosion process will be monitor using AE method. This paper will discuss the background, material and is technical specification, design and also the difficulties faced during design and fabrication process. (Author)

  5. Effect of viscosity on seismic response of waste storage tanks

    International Nuclear Information System (INIS)

    Tang, Yu; Uras, R.A.; Chang, Yao-Wen.

    1992-06-01

    The dynamic response of liquid-storage tanks subjected to harmonic excitations and earthquake ground motions has been studied. A rigid tank of negligible mass, rigidly supported at the base having a diameter of 50 ft. and fluid height of 20.4 ft. was used in the computer analysis. The liquid is assumed to have a density of 1.5 g/ml. Viscosity values, μ = 60, 200, 100, and 10,000 cP, were used in the numerical analyses to study the effects of viscosity on sloshing wave height, impulsive and convective pressure on the tank wall, base shear and base moments. Harmonic excitations as well as earthquake ground motions were used as input motions. The harmonic excitations used in the analyses covers a wide range of frequencies, including both the resonant and non-resonant frequencies. Two earthquake motions were used. One matches the Newmark-Hall median response spectrum and is anchored at 0.24 g for a rock site with a damping of 2% and a time duration of 10 s. The other is the 1978 Tabas earthquake which had a peak ZPA of 0.81 g and a time duration of 29 s. A small tank, about 1/15 the size of the typical waste storage tank, was used in the harmonic excitation study to investigate the effect of viscosity on the response of liquid-storage tanks and how the viscosity effect is affected by the size of the storage tank. The results of this study show that for the typical waste storage tank subjected to earthquake motions, the effect of viscosity on sloshing wave height and impulsive and convective pressures is very small and can be neglected. For viscosity effect to become noticeable in the response of the typical waste storage tank, the waste viscosity must be greater than 10,000 cP. This value is far greater than the estimated viscosity value of the high level wastes, which may range from 60 to 200 cP for some tanks

  6. Hanford Tank Farm interim storage phase probabilistic risk assessment outline

    International Nuclear Information System (INIS)

    1994-01-01

    This report is the second in a series examining the risks for the high level waste (HLW) storage facilities at the Hanford Site. The first phase of the HTF PSA effort addressed risks from Tank 101-SY, only. Tank 101-SY was selected as the initial focus of the PSA because of its propensity to periodically release (burp) a mixture of flammable and toxic gases. This report expands the evaluation of Tank 101-SY to all 177 storage tanks. The 177 tanks are arranged into 18 farms and contain the HLW accumulated over 50 years of weapons material production work. A centerpiece of the remediation activity is the effort toward developing a permanent method for disposing of the HLW tank's highly radioactive contents. One approach to risk based prioritization is to perform a PSA for the whole HLW tank farm complex to identify the highest risk tanks so that remediation planners and managers will have a more rational basis for allocating limited funds to the more critical areas. Section 3 presents the qualitative identification of generic initiators that could threaten to produce releases from one or more tanks. In section 4 a detailed accident sequence model is developed for each initiating event group. Section 5 defines the release categories to which the scenarios are assigned in the accident sequence model and presents analyses of the airborne and liquid source terms resulting from different release scenarios. The conditional consequences measured by worker or public exposure to radionuclides or hazardous chemicals and economic costs of cleanup and repair are analyzed in section 6. The results from all the previous sections are integrated to produce unconditional risk curves in frequency of exceedance format

  7. SIGNIFICANT PROGRESS IN THE DEPLOYMENT OF NEW TECHNOLOGIES FOR THE RETRIEVAL OF HANFORD RADIOACTIVE WASTE STORAGE TANKS

    International Nuclear Information System (INIS)

    RAYMOND RE; DODD RA; CARPENTER KE; STURGES MH

    2008-01-01

    Significant enhancements in the development and deployment of new technologies for removing waste from storage tanks at the Hanford Site have resulted in accelerated progress and reduced costs for tank cleanup. CH2M HILL Hanford Group, Inc. is the U.S. Department of Energy, Office of River Protection's prime contractor responsible for safely storing and retrieving approximately 53 million gallons of highly-radioactive and hazardous waste stored in 177 underground tanks. The waste is stored in 149 older single-shell tanks (SST) and 28 newer double-shell tanks (DST) that are grouped in 18 so-called farms near the center of the Hanford Site, located in southeastern Washington State. Tank contents include materials from years of World-War II and post-war weapons production, which account for 60 percent by volume of the nation's high-level radioactive waste. A key strategy for improved cleanup is the development and deployment of innovative technologies, which enhance worker safety, resolve technical challenges, streamline retrieval processes, and cut project costs and durations. During the past seven years of tank cleanout projects we have encountered conditions and waste chemistry that defy conventional approaches, requiring a variety of new tools and techniques. Through the deployment of advanced technology and the creative application of resources, we are finding ways to accomplish the retrieval process safely, swiftly, and economically. To date, retrieval operations have been completed in seven tanks, including a record six tanks in a two-year period. Retrieval operations are in progress for another three tanks. This paper describes the following tank cleanup technologies deployed at Hanford in the past few years: Modified waste sluicing, High pressure water lance, Mobile retrieval tools, Saltcake dissolution, Vacuum retrieval, Sparging of wastes, Selective dissolution for waste treatment, Oxalic acid dissolution, High-pressure water mixers, Variable height pumps

  8. 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

  9. 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

  10. Thermal analysis elements of liquefied gas storage tanks

    Science.gov (United States)

    Yanvarev, I. A.; Krupnikov, A. V.

    2017-08-01

    Tasks of solving energy and resource efficient usage problems, both for oil producing companies and for companies extracting and transporting natural gas, are associated with liquefied petroleum gas technology development. Improving the operation efficiency of liquefied products storages provides for conducting structural, functional, and appropriate thermal analysis of tank parks in the general case as complex dynamic thermal systems.

  11. Impact of environmental conditions on sub-surface storage tanks ...

    African Journals Online (AJOL)

    Cast iron made storage tanks with gasoline fluid were buried under the soil at a depth of 4 m under various environment conditions. The simulated conditions include natural rain fail, temperature and acidic, alkaline and neutral soils. A control condition of neutral sea sand as base and filling materials were also investigated.

  12. K Basins sludge removal temporary sludge storage tank system

    Energy Technology Data Exchange (ETDEWEB)

    Mclean, M.A.

    1997-06-12

    Shipment of sludge from the K Basins to a disposal site is now targeted for August 2000. The current path forward for sludge disposal is shipment to Tank AW-105 in the Tank Waste Remediation System (TWRS). Significant issues of the feasibility of this path exist primarily due to criticality concerns and the presence of polychlorinated biphenyls (PCBS) in the sludge at levels that trigger regulation under the Toxic Substance Control Act. Introduction of PCBs into the TWRS processes could potentially involve significant design and operational impacts to both the Spent Nuclear Fuel and TWRS projects if technical and regulatory issues related to PCB treatment cannot be satisfactorily resolved. Concerns of meeting the TWRS acceptance criteria have evolved such that new storage tanks for the K Basins sludge may be the best option for storage prior to vitrification of the sludge. A reconunendation for the final disposition of the sludge is scheduled for June 30, 1997. To support this decision process, this project was developed. This project provides a preconceptual design package including preconceptual designs and cost estimates for the temporary sludge storage tanks. Development of cost estimates for the design and construction of sludge storage systems is required to help evaluate a recommendation for the final disposition of the K Basin sludge.

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

    International Nuclear Information System (INIS)

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

    1993-10-01

    Hanford's underground storage 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. The IRG's Preliminary Report assessed retrieval systems for underground storage tank wastes at Hanford in 1992. Westinghouse Hanford Company (WHC) concurred with the report's recommendation that a tool should be developed for evaluating retrieval concepts. The report recommended that this tool include (1) important considerations identified previously by the IRG, (2) a means of documenting important decisions concerning retrieval systems, and (3) a focus on evaluations and assessments for the Tank Waste Remediation System (TWRS) and the Underground Storage Tank-Integrated Demonstration (UST-ID)

  14. Elephant's foot phenomenon in liquid storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Chen, C.Q.

    1983-01-01

    This paper presents a method for analyzing the seismic response of a flat bottomed cylindrical liquid storage tank to vertical earthquake excitation. Here, vertical earthquake acceleration is considered to correspond to an increase in the density of a stored liquid. Taking into account the vertical and horizontal earthquake loads, hydrostatic pressure, and considering restrictive moment and shear forces at shell-bottom welded joint, the author has calculated circumferential and longitudinal stresses. These are combined to more accurately approximate the stresses at the base shell course. The calculated result closely conforms to the actual damage, termed ''elephant's foot,'' observed in the fuel storage tanks damaged in the Tangshan earthquake. This result shows that the ''elephant's foot'' phenomenon is not caused by buckling of the tank shell due to longitudinal compressive stresses resulting from horizontal earthquake acceleration, but rather by the combined stresses in the base shell course of the storage tank exceeding the yield strength of the shell course material. The effect due to vertical earthquake load is more than the effect from the horizontal load. Finally, some earthquake resistant methods to prevent the ''elephant's foot'' phenomenon are suggested by the author.

  15. Nondestructive examination technologies for inspection of radioactive waste storage tanks

    International Nuclear Information System (INIS)

    Anderson, M.T.; Kunerth, D.C.; Davidson, J.R.

    1995-08-01

    The evaluation of underground radioactive waste storage tank structural integrity poses a unique set of challenges. Radiation fields, limited access, personnel safety and internal structures are just some of the problems faced. To examine the internal surfaces a sensor suite must be deployed as an end effector on a robotic arm. The purpose of this report is to examine the potential failure modes of the tanks, rank the viability of various NDE technologies for internal surface evaluation, select a technology for initial EE implementation, and project future needs for NDE EE sensor suites

  16. Rationale for the closure of the soil density unreviewed safety question and recommended structural analyses improvements for the Tank Waste Remidiation System underground storage facilities

    International Nuclear Information System (INIS)

    Morris, K.H.

    1998-01-01

    The purpose of this report is twofold. First, this report documents the technical evaluation supporting the Project Hanford Management Contract (PHMC) contractor recommendation to close the Unreviewed Safety Question (USQ) as originally evaluated in TF-94-0260, Soil Compaction Test Data Indicates Soil Density in Excess of Density Used in Tank Qualification Analysis for AP Tank Farm. Second, this report describes the status of existing structural analyses for the Tank Waste Remediation System (TWRS) waste storage structures and outlines the associated technical upgrades being considered by the contractor. This second feature of the report serves to communicate the distinction between the soil density issue which is the topic of the open USQ and other technical issues which are important to the contractor from a programmatic standpoint. Contractor actions to address the latter technical issues would support improvements in day-to-day operations (e.g., provide possible relaxations in soil load restrictions) but are not necessary to close the soil density USQ. Section 2.0 of this report documents the rationale for the PHMC contractor recommendation to the Department of Energy (DOE) to close the soil density USQ. Section 3.0 documents the recommended structural analyses improvements for the double-shell tanks (DSTs) which are the structures associated with the soil density USQ. Sections 4.0 and 5.0 provide, for completeness, the same information for single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks and inactive miscellaneous underground storage tanks (IMUSTs). Section 6.0 provides the conclusions of this report

  17. Tank 241-C-103 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-10-06

    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.

  18. Experimental study and modelization of a propane storage tank depressurization

    International Nuclear Information System (INIS)

    Veneau, Tania

    1995-01-01

    The risks associated with the fast depressurization of propane storage tanks reveals the importance of the 'source term' determination. This term is directly linked, among others, to the characteristics of the jet developed downstream of the breach. The first aim of this work was to provide an original data bank concerning drop velocity and diameter distributions in a propane jet. For this purpose, a phase Doppler anemometer bas been implemented on an experimental set-up. Propane blowdowns have been performed with different breach sizes and several initial pressures in the storage tank. Drop diameter and velocity distributions have been investigated at different locations in the jet zone. These measurements exhibited the fragmentation and vaporisation trends in the jet. The second aim of this work concerned the 'source term'. lt required to study the coupling between the fluid behaviour inside the tank and the flow through the breach. This model took into account the phase exchange when flashing occurred in the tank. The flow at the breach was described with an homogeneous relaxation model. This coupled modelization has been successfully and exhaustively validated. lt originality lies on the application to propane flows. (author) [fr

  19. 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

  20. Estimating Residual Solids Volume In Underground Storage Tanks

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-01-08

    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

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

    International Nuclear Information System (INIS)

    2009-01-01

    Corrective Action Unit (CAU) 134 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Aboveground Storage Tanks' and consists of the following four Corrective Action Sites (CASs), located in Areas 3, 15, and 29 of the Nevada Test Site: (1) CAS 03-01-03, Aboveground Storage Tank; (2) CAS 03-01-04, Tank; (3) CAS 15-01-05, Aboveground Storage Tank; and (4) CAS 29-01-01, Hydrocarbon Stain

  2. 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

  3. Fluid manifold design for a solar energy storage tank

    Science.gov (United States)

    Humphries, W. R.; Hewitt, H. C.; Griggs, E. I.

    1975-01-01

    A design technique for a fluid manifold for use in a solar energy storage tank is given. This analytical treatment generalizes the fluid equations pertinent to manifold design, giving manifold pressures, velocities, and orifice pressure differentials in terms of appropriate fluid and manifold geometry parameters. Experimental results used to corroborate analytical predictions are presented. These data indicate that variations in discharge coefficients due to variations in orifices can cause deviations between analytical predictions and actual performance values.

  4. 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.

  5. [Study on the quantitative estimation method for VOCs emission from petrochemical storage tanks based on tanks 4.0.9d model].

    Science.gov (United States)

    Li, Jing; Wang, Min-Yan; Zhang, Jian; He, Wan-Qing; Nie, Lei; Shao, Xia

    2013-12-01

    VOCs emission from petrochemical storage tanks is one of the important emission sources in the petrochemical industry. In order to find out the VOCs emission amount of petrochemical storage tanks, Tanks 4.0.9d model is utilized to calculate the VOCs emission from different kinds of storage tanks. VOCs emissions from a horizontal tank, a vertical fixed roof tank, an internal floating roof tank and an external floating roof tank were calculated as an example. The consideration of the site meteorological information, the sealing information, the tank content information and unit conversion by using Tanks 4.0.9d model in China was also discussed. Tanks 4.0.9d model can be used to estimate VOCs emissions from petrochemical storage tanks in China as a simple and highly accurate method.

  6. 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.

  7. Seismic performance of spherical liquid storage tanks: a case study

    Science.gov (United States)

    Fiore, Alessandra; Demartino, Cristoforo; Greco, Rita; Rago, Carlo; Sulpizio, Concetta; Vanzi, Ivo

    2018-02-01

    Spherical storage tanks are widely used for various types of liquids, including hazardous contents, thus requiring suitable and careful design for seismic actions. On this topic, a significant case study is described in this paper, dealing with the dynamic analysis of a spherical storage tank containing butane. The analyses are based on a detailed finite element (FE) model; moreover, a simplified single-degree-of-freedom idealization is also set up and used for verification of the FE results. Particular attention is paid to the influence of sloshing effects and of the soil-structure interaction for which no special provisions are contained in technical codes for this reference case. Sloshing effects are investigated according to the current literature state of the art. An efficient methodology based on an "impulsive-convective" decomposition of the container-fluid motion is adopted for the calculation of the seismic force. With regard to the second point, considering that the tank is founded on piles, soil-structure interaction is taken into account by computing the dynamic impedances. Comparison between seismic action effects, obtained with and without consideration of sloshing and soil-structure interaction, shows a rather important influence of these parameters on the final results. Sloshing effects and soil-structure interaction can produce, for the case at hand, beneficial effects. For soil-structure interaction, this depends on the increase of the fundamental period and of the effective damping of the overall system, which leads to reduced design spectral values.

  8. 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

  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. 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.

  11. Interim criteria for Organic Watch List tanks at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Babad, S.; Turner, D.A.

    1993-09-01

    This document establishes interim criteria for identifying single-shell radioactive waste storage tanks at the Hanford Site that contain organic chemicals mixed with nitrate/nitrite salts in potentially hazardous concentrations. These tanks are designated as ``organic Watch List tanks.`` Watch List tanks are radioactive waste storage tanks that have the potential for release of high-level waste as a result of uncontrolled increases in temperature or pressure. Organic Watch List tanks are those Watch List tanks that contain relatively high concentrations of organic chemicals. Because of the potential for release of high-level waste resulting from uncontrolled increases in temperature or pressure, the organic Watch List tanks (collectively) constitute a Hanford Site radioactive waste storage tank ``safety issue.``

  12. Interim criteria for Organic Watch List tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Babad, S.; Turner, D.A.

    1993-09-01

    This document establishes interim criteria for identifying single-shell radioactive waste storage tanks at the Hanford Site that contain organic chemicals mixed with nitrate/nitrite salts in potentially hazardous concentrations. These tanks are designated as ''organic Watch List tanks.'' Watch List tanks are radioactive waste storage tanks that have the potential for release of high-level waste as a result of uncontrolled increases in temperature or pressure. Organic Watch List tanks are those Watch List tanks that contain relatively high concentrations of organic chemicals. Because of the potential for release of high-level waste resulting from uncontrolled increases in temperature or pressure, the organic Watch List tanks (collectively) constitute a Hanford Site radioactive waste storage tank ''safety issue.''

  13. Automatic non destructive testing of storage tanks; Controle non destructif automatique des cuves de stockage

    Energy Technology Data Exchange (ETDEWEB)

    Kowarski, A. [Alstom CND, 91 - Bretigny sur Orge (France); Otte, H.J. [Alstom Automation, Nuremberg (Germany)

    2001-07-01

    Storage tanks in the chemical and petrochemical industry have to be inspected periodically in order to prevent damage to the environment due to leakages caused by corrosion of the tanks. ALSTOM presents a innovative concept for the inspection of storage tanks without the need to decommission, empty and clean the tank in order to make the tanks accessible for inspection personnel. A Remote Operated Vehicle (ROV) floating in the liquid inside the tank performs the inspection with a very high positioning accuracy. The results are displayed in colour-coded mode and stored digitally for comparison with earlier inspections. (authors)

  14. Structural Health Monitoring of Above-Ground Storage Tank Floors by Ultrasonic Guided Wave Excitation on the Tank Wall

    Directory of Open Access Journals (Sweden)

    Premesh S. Lowe

    2017-11-01

    Full Text Available There is an increasing interest in using ultrasonic guided waves to assess the structural degradation of above-ground storage tank floors. This is a non-invasive and economically viable means of assessing structural degradation. Above-ground storage tank floors are ageing assets which need to be inspected periodically to avoid structural failure. At present, normal-stress type transducers are bonded to the tank annular chime to generate a force field in the thickness direction of the floor and excite fundamental symmetric and asymmetric Lamb modes. However, the majority of above-ground storage tanks in use have no annular chime due to a simplified design and/or have a degraded chime due to corrosion. This means that transducers cannot be mounted on the chime to assess structural health according to the present technology, and the market share of structural health monitoring of above-ground storage tank floors using ultrasonic guided wave is thus limited. Therefore, the present study investigates the potential of using the tank wall to bond the transducer instead of the tank annular chime. Both normal and shear type transducers were investigated numerically, and results were validated using a 4.1 m diameter above-ground storage tank. The study results show shear mode type transducers bonded to the tank wall can be used to assess the structural health of the above-ground tank floors using an ultrasonic guided wave. It is also shown that for the cases studied there is a 7.4 dB signal-to-noise ratio improvement at 45 kHz for the guided wave excitation on the tank wall using shear mode transducers.

  15. Structural Health Monitoring of Above-Ground Storage Tank Floors by Ultrasonic Guided Wave Excitation on the Tank Wall.

    Science.gov (United States)

    Lowe, Premesh S; Duan, Wenbo; Kanfoud, Jamil; Gan, Tat-Hean

    2017-11-04

    There is an increasing interest in using ultrasonic guided waves to assess the structural degradation of above-ground storage tank floors. This is a non-invasive and economically viable means of assessing structural degradation. Above-ground storage tank floors are ageing assets which need to be inspected periodically to avoid structural failure. At present, normal-stress type transducers are bonded to the tank annular chime to generate a force field in the thickness direction of the floor and excite fundamental symmetric and asymmetric Lamb modes. However, the majority of above-ground storage tanks in use have no annular chime due to a simplified design and/or have a degraded chime due to corrosion. This means that transducers cannot be mounted on the chime to assess structural health according to the present technology, and the market share of structural health monitoring of above-ground storage tank floors using ultrasonic guided wave is thus limited. Therefore, the present study investigates the potential of using the tank wall to bond the transducer instead of the tank annular chime. Both normal and shear type transducers were investigated numerically, and results were validated using a 4.1 m diameter above-ground storage tank. The study results show shear mode type transducers bonded to the tank wall can be used to assess the structural health of the above-ground tank floors using an ultrasonic guided wave. It is also shown that for the cases studied there is a 7.4 dB signal-to-noise ratio improvement at 45 kHz for the guided wave excitation on the tank wall using shear mode transducers.

  16. Large-Scale Wireless Temperature Monitoring System for Liquefied Petroleum Gas Storage Tanks

    OpenAIRE

    Fan, Guangwen; Shen, Yu; Hao, Xiaowei; Yuan, Zongming; Zhou, Zhi

    2015-01-01

    Temperature distribution is a critical indicator of the health condition for Liquefied Petroleum Gas (LPG) storage tanks. In this paper, we present a large-scale wireless temperature monitoring system to evaluate the safety of LPG storage tanks. The system includes wireless sensors networks, high temperature fiber-optic sensors, and monitoring software. Finally, a case study on real-world LPG storage tanks proves the feasibility of the system. The unique features of wireless transmission, au...

  17. Final report of the systems engineering technical advisory board for the Tank Waste Remediation Program

    International Nuclear Information System (INIS)

    Baranowski, F.P.; Goodlett, C.B.; Beard, S.J.; Duckworth, J.P.; Schneider, A.; Zahn, L.L.

    1993-03-01

    The Tank Waste Remediation System (TWRS) is one segment of the environmental restoration program at the Hanford site. The scope is to retrieve the contents of both the single shell and double shell tanks and process the wastes into forms acceptable for long term storage and/or permanent disposal. The quantity of radioactive waste in tanks is significantly larger and substantially more complex in composition than the radioactive waste stored in tanks at other DOE sites. The waste is stored in 149 single shell tanks and 28 double shell tanks. The waste was produced over a period from the mid 1940s to the present. The single shell tanks have exceeded their design life and are experiencing failures. The oldest of the double shell tanks are approaching their design life. Spar double shell tank waste volume is limited. The priorities in the Board's view are to manage safely the waste tank farms, accelerate emptying of waste tanks, provide spare tank capacity and assure a high degree of confidence in performance of the TWRS integrated program. At its present design capacity, the glass vitrification plant (HWVP) will require a period of about 15 years to empty the double shell tanks; the addition of the waste in single shell tanks adds another 100 years. There is an urgent need to initiate now a well focused and centralized development and engineering program on both larger glass melters and advanced separations processes that reduce radioactive constituents in the low-level waste (LLW). The Board presents its conclusions and has other suggestions for the management plan. The Board reviews planning schedules for accelerating the TWRS program

  18. Final report of the systems engineering technical advisory board for the Tank Waste Remediation Program

    Energy Technology Data Exchange (ETDEWEB)

    Baranowski, F.P.; Goodlett, C.B.; Beard, S.J.; Duckworth, J.P.; Schneider, A.; Zahn, L.L.

    1993-03-01

    The Tank Waste Remediation System (TWRS) is one segment of the environmental restoration program at the Hanford site. The scope is to retrieve the contents of both the single shell and double shell tanks and process the wastes into forms acceptable for long term storage and/or permanent disposal. The quantity of radioactive waste in tanks is significantly larger and substantially more complex in composition than the radioactive waste stored in tanks at other DOE sites. The waste is stored in 149 single shell tanks and 28 double shell tanks. The waste was produced over a period from the mid 1940s to the present. The single shell tanks have exceeded their design life and are experiencing failures. The oldest of the double shell tanks are approaching their design life. Spar double shell tank waste volume is limited. The priorities in the Board`s view are to manage safely the waste tank farms, accelerate emptying of waste tanks, provide spare tank capacity and assure a high degree of confidence in performance of the TWRS integrated program. At its present design capacity, the glass vitrification plant (HWVP) will require a period of about 15 years to empty the double shell tanks; the addition of the waste in single shell tanks adds another 100 years. There is an urgent need to initiate now a well focused and centralized development and engineering program on both larger glass melters and advanced separations processes that reduce radioactive constituents in the low-level waste (LLW). The Board presents its conclusions and has other suggestions for the management plan. The Board reviews planning schedules for accelerating the TWRS program.

  19. Tank waste remediation system dangerous waste training plan

    International Nuclear Information System (INIS)

    POHTO, R.E.

    1999-01-01

    This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by Lockheed Martin Hanford Corporation (LMHC) Tank Waste Remediation System (TWRS) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units operated by TWRS are: the Double-Shell Tank (DST) System (including 204-AR Waste Transfer Building), the 600 Area Purgewater Storage and the Effluent Treatment Facility. TSD Units undergoing closure are: the Single-Shell Tank (SST) System, 207-A South Retention Basin, and the 216-B-63 Trench

  20. Prevention of stress corrosion cracking in nuclear waste storage tanks

    International Nuclear Information System (INIS)

    Ondrejcin, R.S.

    1983-01-01

    At the Savannah River Plant, stress corrosion of carbon steel storage tanks containing alkaline nitrate radioactive waste is prevented by stress relief and specification of limits on waste composition and temperature. Actual cases of cracking have occurred in the primary steel shell of tanks designed and built before 1960 and were attributed to a combination of high residual stresses from fabrication welding and aggressiveness of fresh wastes from the reactor fuel reprocessing plants. The fresh wastes have the highest concentration of nitrate, which has been shown to be the cracking agent. Also, as the waste solutions age and are reduced in volume by evaporation of water, nitrite and hydroxide ions become more concentrated and inhibit stress corrosion. Thus, by providing a heel of aged evaporated waste in tanks that receive fresh wastes, concentrations of the inhibitor ions are maintained within specific ranges to protect against nitrate cracking. The concentration and temperature range limits to prevent cracking were determined by a series of statistically designed experiments

  1. A study of liquid storage tank seismic uplift behavior

    Energy Technology Data Exchange (ETDEWEB)

    Cambra, F.J.

    1983-01-01

    The earthquake response behavior of a 6 X 12 ft model cylindrical liquid storage tank was studied at the Richmond Field Station, Earthquake Engineering Research Center in the University of California, Berkeley earthquake simulator laboratory. This study included static tilt and dynamic shaking table tests using both a rigid mortar foundation as well as a flexible ''simulated soil'' rubber foundation. It is observed that the state-of-the-art mathematical representation of tank bottom plating using a one dimensional beam element with the formation of two plastic hinges, while neglecting both radial catenary tension and support foundation stiffness, poorly predicts the true displacements and stresses recorded in these experiments. There may exist serious implications for the adequacy of aseismic design regarding tank bottom plate rupture and wall buckling resistance. The development of an ''empirical tie element model'' is given which includes the consideration of catenary tension and foundation stiffness parameters. The purpose of this formulation is to arouse discussion leading to an improved treatment of this problem. It is not intended to supplement current practice.

  2. Large-Scale Wireless Temperature Monitoring System for Liquefied Petroleum Gas Storage Tanks.

    Science.gov (United States)

    Fan, Guangwen; Shen, Yu; Hao, Xiaowei; Yuan, Zongming; Zhou, Zhi

    2015-09-18

    Temperature distribution is a critical indicator of the health condition for Liquefied Petroleum Gas (LPG) storage tanks. In this paper, we present a large-scale wireless temperature monitoring system to evaluate the safety of LPG storage tanks. The system includes wireless sensors networks, high temperature fiber-optic sensors, and monitoring software. Finally, a case study on real-world LPG storage tanks proves the feasibility of the system. The unique features of wireless transmission, automatic data acquisition and management, local and remote access make the developed system a good alternative for temperature monitoring of LPG storage tanks in practical applications.

  3. Large-Scale Wireless Temperature Monitoring System for Liquefied Petroleum Gas Storage Tanks

    Directory of Open Access Journals (Sweden)

    Guangwen Fan

    2015-09-01

    Full Text Available Temperature distribution is a critical indicator of the health condition for Liquefied Petroleum Gas (LPG storage tanks. In this paper, we present a large-scale wireless temperature monitoring system to evaluate the safety of LPG storage tanks. The system includes wireless sensors networks, high temperature fiber-optic sensors, and monitoring software. Finally, a case study on real-world LPG storage tanks proves the feasibility of the system. The unique features of wireless transmission, automatic data acquisition and management, local and remote access make the developed system a good alternative for temperature monitoring of LPG storage tanks in practical applications.

  4. 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

  5. Device for sealing and shielding a nuclear fuel storage tank

    International Nuclear Information System (INIS)

    Masaki, Gengo.

    1975-01-01

    Object: To provide a shield device for opening and closing a great opening in a relay-storage-tank within a hot cell for temporarily storing a nuclear fuel, in which the device is simplified in construction and which can perform the opening and closing operation in simple, positive and quick manner. Structure: A biological shield is positioned upwardly of an opening of a nuclear fuel storage tank to render an actuator inoperative. A sealing plate, which is pivotally supported by a plurality of support rod devices from the biological shield for parallel movement with respect to the biological shield, comes in contact with a resilient seal disposed along the entire peripheral edge of the opening to form an air-tight seal therebetween. In order to release the opening, the actuator is first actuated and the end of the sealing plate is horizontally pressed by a piston rod thereof. Then, the sealing plate is moved along the line depicted by the end of the support rod in the support rod devices and as a consequence, the plate is moved away from the resilient seal in the peripheral edge of the opening. When a driving device is actuated to travel the plate along the aforesaid line while maintaining the condition as described, the biological device moves along the guide. (Kamimura, M.)

  6. 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

  7. Numerical model for the thermal behavior of thermocline storage tanks

    Science.gov (United States)

    Ehtiwesh, Ismael A. S.; Sousa, Antonio C. M.

    2017-10-01

    Energy storage is a critical factor in the advancement of solar thermal power systems for the sustained delivery of electricity. In addition, the incorporation of thermal energy storage into the operation of concentrated solar power systems (CSPs) offers the potential of delivering electricity without fossil-fuel backup even during peak demand, independent of weather conditions and daylight. Despite this potential, some areas of the design and performance of thermocline systems still require further attention for future incorporation in commercial CSPs, particularly, their operation and control. Therefore, the present study aims to develop a simple but efficient numerical model to allow the comprehensive analysis of thermocline storage systems aiming better understanding of their dynamic temperature response. The validation results, despite the simplifying assumptions of the numerical model, agree well with the experiments for the time evolution of the thermocline region. Three different cases are considered to test the versatility of the numerical model; for the particular type of a storage tank with top round impingement inlet, a simple analytical model was developed to take into consideration the increased turbulence level in the mixing region. The numerical predictions for the three cases are in general good agreement against the experimental results.

  8. Numerical model for the thermal behavior of thermocline storage tanks

    Science.gov (United States)

    Ehtiwesh, Ismael A. S.; Sousa, Antonio C. M.

    2018-03-01

    Energy storage is a critical factor in the advancement of solar thermal power systems for the sustained delivery of electricity. In addition, the incorporation of thermal energy storage into the operation of concentrated solar power systems (CSPs) offers the potential of delivering electricity without fossil-fuel backup even during peak demand, independent of weather conditions and daylight. Despite this potential, some areas of the design and performance of thermocline systems still require further attention for future incorporation in commercial CSPs, particularly, their operation and control. Therefore, the present study aims to develop a simple but efficient numerical model to allow the comprehensive analysis of thermocline storage systems aiming better understanding of their dynamic temperature response. The validation results, despite the simplifying assumptions of the numerical model, agree well with the experiments for the time evolution of the thermocline region. Three different cases are considered to test the versatility of the numerical model; for the particular type of a storage tank with top round impingement inlet, a simple analytical model was developed to take into consideration the increased turbulence level in the mixing region. The numerical predictions for the three cases are in general good agreement against the experimental results.

  9. Polymeric hydrogen diffusion barrier, high-pressure storage tank so equipped, method of fabricating a storage tank and method of preventing hydrogen diffusion

    Science.gov (United States)

    Lessing, Paul A [Idaho Falls, ID

    2008-07-22

    An electrochemically active hydrogen diffusion barrier which comprises an anode layer, a cathode layer, and an intermediate electrolyte layer, which is conductive to protons and substantially impermeable to hydrogen. A catalytic metal present in or adjacent to the anode layer catalyzes an electrochemical reaction that converts any hydrogen that diffuses through the electrolyte layer to protons and electrons. The protons and electrons are transported to the cathode layer and reacted to form hydrogen. The hydrogen diffusion barrier is applied to a polymeric substrate used in a storage tank to store hydrogen under high pressure. A storage tank equipped with the electrochemically active hydrogen diffusion barrier, a method of fabricating the storage tank, and a method of preventing hydrogen from diffusing out of a storage tank are also disclosed.

  10. Polymeric hydrogen diffusion barrier, high-pressure storage tank so equipped, method of fabricating a storage tank and method of preventing hydrogen diffusion

    Science.gov (United States)

    Lessing, Paul A.

    2004-09-07

    An electrochemically active hydrogen diffusion barrier which comprises an anode layer, a cathode layer, and an intermediate electrolyte layer, which is conductive to protons and substantially impermeable to hydrogen. A catalytic metal present in or adjacent to the anode layer catalyzes an electrochemical reaction that converts any hydrogen that diffuses through the electrolyte layer to protons and electrons. The protons and electrons are transported to the cathode layer and reacted to form hydrogen. The hydrogen diffusion barrier is applied to a polymeric substrate used in a storage tank to store hydrogen under high pressure. A storage tank equipped with the electrochemically active hydrogen diffusion barrier, a method of fabricating the storage tank, and a method of preventing hydrogen from diffusing out of a storage tank are also disclosed.

  11. 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.”

  12. Melton Valley Storage Tanks Capacity Increase Project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-04-01

    The US Department of Energy (DOE) proposes to construct and maintain additional storage capacity at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee, for liquid low-level radioactive waste (LLLW). New capacity would be provided by a facility partitioned into six individual tank vaults containing one 100,000 gallon LLLW storage tank each. The storage tanks would be located within the existing Melton Valley Storage Tank (MVST) facility. This action would require the extension of a potable water line approximately one mile from the High Flux Isotope Reactor (HFIR) area to the proposed site to provide the necessary potable water for the facility including fire protection. Alternatives considered include no-action, cease generation, storage at other ORR storage facilities, source treatment, pretreatment, and storage at other DOE facilities

  13. Melton Valley Storage Tanks Capacity Increase Project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    The US Department of Energy (DOE) proposes to construct and maintain additional storage capacity at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee, for liquid low-level radioactive waste (LLLW). New capacity would be provided by a facility partitioned into six individual tank vaults containing one 100,000 gallon LLLW storage tank each. The storage tanks would be located within the existing Melton Valley Storage Tank (MVST) facility. This action would require the extension of a potable water line approximately one mile from the High Flux Isotope Reactor (HFIR) area to the proposed site to provide the necessary potable water for the facility including fire protection. Alternatives considered include no-action, cease generation, storage at other ORR storage facilities, source treatment, pretreatment, and storage at other DOE facilities.

  14. Feasibility report on criticality issues associated with storage of K Basin sludge in tanks farms

    Energy Technology Data Exchange (ETDEWEB)

    Vail, T.S.

    1997-05-29

    This feasibility study provides the technical justification for conclusions about K Basin sludge storage options. The conclusions, solely based on criticality safety considerations, depend on the treatment of the sludge. The two primary conclusions are, (1) untreated sludge must be stored in a critically safe storage tank, and (2) treated sludge (dissolution, precipitation and added neutron absorbers) can be stored in a standard Double Contained Receiver Tank (DCRT) or 241-AW-105 without future restrictions on tank operations from a criticality safety perspective.

  15. 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.

  16. 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

  17. Case study of successful weld repair of a storage tank

    International Nuclear Information System (INIS)

    Sinha, S; Ambrose, S.

    2012-01-01

    Weld repairs or modifications may be required for existing welded structures or components as a result of service damage or failure, or as a result of wear, corrosion or changed service condition. A case study of a repair to a large oil storage tank which failed in Australia by brittle fracture during modification is described to demonstrate the application of basic principles and good practice needed to produce successful repairs/modifications. Prevention of brittle fracture in welded steel structures requires consideration of the toughness at minimum temperature of the weld, the HAZ and the base material itself, applied and residual stress and 'equivalent crack' size. This case shows the importance of residual stress, repair planning and the care needed with old steels.

  18. Mixed waste removal from a hazardous waste storage tank

    International Nuclear Information System (INIS)

    Geber, K.R.

    1993-01-01

    The spent fuel transfer canal at the Oak Ridge Graphite Reactor was found to be leaking 400 gallons of water per day into the surrounding soil. Sampling of the sediment layer on the floor of the canal to determine the environmental impact of the leak identified significant radiological contamination and elevated levels of cadmium and lead which are hazardous under the Resource Conservation and Recovery Act (RCRA). Under RCRA regulations and Rules of Tennessee Department of Environment and Conservation, the canal was considered a hazardous waste storage tank. This paper describes elements of the radiological control program established in support of a fast-track RCRA closure plan that involved underwater mapping of the radiation fields, vacuuming, and ultra-filtration techniques that were successfully used to remove the mixed waste sediments and close the canal in a method compliant with state and federal regulations

  19. Hole in the storage tank. Causes of failures and outline of alternative means of insulation. [Fuel storage

    Energy Technology Data Exchange (ETDEWEB)

    Krause, G. (Vereinigung der Technischen Ueberwachungsvereine e.V., Essen (Germany, F.R.). Abt. Tankanlagen)

    1980-07-01

    A few years ago, when single-walled steel tanks were provided with inner plastic linings for fuel storage purposes, it turned out that an average 25 to 30% of the tanks were perforated, due to previous corrosion, when sanded. The usual kind of external protection of these tanks to this day has been the enclosure of the tank wall in several layers of bitumen-impregnated fabric. However, in practice this type of insulation has been found to be extremely sensitive to faulty treatment and to influences of the weather before being put in the ground. Also the low chemical stability to the coating are further disadvantages. Coating with epoxy resin is a good and reliable external insulation of underground storage tanks, meeting nearly all requirements of these tanks and being only slightly more expensive than the former system.

  20. Turning the Corner on Hanford Tank Waste Cleanup-From Safe Storage to Closure

    International Nuclear Information System (INIS)

    Boston, H. L.; Cruz, E. J.; Coleman, S. 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 the disposition of 204,000 cubic meters (54 million gallons) of high-level radioactive waste that have accumulated in large underground tanks at the Hanford Site since 1944. ORP continues to make good progress on improving the capability to treat Hanford tank waste. Design of the waste vitrification facilities is proceeding well and construction will begin within the next year. Progress is also being made in reducing risk to the worker and the environment from the waste currently stored in the tank farms. Removal of liquids from single-shell tanks (SSTs) is on schedule and we will begin removing solids (salt cake) from a tank (241-U-107) in 2002. There is a sound technical foundation for the waste vitrification facilities. These initial facilities will be capable of treating (vitrifying) the bulk of Hanford tank waste and are the corners tone of the clean-up strategy. ORP recognizes that as the near-term work is performed, it is vital that there be an equally strong and defensible plan for completing the mission. ORP is proceeding on a three-pronged approach for moving the mission forward. First, ORP will continue to work aggressively to complete the waste vitrification facilities. ORP intends to provide the most capable and robust facilities to maximize the amount of waste treated by these initial facilities by 2028 (regulatory commitment for completion of waste treatment). Second, and in parallel with completing the waste vitrification facilities, ORP is beginning to consider how best to match the hazard of the waste to the disposal strategy. The final piece of our strategy is to continue to move forward with actions to reduce risk in the tank farms and complete cleanup

  1. Single bi-temperature thermal storage tank for application in solar thermal plant

    Energy Technology Data Exchange (ETDEWEB)

    Litwin, Robert Zachary; Wait, David; Lancet, Robert T.

    2017-05-23

    Thermocline storage tanks for solar power systems are disclosed. A thermocline region is provided between hot and cold storage regions of a fluid within the storage tank cavity. One example storage tank includes spaced apart baffles fixed relative to the tank and arranged within the thermocline region to substantially physically separate the cavity into hot and cold storage regions. In another example, a flexible baffle separated the hot and cold storage regions and deflects as the thermocline region shifts to accommodate changing hot and cold volumes. In yet another example, a controller is configured to move a baffle within the thermocline region in response to flow rates from hot and cold pumps, which are used to pump the fluid.

  2. Improvement of floating roof tanks for liquids, more particularly for storage tanks used in nuclear power plants

    International Nuclear Information System (INIS)

    Barbillat, C.

    1986-01-01

    The invention concerns floating roof tanks for liquids, comprising a cylindrical wall, a flexible membrane sealing the circumference of the roof to the wall. According to the invention, means permit the counter pressure liquid to escape when the roof is raised the counter pressure liquid being in the space defined between the membrane and the wall. These means are at the upper part of the tank. The present invention can be applied more particularly to storage tanks ensuring the reserve of degased water of a nuclear reactor primary coolant circuit [fr

  3. Improvement of floating roof tanks for liquids, more particularly for storage tanks used in nuclear power plants

    International Nuclear Information System (INIS)

    Barbillat, C.

    1986-01-01

    The invention deals with floating roof tanks for liquids, comprising a cylindrical wall, a floating roof and a flexible membrane sealing the roof circumference to the wall. The present tank has a protection against a filling excess when the roof is at its upper position, an overflow pipe on the outer face of the wall with a U-shaped portion at its upper end at the maximal desired reservoir filling level. The invention can be applied to the storage tanks ensuring the reserve of degased water for a primary coolant circuit of a nuclear reactor [fr

  4. Improvement of floating roof tanks for liquids, more particularly to storage tanks used in nuclear power plants

    International Nuclear Information System (INIS)

    Barbillat, C.

    1986-01-01

    The invention deals with floating roof tanks for liquids, comprising a cylindrical wall, a flexible membrane sealing the circumference of the roof to the wall. The present tank has a protection against an overpressure and/or depression, when the roof is at its lower position, or jammed at an intermediate position a pressure equalizing tube mounted on the roof to communicate its interior with the reservoir liquid sized to maintain a predetermined pressure. The invention can be applied to storage tanks ensuring the reserve of degased water for a nuclear reactor primary coolant circuit [fr

  5. 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

  6. Technical Assessment of Compressed Hydrogen Storage Tank Systems for Automotive Applications

    Energy Technology Data Exchange (ETDEWEB)

    Hua, Thanh [Argonne National Lab. (ANL), Argonne, IL (United States); Ahluwalia, Rajesh [Argonne National Lab. (ANL), Argonne, IL (United States); Peng, J. -K [Argonne National Lab. (ANL), Argonne, IL (United States); Kromer, Matt [TIAX LLC, Lexington, MA (United States); Lasher, Stephen [TIAX LLC, Lexington, MA (United States); McKenney, Kurtis [TIAX LLC, Lexington, MA (United States); Law, Karen [TIAX LLC, Lexington, MA (United States); Sinha, Jayanti [TIAX LLC, Lexington, MA (United States)

    2010-09-01

    This technical report describes DOE's assessment of the performance and cost of compressed hydrogen storage tank systems for automotive applications. The on-board performance (by Argonne National Lab) and high-volume manufacturing cost (by TIAX LLC) were estimated for compressed hydrogen storage tanks. The results were compared to DOE's 2010, 2015, and ultimate full fleet hydrogen storage targets. The Well-to-Tank (WTT) efficiency as well as the off-board performance and cost of delivering compressed hydrogen were also documented in the report.

  7. EVALUATION OF BEST AVAILABLE CONTROL TECHNOLOGY FOR TOXICS (TBACT) DOUBLE SHELL TANK FARMS PRIMARY VENTILATION SYSTEMS SUPPORTING WASTE TRANSFER OPERATIONS

    International Nuclear Information System (INIS)

    Haas, C.C.; Kovach, J.L.; Kelly, S.E.; Turner, D.A.

    2010-01-01

    This report is an evaluation of Best Available Control Technology for Toxics (tBACT) for installation and operation of the Hanford double shell (DST) tank primary ventilation systems. The DST primary ventilation systems are being modified to support Hanford's waste retrieval, mixing, and delivery of single shell tank (SST) and DST waste through the DST storage system to the Waste Treatment and Immobilization Plant (WTP).

  8. EVALUATION OF BEST AVAILABLE CONTROL TECHNOLOGY FOR TOXICS -TBACT- DOUBLE SHELL TANK FARMS PRIMARY VENTILATION SYSTEMS SUPPORTING WASTE TRANSFER OPERATIONS

    Energy Technology Data Exchange (ETDEWEB)

    HAAS CC; KOVACH JL; KELLY SE; TURNER DA

    2010-06-24

    This report is an evaluation of Best Available Control Technology for Toxics (tBACT) for installation and operation of the Hanford double shell (DST) tank primary ventilation systems. The DST primary ventilation systems are being modified to support Hanford's waste retrieval, mixing, and delivery of single shell tank (SST) and DST waste through the DST storage system to the Waste Treatment and Immobilizaiton Plant (WTP).

  9. EVALUATION OF BEST AVAILABLE CONTROL TECHNOLOGY FOR TOXICS (TBACT) DOUBLE SHELL TANK FARMS PRIMARY VENTILATION SYSTEM SUPPORTING WASTE TRANSFER OPERATIONS

    Energy Technology Data Exchange (ETDEWEB)

    KELLY SE; HAASS CC; KOVACH JL; TURNER DA

    2010-06-03

    This report is an evaluation of Best Available Control Technology for Toxics (tBACT) for installation and operation of the Hanford double shell (DST) tank primary ventilation systems. The DST primary ventilation systems are being modified to support Hanford's waste retrieval, mixing, and delivery of single shell tank (SST) and DST waste throught the DST storage system to the Waste Treatment and Immobilization Plant (WTP).

  10. EVALUATION OF BEST AVAILABLE CONTROL TECHNOLOGY FOR TOXICS (TBACT) DOUBLE SHELL TANK FARMS PRIMARY VENTILATION SYSTEM SUPPORTING WASTE TRANSFER OPERATIONS

    International Nuclear Information System (INIS)

    Kelly, S.E.; Haass, C.C.; Kovach, J.L.; Turner, D.A.

    2010-01-01

    This report is an evaluation of Best Available Control Technology for Toxics (tBACT) for installation and operation of the Hanford double shell (DST) tank primary ventilation systems. The DST primary ventilation systems are being modified to support Hanford's waste retrieval, mixing, and delivery of single shell tank (SST) and DST waste through out the DST storage system to the Waste Treatment and Immobilization Plant (WTP).

  11. A STUDY OF CORROSION AND STRESS CORROSION CRACKING OF CARBON STEEL NUCLEAR WASTE STORAGE TANKS

    International Nuclear Information System (INIS)

    BOOMER, K.D.

    2007-01-01

    The Hanford reservation Tank Farms in Washington State has 177 underground storage tanks that contain approximately 50 million gallons of liquid legacy radioactive waste from cold war plutonium production. These tanks will continue to store waste until it is treated and disposed. These nuclear wastes were converted to highly alkaline pH wastes to protect the carbon steel storage tanks from corrosion. However, the carbon steel is still susceptible to localized corrosion and stress corrosion cracking. The waste chemistry varies from tank to tank, and contains various combinations of hydroxide, nitrate, nitrite, chloride, carbonate, aluminate and other species. The effect of each of these species and any synergistic effects on localized corrosion and stress corrosion cracking of carbon steel have been investigated with electrochemical polarization, slow strain rate, and crack growth rate testing. The effect of solution chemistry, pH, temperature and applied potential are all considered and their role in the corrosion behavior will be discussed

  12. 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

  13. DESIGN OF LIQUID-STORAGE TANK: RESULTS OF SOFTWARE MODELING VS CALCULATIONS ACCORDING TO EUROCODE

    Directory of Open Access Journals (Sweden)

    Matko Gulin

    2017-01-01

    Full Text Available The objective of this article is to show the design process of a liquid-storage tank shell according to Eurocode and compare the results obtained using the norms with those from a finite element method (FEM analysis. The calculations were performed for an aboveground vertical steel water-storage tank with a variable thickness wall and stiffening ring on top. First, the types of liquid storage tanks are briefly explained. Second, the given tank is described. Third, an analysis of the tank wall according to the Eurocode was carried out. The FEM analysis was performed using the Scia Engineer ver. 17 software. Finally, all the results are presented in tables and compared.

  14. Small-Scale Metal Tanks for High Pressure Storage of Fluids

    Science.gov (United States)

    London, Adam (Inventor)

    2016-01-01

    Small scale metal tanks for high-pressure storage of fluids having tank factors of more than 5000 meters and volumes of ten cubic inches or less featuring arrays of interconnected internal chambers having at least inner walls thinner than gage limitations allow. The chambers may be arranged as multiple internal independent vessels. Walls of chambers that are also portions of external tank walls may be arcuate on the internal and/or external surfaces, including domed. The tanks may be shaped adaptively and/or conformally to an application, including, for example, having one or more flat outer walls and/or having an annular shape. The tanks may have dual-purpose inlet/outlet conduits of may have separate inlet and outlet conduits. The tanks are made by fusion bonding etched metal foil layers patterned from slices of a CAD model of the tank. The fusion bonded foil stack may be further machined.

  15. Ferrocyanide tank waste stability

    International Nuclear Information System (INIS)

    Fowler, K.D.

    1993-01-01

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

  16. EVALUATION OF VOLUMETRIC LEAK DETECTION METHODS USED IN UNDERGROUND STORAGE TANKS

    Science.gov (United States)

    In the spring and summer of 1987, the United States Environmental Protection Agency (EPA) evaluated the performance of 25 commercially available volumetric test methods for the detection of small leaks in underground storage tanks containing gasoline. Performance was estimated by...

  17. 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...

  18. Secondary Containment for Underground Storage Tank Systems - 2005 Energy Policy Act

    Science.gov (United States)

    These grant guidelines implement the secondary containment provision in Section 9003(i)(1) of the Solid Waste Disposal Act, enacted by the Underground Storage Tank Compliance Act, part of the Energy Policy Act of 2005.

  19. Numerical simulation on heat transfer characteristics of the storage tank for concentrating solar power plant

    Directory of Open Access Journals (Sweden)

    Qianjun Mao

    2016-06-01

    Full Text Available Concentrating solar power plant coupling with energy storage is a new and emerging technology, which can solve two issues, that is, low flux density and intermittent of solar energy. Heat transfer characteristics of the storage tank in this system have a key effect on the system’s efficiency and cost. In this article, the heat transfer performance of a phase change thermal storage tank has been proposed, and the temperature distribution and liquid fraction of phase change material in the tank has numerically been investigated. The results show that the temperature increases with the increasing charge time. The results also show that there is a phase change process at the charge time of 200 min, and no phase change for the charge time of 250 and 300 min. The results of this article can provide a reference for future design and optimal operation of the storage tank in concentrating solar power plant.

  20. Sampling study in milk storage tanks by INAA

    International Nuclear Information System (INIS)

    Santos, L.G.C.; Nadai Fernandes de, E.A.; Bacchi, M.A.; Tagliaferro, F.S.

    2008-01-01

    This study investigated the representativeness of samples for assessing chemical elements in milk bulk tanks. Milk samples were collected from a closed tank in a dairy plant and from an open top tank in a dairy farm. Samples were analyzed for chemical elements by instrumental neutron activation analysis (INAA). For both experiments, Br, Ca, Cs, K, Na, Rb and Zn did not present significant differences between samples thereby indicating the appropriateness of the sampling procedure adopted to evaluate the analytes of interest. (author)

  1. 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

  2. Storage tank materials for biodiesel blends; the analysis of fuel property changes

    Directory of Open Access Journals (Sweden)

    Nurul Komariah Leily

    2017-01-01

    Full Text Available Fuel stability is one of major problem in biodiesel application. Some of the physical properties of biodiesel are commonly changed during storage. The change in physico-chemical properties is strongly correlated to the stability of the fuel. This study is objected to observe the potential materials for biodiesel storage. The test was conducted in three kinds of tank materials, such as glass, HDPE, and stainless steel. The fuel properties are monitored in 12 weeks, while the sample was analyzed every week. Biodiesel used is palm oil based. The storage tanks were placed in a confined indoor space with range of temperature 27–34 °C. The relative humidity and sunshine duration on the location was also evaluated. The observed properties of the fuel blends were density, viscosity and water content. During 12 weeks of storage, the average density of B20 was changed very slightly in all tanks, while the viscosity was tend to increase sharply, especially in polimerics tank. Water content of B20 was increased by the increase of storage time especially in HDPE tank. In short period of storage, the biodiesel blends is found more stable in glass tank due to its versatility to prohibit oxidation, degradation, and its chemical resistance.

  3. Refurbishment and retrofitting of SF6 gas storage tanks of the pelletron accelerator

    International Nuclear Information System (INIS)

    Reddy, G.R.; Datar, V.M.; Parulekar, Y.M.

    2015-01-01

    The BARC-TIFR Pelletron Accelerator Facility has completed more than twenty six years of successful round-the-clock operation, serving diverse users from institutions within and outside DAE. The main accelerating structure and associated subsystems are housed in the accelerator tank under SF 6 gas medium. During maintenance of the accelerator, the SF 6 gas present in the accelerator tank is transferred in the four storage tanks located on the terrace of the building open to outside environment. These four storage tanks (with ∼ 1/4th of the main tank volume each) are ∼ 4.27 m in diameter and ∼ 10 m in height each and are supported on RCC ring beams which are monolithically connected with the RCC structure below. Over the years, the anchor bolts and the base plates of support structure of storage tanks were found corroded and the foundation RCC ring beam indicated a few corrosion cracks. Health assessment of relevant structures and components were carried out. Considering the limitations of existing anchorage and also giving due considerations for reparability and replaceability, a new anchorage system was designed. The entire refurbishment and retrofitting works pertaining to the four SF 6 gas storage tanks was executed in a time bound manner to comply with the then PASC (Particle Accelerator Safety Committee) recommendations successfully, without disrupting the operations of the round-the-clock running Pelletron Accelerator facility. In addition, the thickness measurements for the storage tanks were performed. The relief valves and rupture disc assemblies across the storage tanks were replaced and reinstalled after introducing appropriate manual valves as suggested by the PASC. A new test set up was fabricated to perform pneumatic testing at the recommended pressure off-line for these relief valves and rupture disc assemblies prior to reinstallation. This paper describes the comprehensive rehabilitation and retrofitting procedures that were carried out at the

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  5. 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

  6. 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

  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. Regional scale analysis for the design of storage tanks for domestic rainwater harvesting systems.

    Science.gov (United States)

    Campisano, A; Modica, C

    2012-01-01

    A regional scale analysis for the design of storage tanks for domestic rain water harvesting systems is presented. The analysis is based on the daily water balance simulation of the storage tank by the yield-after-spillage algorithm as tank release rule. Water balances are applied to 17 rainfall gauging stations in Sicily (Italy). Compared with literature existing methods, a novel dimensionless parameter is proposed to better describe the intra-annual character of the rainfall patterns. As a result, easy-to-use regional regressive models to evaluate the water saving performance and the overflow discharges from the tank are provided along with a stepwise procedure for practical application. The regional models demonstrate good fits between model predictions and simulated values of both water savings and overflows from the tank.

  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. 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

  11. Energy-Saving Analysis of Solar Heating System with PCM Storage Tank

    Directory of Open Access Journals (Sweden)

    Juan Zhao

    2018-01-01

    Full Text Available A solar heating system (SHS with a phase change material (PCM thermal storage tank is proposed with the view that traditional heat water storage tanks present several problems including large space requirements, significant heat loss and unstable system performance. An entire heating season (November–March is selected as the research period on the basis of numerical models of the SHS-PCM. In addition, taking a public building in Lhasa as the object, the heating conditions, contribution rate of solar energy, and overall energy-saving capability provided by the heating system are analyzed under different PCM storage tanks and different terminal forms. The results show that an SHS with a PCM tank provides a 34% increase in energy saving capability compared to an ordinary water tank heating system. It is suggested that the design selection parameters of the PCM storage tank should specify a daily heat storage capacity that satisfies 70~80% of the entire heating season. A floor radiant system with supply/return water temperatures of 40/35 °C provides the optimal operation and the largest energy saving capability.

  12. Tank 241-U-203: Tank Characterization Plan

    International Nuclear Information System (INIS)

    Sathyanarayana, P.

    1995-01-01

    The revised Federal Facility Agreement and Consent Order states that a tank characterization plan will be developed for each double-shell tank and single-shell tank using the data quality objective process. The plans are intended to allow users and regulators to ensure their needs will be met and resources are devoted to gaining only necessary information. This document satisfies that requirement for Tank 241-U-203 sampling activities

  13. 40 CFR 61.132 - Standard: Process vessels, storage tanks, and tar-intercepting sumps.

    Science.gov (United States)

    2010-07-01

    ... process vessel, tar storage tank, and tar-intercepting sump to the gas collection system, gas distribution system, or other enclosed point in the by-product recovery process where the benzene in the gas will be... 40 Protection of Environment 8 2010-07-01 2010-07-01 false Standard: Process vessels, storage...

  14. Innovative tank emptying system for the retrieval of salt, sludge and IX resins from storage tanks of NPPs

    International Nuclear Information System (INIS)

    Karl Froschauer; Holger Witing; Bernhard Christ

    2006-01-01

    RWE NUKEM recently developed a new Tank Emptying System (TESY) for the extraction of stored radioactive boric acid/borate salt blocks, sludge and IX resin from NPP stainless steel tanks of several hundred cubic meters content in Russia. RWE NUKEM has chosen the emptying concept consisting of a tracked submersible vehicle ('Crawler'), with jet nozzles for solution, agitation and fluidization, and a suction head to pick up the generated solution or suspension respectively. With the employment of RWE NUKEM's TESY system, spent radioactive salt deposits, ion-exchange resins and sludge, can be emptied and transferred out of the tank. The sediment, crystallized and settled during storage, will be agitated with increased temperature and suitable pH value and then picked up in form of a suspension or solution directly at the point of mobilization. This new Tank Emptying System concept enables efficiently to retrieve stored salt and other sediment waste, reduces operating time, safes cost for spare parts, increases the safety of operation and minimizes radiation exposure to personnel. All emptying tasks are performed remotely from a panel board and TV monitor located in a central control room. The TESY system consists of the following main components: glove box, crawler, submersible pump, heater, TV camera and spot light, control panel and monitor, water separation and feed unit, sodium hydroxide dosing unit. The system is specially requested for the removal of more than 2,500 cubic meter salt solution generated from the dissolution of some 300 cubic meter crystallized salt deposit per tank and per year. The TESY system is able to dissolve efficiently the salts and retrieve solutions and other liquefied suspensions. TESY is adaptable to all liquid waste storage facilities and especially deployable for tanks with limited access openings (<550 mm)

  15. Underground storage tank 253-D1U1 Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mancieri, S.; Giuntoli, N.

    1993-09-01

    This report is a closure plan for a diesel fuel tank at the Lawrence Livermore National Laboratory. Included are maps of the site, work plans, and personnel information regarding training and qualification.

  16. Effect of tank diameter on thermal behavior of gasoline and diesel storage tanks fires.

    Science.gov (United States)

    Leite, Ricardo Machado; Centeno, Felipe Roman

    2018-01-15

    Studies on fire behavior are extremely important as they contribute in a firefighting situation or even to avoid such hazard. Experimental studies of fire in real scale are unfeasible, implying that reduced-scale experiments must be performed, and results extrapolated to the range of interest. This research aims to experimentally study the fire behavior in tanks of 0.04m, 0.20m, 0.40m, 0.80m and 4.28m diameter, burning regular gasoline or diesel oil S-500. The following parameters were here obtained: burning rates, burning velocities, heat release rates, flame heights, and temperature distributions adjacent to the tank. Such parameters were obtained for each tank diameter with the purpose of correlating the results and understanding the relationship of each parameter for the different geometrical scale of the tanks. Asymptotic results for larger tanks were found as (regular gasoline and diesel oil S-500, respectively): burning rates 0.050kg/(m 2 s) and 0.031kg/(m 2 s), burning velocities 4.0mm/min and 2.5mm/min, heat release rates per unit area 2200kW/m 2 and 1500kW/m 2 , normalized averaged flame heights (H i /D, where H i is the average flame height, D is the tank diameter) 0.9 and 0.8. Maximum temperatures for gasoline pools were higher than for diesel oil pools, and temperature gradients close to the tanks were also higher for the former fuel. The behavior of the maximum temperature was correlated as a function of the tank diameter, the heat release rate of each fuel and the dimensionless distance from the tank. Copyright © 2017 Elsevier B.V. All rights reserved.

  17. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1994-07-01

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ''Safety Measures for Waste Tanks at Hanford Nuclear Reservation,'' of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues

  18. Modeling and analysis of ORNL horizontal storage tank mobilization and mixing

    International Nuclear Information System (INIS)

    Mahoney, L.A.; Terrones, G.; Eyler, L.L.

    1994-06-01

    The retrieval and treatment of radioactive sludges that are stored in tanks constitute a prevalent problem at several US Department of Energy sites. The tanks typically contain a settled sludge layer with non-Newtonian rheological characteristics covered by a layer of supernatant. The first step in retrieval is the mobilization and mixing of the supernatant and sludge in the storage tanks. Submerged jets have been proposed to achieve sludge mobilization in tanks, including the 189 m 3 (50,000 gallon) Melton Valley Storage tanks (MVST) at Oak Ridge National Laboratory (ORNL) and the planned 378 m 3 (100,000 gallon) tanks being designed as part of the MVST Capacity Increase Project (MVST-CIP). This report focuses on the modeling of mixing and mobilization in horizontal cylindrical tanks like those of the MVST design using submerged, recirculating liquid jets. The computer modeling of the mobilization and mixing processes uses the TEMPEST computational fluid dynamics program (Trend and Eyler 1992). The goals of the simulations are to determine under what conditions sludge mobilization using submerged liquid jets is feasible in tanks of this configuration, and to estimate mixing times required to approach homogeneity of the contents

  19. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

  20. Entropy generation minimization for the sloshing phenomenon in half-full elliptical storage tanks

    Science.gov (United States)

    Saghi, Hassan

    2018-02-01

    In this paper, the entropy generation in the sloshing phenomenon was obtained in elliptical storage tanks and the optimum geometry of tank was suggested. To do this, a numerical model was developed to simulate the sloshing phenomenon by using coupled Reynolds-Averaged Navier-Stokes (RANS) solver and the Volume-of-Fluid (VOF) method. The RANS equations were discretized and solved using the staggered grid finite difference and SMAC methods, and the available data were used for the model validation. Some parameters consisting of maximum free surface displacement (MFSD), maximum horizontal force exerted on the tank perimeter (MHF), tank perimeter (TP), and total entropy generation (Sgen) were introduced as design criteria for elliptical storage tanks. The entropy generation distribution provides designers with useful information about the causes of the energy loss. In this step, horizontal periodic sway motions as X =amsin(ωt) were applied to elliptical storage tanks with different aspect ratios namely ratios of large diameter to small diameter of elliptical storage tank (AR). Then, the effect of am and ω was studied on the results. The results show that the relation between MFSD and MHF is almost linear relative to the sway motion amplitude. Moreover, the results show that an increase in the AR causes a decrease in the MFSD and MHF. The results, also, show that the relation between MFSD and MHF is nonlinear relative to the sway motion angular frequency. Furthermore, the results show that an increase in the AR causes that the relation between MFSD and MHF becomes linear relative to the sway motion angular frequency. In addition, MFSD and MHF were minimized in a sway motion with a 7 rad/s angular frequency. Finally, the results show that the elliptical storage tank with AR =1.2-1.4 is the optimum section.

  1. Variable friction pendulum system for seismic isolation of liquid storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Panchal, V.R. [Department of Civil Engineering, Indian Institute of Technology Bombay, Powai, Mumbai 400076 (India); Jangid, R.S. [Department of Civil Engineering, Indian Institute of Technology Bombay, Powai, Mumbai 400076 (India)], E-mail: rsjangid@civil.iitb.ac.in

    2008-06-15

    Earthquake response of liquid storage steel tanks isolated with variable friction pendulum system (VFPS) is investigated under normal component of six recorded near-fault ground motions. The continuous liquid mass of the tank is modeled as lumped masses known as sloshing mass, impulsive mass and rigid mass. The corresponding stiffness constants associated with these lumped masses are worked out depending upon the properties of the tank wall and liquid mass. The governing equations of motion of the tanks isolated with variable friction pendulum system are derived and solved by Newmark's step-by-step method assuming linear variation of acceleration over small time interval. In order to verify the effectiveness of the VFPS in tanks, the seismic response of tanks isolated with VFPS is compared with that of the same tanks isolated using the conventional friction pendulum system (FPS). Furthermore, a parametric study is also carried out to critically examine the behaviour of tanks isolated with VFPS. The various important parameters considered are the tank aspect ratio, the isolation period and initial time period of the VFPS. In addition, the seismic response of tanks isolated with VFPS under trigonometric cycloidal pulses is also investigated. From these investigations, it is concluded that with the installation of VFPS in tanks, the seismic response of tanks during near-fault ground motions can be controlled within a desirable range. Finally, it is also observed that the response of tanks isolated with VFPS under the near-fault ground motions and trigonometric cycloidal pulses matches well only when the isolation period reaches high values.

  2. Polymer/Silicate Nanocomposites Used to Manufacture Gas Storage Tanks With Reduced Permeability

    Science.gov (United States)

    Campbell, Sandi G.; Johnston, Chris

    2004-01-01

    Over the past decade, there has been considerable research in the area of polymer-layered silicate nanocomposites. This research has shown that the dispersion of small amounts of an organically modified layered silicate improves the polymer strength, modulus, thermal stability, and barrier properties. There have been several reports on the dispersion of layered silicates in an epoxy matrix. Potential enhancements to the barrier properties of epoxy/silicate nanocomposites make this material attractive for low permeability tankage. Polymer matrix composites (PMCs) have several advantages for cryogenic storage tanks. They are lightweight, strong, and stiff; therefore, a smaller fraction of a vehicle's potential payload capacity is used for propellant storage. Unfortunately, the resins typically used to make PMC tanks have higher gas permeability than metals. This can lead to hydrogen loss through the body of the tank instead of just at welds and fittings. One approach to eliminate this problem is to build composite tanks with thin metal liners. However, although these tanks provide good permeability performance, they suffer from a substantial mismatch in the coefficient of thermal expansion, which can lead to failure of the bond between the liner and the body of the tank. Both problems could be addressed with polymersilicate nanocomposites, which exhibit reduced hydrogen permeability, making them potential candidates for linerless PMC tanks. Through collaboration with Northrop Grumman and Michigan State University, nanocomposite test tanks were manufactured for the NASA Glenn Research Center, and the helium permeability was measured. An organically modified silicate was prepared at Michigan State University and dispersed in an epoxy matrix (EPON 826/JeffamineD230). The epoxy/silicate nanocomposites contained either 0 or 5 wt% of the organically modified silicate. The tanks were made by filament winding carbon fibers with the nanocomposite resin. Helium permeability

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

    Energy Technology Data Exchange (ETDEWEB)

    Bitz, D.A. [Independent Consultant, Kirkland, WA (United States); Berry, D.L. [Sandia National Labs., Albuquerque, NM (United States); Jardine, L.J. [Lawrence Livermore National Lab., CA (United States)

    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. 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

  5. Analysis on engineering application of CNP1000 in-containment refueling water storage tank

    International Nuclear Information System (INIS)

    Wang Bin; Wang Yong; Qiu Jian; Weng Minghui

    2005-01-01

    Based on the basic design of CNP1000 (three loops), which is self-reliance designed by China National Nuclear Cooperation, and investigation results from abroad advanced nuclear power plant design of In-containment Refueling Water Storage tank, this paper describe the system flowsheet, functional requirements, structural design and piping arrangement about In-containment Refueling Water Storage Tank. The design takes the lower structural space as the IRWST. Four areas are configured to meet the diverse functional requirements, including depressurization area, water collection area, safety injection and/or containment spray suction area, TSP storage area / reactor cavity flooding holdup tank. Also the paper depict the corresponding analysis and demonstration, such as In-containment Refueling Water Storage Tank pressure transient on depressurization area of IRWST, suction and internal flow stream of IRWST, configuration of strains, the addition method and amount of chemical addition, design and engineering applicant of Reactor Cavity Flooding System. All the analysis results show the basic design of IRWST meeting with the Utility Requirement Document's requirements on performance of safety function, setting of overfill passage, overpressure protection, related interference, etc., and show the reliability of Engineering Safety Features being improved for CNP1000 (three loops). Meanwhile, it is demonstrated that the design of In-containment Refueling Water Storage Tank can apply on the future nuclear power plant project in China. (authors)

  6. Case study to remove radioactive hazardous sludge from long horizontal storage tanks

    International Nuclear Information System (INIS)

    Hylton, T.D.; Youngblood, E.L.; Cummins, R.L.

    1995-01-01

    The removal of radioactive hazardous sludge from waste tanks is a significant problem at several US Department of Energy (DOE) sites. The use of submerged jets produced by mixing pumps lowered into the supernatant/sludge interface to produce a homogeneous slurry is being studied at several DOE facilities. The homogeneous slurry can be pumped from the tanks to a treatment facility or alternative storage location. Most of the previous and current studies with this method are for flat-bottom tanks with vertical walls. Because of the difference in geometry, the results of these studies are not directly applicable to long horizontal tanks such as those used at the Oak Ridge National Laboratory. Mobilization and mixing studies were conducted with a surrogate sludge (e.g., kaolin clay) using submerged jets in two sizes of horizontal tanks. The nominal capacities of these tanks were 0.87 m 3 (230 gal) and 95 m 3 (25,000 gal). Mobilization efficiencies and mixing times were determined for single and bidirectional jets in both tanks with the discharge nozzles positioned at two locations in the tanks. Approximately 80% of the surrogate sludge was mobilized in the 95-m 3 tank using a fixed bidirectional jet (inside diameter = 0.035 m) and a jet velocity of 6.4 m/s (21 ft/s)

  7. On the Behavior of Different PCMs in a Hot Water Storage Tank against Thermal Demands.

    Science.gov (United States)

    Porteiro, Jacobo; Míguez, José Luis; Crespo, Bárbara; de Lara, José; Pousada, José María

    2016-03-21

    Advantages, such as thermal storage improvement, are found when using PCMs (Phase Change Materials) in storage tanks. The inclusion of three different types of materials in a 60 l test tank is studied. Two test methodologies were developed, and four tests were performed following each methodology. A thermal analysis is performed to check the thermal properties of each PCM. The distributions of the water temperatures inside the test tanks are evaluated by installing four Pt-100 sensors at different heights. A temperature recovery is observed after exposing the test tank to an energy demand. An energetic analysis that takes into account the energy due to the water temperature, the energy due to the PCM and the thermal loss to the ambient environment is also presented. The percentage of each PCM that remains in the liquid state after the energy demand is obtained.

  8. On the Behavior of Different PCMs in a Hot Water Storage Tank against Thermal Demands

    Directory of Open Access Journals (Sweden)

    Jacobo Porteiro

    2016-03-01

    Full Text Available Advantages, such as thermal storage improvement, are found when using PCMs (Phase Change Materials in storage tanks. The inclusion of three different types of materials in a 60 l test tank is studied. Two test methodologies were developed, and four tests were performed following each methodology. A thermal analysis is performed to check the thermal properties of each PCM. The distributions of the water temperatures inside the test tanks are evaluated by installing four Pt-100 sensors at different heights. A temperature recovery is observed after exposing the test tank to an energy demand. An energetic analysis that takes into account the energy due to the water temperature, the energy due to the PCM and the thermal loss to the ambient environment is also presented. The percentage of each PCM that remains in the liquid state after the energy demand is obtained.

  9. Project plan for resolution of the organic waste tank safety issues at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Meacham, J.E.

    1996-10-03

    A multi-year project plan for the Organic Safety Project has been developed with the objective of resolving the organic safety issues associated with the High Level Waste (HLW) in Hanford`s single-shell tanks (SSTS) and double-shell tanks (DSTs). The objective of the Organic Safety Project is to ensure safe interim storage until retrieval for pretreatment and disposal operations begins, and to resolve the organic safety issues by September 2001. Since the initial identification of organics as a tank waste safety issue, progress has been made in understanding the specific aspects of organic waste combustibility, and in developing and implementing activities to resolve the organic safety issues.

  10. 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)

  11. 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).

  12. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume II

    International Nuclear Information System (INIS)

    1996-08-01

    This document, Volume 2, provides the inventory of waste addressed in this Final Environmental Impact Statement (EIS) for the Tank Waste Remediation System, Hanford Site, Richland, Washington. The inventories consist of waste from the following four groups: (1) Tank waste; (2) Cesium (Cs) and Strontium (Sr) capsules; (3) Inactive miscellaneous underground storage tanks (MUSTs); and (4) Anticipated future tank waste additions. The major component by volume of the overall waste is the tank waste inventory (including future tank waste additions). This component accounts for more than 99 percent of the total waste volume and approximately 70 percent of the radiological activity of the four waste groups identified previously. Tank waste data are available on a tank-by-tank basis, but the accuracy of these data is suspect because they primarily are based on historical records of transfers between tanks rather than statistically based sampling and analyses programs. However, while the inventory of any specific tank may be suspect, the overall inventory for all of the tanks combined is considered more accurate. The tank waste inventory data are provided as the estimated overall chemical masses and radioactivity levels for the single-shell tanks (SSTs) and double-shell tanks (DSTs). The tank waste inventory data are broken down into tank groupings or source areas that were developed for analyzing groundwater impacts

  13. 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

  14. Thermal Stratification in Small Solar Domestic Storage Tanks caused by Draw-offs

    DEFF Research Database (Denmark)

    Jordan, Ulrike; Furbo, Simon

    2005-01-01

    As shown in many research studies in the past, the thermal stratification of the tank caused by draw-offs has a high impact on the performance of a Solar Domestic Hot Water (SDHW) system. Nevertheless, in most tank models for system simulations the influence of the draw-off pattern on the mixing...... with a component oriented simulation tool for solar thermal systems....... are placed in order to reduce the mixing of the incoming cold water with the warmer storage water. To measure the thermal stratification thermocouples were placed in a vertical glass tube inside the tank. Measurements were carried out with different draw-off volumes, flow rates, and initial temperatures...

  15. Application of mass-spring model in seismic analysis of liquid storage tank

    International Nuclear Information System (INIS)

    Liu Jiayi; Bai Xinran; Li Xiaoxuan

    2013-01-01

    There are many tanks for storing liquid in nuclear power plant. When seismic analysis is performed, swaying of liquid may change the mechanical parameters of those tanks, such as the center of mass and the moment of inertia, etc., so the load due to swaying of liquid can't be neglected. Mass-spring model is a simplified model to calculate the dynamic pressure of liquid in tank under earthquake, which is derived by the theory of Housner and given in the specification of seismic analysis of Safety-Related Nuclear Structures and Commentary-4-98 (ASCE-4-98 for short hereinafter). According to the theory of Housner and ASCE-4-98, the mass-spring 3-D FEM model for storage tank and liquid in it was established, by which the force of stored liquid acted on liquid storage tank in nuclear power plant under horizontal seismic load was calculated. The calculated frequency of liquid swaying and effect of liquid convection on storage tank were compared with those calculated by simplified formula. It is shown that the results of 3-D FEM model are reasonable and reliable. Further more, it is more direct and convenient compared with description in ASCE-4-98 when the mass-spring model is applied to 3-D FEM model for seismic analysis, from which the displacement and stress distributions of the plate-shell elements or the 3-D solid finite elements can be obtained directly from the seismic input model. (authors)

  16. Dynamic analysis of liquid storage tank including hydrodynamic interaction by boundary element method

    International Nuclear Information System (INIS)

    Hwang, I.T.; Ting, K.

    1987-01-01

    Dynamic response of liquid storage tanks considering the hydrodynamic interactions due to earthquake ground motion has been extensively studied. Several finite element procedures, such as Balendra et. al. (1982) and Haroun (1983), have been devoted to investigate the dynamic interaction between the deformable wall of the tank and the liquid. Further, if the geometry of the storage tank can not be described by axi-symmetric case, the tank wall and the fluid domain must be discretized by three dimensional finite elements to investigate the fluid-structure-interactions. Thus, the need of large computer memory and expense of vast computer time usually make this analysis impractical. To demonstrate the accuracy and reliability of the solution technique developed herein, the dynamic behavior of ground-supported, deformed, cylindrical tank with incompressible fluid conducted by Haroun (1983) are analyzed. Good correlations of hydrodynamic pressure distribution between the computed results with the referenced solutions are noted. The fluid compressibility significantly affects the hydrodynamic pressures of the liquid-tank-interactions and the work which is done on this discussion is still little attention. Thus, the influences of the compressibility of the liquid on the reponse of the liquid storage due to ground motion are then drawn. By the way, the complex-valued frequency response functions for hydrodynamic forces of Haroun's problem are also displayed. (orig./GL)

  17. Anti-seismic analysis for air storage tank used in the nuclear power plant

    International Nuclear Information System (INIS)

    Hua Jun; Ren Xin; Feng Ping

    2011-01-01

    This text calculates and analyses the structure of the air storage tank used for the SBO diesel generator set of Taishan nuclear power plant through finite element method, and simply introduces the mechanical modeling, loading condition and seismic response spectrum analyzing method for the structure, then get the natural frequency, vibration mode and response under seismic load of the structure through calculation. Evaluate the stress under the combined load such as gravity, internal stress, earthquake of the structure according to RCCM. The result shows that the structure intensity of the air storage tank meets the requirements of the specification. The calculating result gives the accordance for the seismic design of the air storage tank. (authors)

  18. Corrosion control of carbon steel radioactive-liquid storage tanks

    International Nuclear Information System (INIS)

    Chang, Ji Young.

    1997-05-01

    As the West Valley Demonstration Project (WVDP) continues vitrification operation and begins decontamination activities, it is vital to continue to maintain the integrity of the high-level waste tanks and prevent further corrosion that may disrupt the operation. This report describes the current operational status and some corrosion concerns with corresponding control measure recommendations. 14 refs., 5 figs., 6 tabs

  19. Knowledge-based emergency planning for storage tank farms

    Czech Academy of Sciences Publication Activity Database

    Nevrlý, Václav; Bitala, P.; Nevrlá, P.; Střižík, Michal

    2008-01-01

    Roč. 10, č. 1 (2008), s. 10-15 ISSN 1335-4205 Institutional research plan: CEZ:AV0Z20760514 Keywords : emergency * preparedness * modeling tank fire boilover Subject RIV: AQ - Safety, Health Protection, Human - Machine http://www.utc.sk/komunikacie

  20. FINAL REPORT - Development of High Pressure Hydrogen Storage Tank for Storage and Gaseous Truck Delivery

    Energy Technology Data Exchange (ETDEWEB)

    Baldwin, Donald [Hexagon Lincoln LLC, Lincoln, NE (United States)

    2017-08-04

    The “Development of High Pressure Hydrogen Storage Tanks for Storage and Gaseous Truck Delivery” project [DE-FG36-08GO18062] was initiated on 01 July 2008. Hexagon Lincoln (then Lincoln Composites) received grant funding from the U.S. Department of Energy to support the design and development of an improved bulk hauling and storage solution for hydrogen in terms of cost, safety, weight and volumetric efficiency. The development of this capability required parallel development and qualification of large all-composites pressure vessels, a custom ISO container to transport and store said tanks, and performance of trade studies to identify optimal operating pressure for the system. Qualification of the 250 bar TITAN® module was completed in 2009 with supervision from the American Bureau of Shipping [ABS], and the equipment has been used internationally for bulk transportation of fuel gases since 2010. Phase 1 of the project was successfully completed in 2012 with the issuance of USDOT SP 14951, the special permit authorizing the manufacture, marking, sale and use of TITAN® Mobile Pipeline® equipment in the United States. The introduction of tube trailers with light weight composite tankage has meant that 2 to 3 times as much gaseous fuel can be transported with each trip. This increased hauling efficiency offers dramatically reduced operating costs and has enabled a profitable business model for over-the-road compressed natural gas delivery. The economic drivers of this business opportunity vary from country to country and region to region, but in many places gas distribution companies have realized profitable operations. Additional testing was performed in 2015 to characterize hydrogen-specific operating protocols for use of TITAN® systems in CHG service at 250 bar. This program demonstrated that existing compression and decompression methodologies can efficiently and safely fill and unload lightweight bulk hauling systems. Hexagon Lincoln and U.S. DOE agreed

  1. 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...

  2. 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...

  3. Remediation and recycling of oil-contaminated soil beneath a large above-ground storage tank

    International Nuclear Information System (INIS)

    Wallace, G.

    1994-01-01

    While retrofitting a large 30-year-old, above-ground petroleum storage tank, Southern California Edison Company (SCE) discovered that soil beneath the fixed-roof, single-bottom tank was contaminated with 40,000 gallons of number-sign 6 fuel oil. The steel tank was left in place during the excavation and remediation of the contaminated soil to retain the operating permit. The resulting 2,000 tons of contaminated aggregate was recycled to make asphalt concrete for paving the tank basin and the remaining 5,600 tons of oily soil was thermally treated on site for use as engineered fill at another location. This successful operation provided an economical cleanup solution for a common leakage problem of single-lined tanks and eliminated the long-term liability of Class 1 landfill disposal. As a pro-active environmental effort, this paper shares SCE's site assessment procedure, reveals the engineering method developed to stabilize the tank, discusses the soil treatment technologies used, describes the problems encountered and lessons learned during the cleanup, discloses the costs of the operation, and offers guidelines and recommendations for similar tank remediation. This paper does not describe the work or costs for removing or replacing the tank bottom

  4. Perfecting on floating roof tanks, especially to storage tanks in a nuclear power plant

    International Nuclear Information System (INIS)

    Marquet, A.

    1987-01-01

    In this invention, the liquid reservoir has a floating roof with a tight connection to its wall by a flexible membrane, forming a space for counterbalancing liquid, and a pressure relief valve for the liquid within the reservoir opening above the counterbalancing liquid. Application for tanks used in nuclear power plant [fr

  5. Tank characterization report: Tank 241-C-109

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-09-01

    Single-shell tank 241-C-109 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in September 1992. Analyses of materials obtained from tank 241-C-109 were conducted to support the resolution of the ferrocyanide unreviewed safety question (USQ) and to support Hanford Federal Facility Agreement and consent Order (Tri- Party Agreement) Milestone M-10-00. This report describes this analysis.

  6. Tank characterization report: Tank 241-C-109

    International Nuclear Information System (INIS)

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

    1993-09-01

    Single-shell tank 241-C-109 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in September 1992. Analyses of materials obtained from tank 241-C-109 were conducted to support the resolution of the ferrocyanide unreviewed safety question (USQ) and to support Hanford Federal Facility Agreement and consent Order (Tri- Party Agreement) Milestone M-10-00. This report describes this analysis

  7. 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)

  8. Super Phenix fuel storage tank investigations concerning the sodium leak

    International Nuclear Information System (INIS)

    Blaix, J.C.; Archer, J.; Foucher, N.; Escaravage

    1989-01-01

    Following the detection of a sodium leak from the fuel storage drum of the Super Phenix LMFBR reactor, investigations have been undertaken in order to: check again that the design of the storage main vessel was right, make an assessment of the vessel behavior under the actual loadings supported during its two first years of life, check the mechanical properties of materials (in purchase and present conditions), find whether the leak could be explained by design failure or unexpected material properties

  9. Seven Operation Modes and Simulation Models of Solar Heating System with PCM Storage Tank

    Directory of Open Access Journals (Sweden)

    Juan Zhao

    2017-12-01

    Full Text Available A physical model and dynamic simulation models of a solar phase-change heat storage heating system with a plate solar collector, phase-change material (PCM storage tank, plate heat exchanger, and auxiliary heat sources were established. A control strategy and numerical models for each of seven different operation modes that cover the entire heating season of the system were developed for the first time. The seven proposed operation modes are Mode 1: free cooling; Mode 2: reservation of heat absorbed by the solar collector in the PCM storage tank when there is no heating demand; Mode 3: direct supply of the heating demand by the solar collector; Mode 4: use of the heat absorbed by the solar collector to meet the heating demands, with the excess heat stored in the PCM storage tank; Mode 5: use of heat stored in the PCM storage tank to meet the heating demands, Mode 6: combined use of heat stored in the PCM storage tank and the auxiliary heating sources to meet the heating demands; and Mode 7: exclusive use of the auxiliary heat sources in order to meet the heating demands. Mathematical models were established for each of the above seven operation modes, taking into consideration the effects of the outdoor meteorological parameters and terminal load on the heating system. The real-time parameters for the entire heating season of the system with respect to the different operation modes can be obtained by solving the simulation models, and used as reference for the optimal design and operation of the actual system.

  10. Influences of model structure and calibration data size on predicting chlorine residuals in water storage tanks.

    Science.gov (United States)

    Hua, Pei; de Oliveira, Keila Roberta Ferreira; Cheung, Peter; Gonçalves, Fábio Veríssimo; Zhang, Jin

    2018-04-09

    This study evaluated the influences of model structure and calibration data size on the modelling performance for the prediction of chlorine residuals in household drinking water storage tanks. The tank models, which consisted of two modules, i.e., hydraulic mixing and water quality modelling processes, were evaluated under identical calibration conditions. The hydraulic mixing modelling processes investigated included the continuously stirred tank reactor (CSTR) and multi-compartment (MC) methods, and the water quality modelling processes included first order (FO), single-reactant second order (SRSO), and variable reaction rate coefficients (VRRC) second order chlorine decay kinetics. Different combinations of these hydraulic mixing and water quality methods formed six tank models. Results show that by applying the same calibration datasets, the tank models that included the MC method for modelling the hydraulic mixing provided better predictions compared to the CSTR method. In terms of water quality modelling, VRRC kinetics showed better predictive abilities compared to FO and SRSO kinetics. It was also found that the overall tank model performance could be substantially improved when a proper method was chosen for the simulation of hydraulic mixing, i.e., the accuracy of the hydraulic mixing modelling plays a critical role in the accuracy of the tank model. Advances in water quality modelling improve the calibration process, i.e., the size of the datasets used for calibration could be reduced when a suitable kinetics method was applied. Although the accuracies of all six models increased with increasing calibration dataset size, the tank model that consisted of the MC and VRRC methods was the most suitable of the tank models as it could satisfactorily predict chlorine residuals in household tanks by using invariant parameters calibrated against the minimum dataset size. Copyright © 2018 Elsevier B.V. All rights reserved.

  11. Speciation of organic carbon in Hanford waste storage tanks: Part 1

    International Nuclear Information System (INIS)

    Carlson, C.D.

    1997-02-01

    This report is the first in a series to report on speciation of organic carbon in Hanford waste storage tanks. The comparison of the existing total organic carbon with oxalate and limited analyses of other organic species (acetate, formate, and normal paraffin hydrocarbons [NPH]) are reported. All of the data have been previously reported by the Grout and Characterization programs; the information includes all of the publicly available data through October 1996. Oxalate data were reported for 33 tanks, TOC data were reported for 82 tanks, and both oxalate and TOC data were available for 27 tanks. Of these 27 tanks, seven were found to have greater than 80% of the TOC identified as oxalate: 241-BY-104, 241-BY-105, 241-BY-106, 241-BY-110, 241-S-109, and 241-SX-108. Eighty percent accountability has been tentatively established as a minimum goal of the Organic Safety Program for speciation of TOC. Accountability of TOC through speciation will allow more accurate estimate of the potential energy content of the wastes as currently stored. Of the remaining 19 tanks, seven had between 40 and 80% of the TOC identified as oxalate, and eleven had less than 35% of the TOC identified. Of these, only five tanks had segment results that were greater than 1% TOC, and none was above 2%. Since the cur-rent safety criterion outlined in the Safety Analysis is 4.5% TOC, it may be determined that the further analyses of these tank wastes are not necessary. If additional analyses are deemed necessary, minimal work may be required, possibly limited to ion chromatography (IC), ion pair chromatography and capillary zone electrophoresis (CZE). Additional speciation work is planned for this fiscal year in both the Organic Tanks Safety and Characterization programs. The Characterization program reports acetate and formate data in addition to the oxalate data for all the tank cores it processes

  12. A survey of fissile solution storage methods: Champion the poisoned tube tank

    International Nuclear Information System (INIS)

    Rothe, R.E.

    1985-01-01

    A number of methods for the safe storage of such liquids are described and evaluated. Some date back to the dawn of the nuclear age; but others are somewhat novel. General regions of applicability for the various methods are also addressed. Rockwell International's plant at Rocky Flats, Colorado has safely handled large amounts of such liquids for over three decades. The cost of the method used and other considerations suggest the continued search for improved methods. One method - the Poisoned Tube Tank - emerges as a candidate with high potential for many future applications. Rockwell International has designed its first such tank for service. This tank will be critically safe, even under a variety of conditions; and it combines reasonable initial cost with an expected low operating and inspection cost. The tank should be installed by the end of 1985

  13. 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

  14. Cathodic Protection for Above Ground Storage Tank Bottom Using Data Acquisition

    Directory of Open Access Journals (Sweden)

    Naseer Abbood Issa Al Haboubi

    2015-07-01

    Full Text Available Impressed current cathodic protection controlled by computer gives the ideal solution to the changes in environmental factors and long term coating degradation. The protection potential distribution achieved and the current demand on the anode can be regulated to protection criteria, to achieve the effective protection for the system. In this paper, cathodic protection problem of above ground steel storage tank was investigated by an impressed current of cathodic protection with controlled potential of electrical system to manage the variation in soil resistivity. Corrosion controller has been implemented for above ground tank in LabView where tank's bottom potential to soil was manipulated to the desired set point (protection criterion 850 mV. National Instruments Data Acquisition (NI-DAQ and PC controllers for tank corrosion control system provides quick response to achieve steady state condition for any kind of disturbances.

  15. Detection of simulated pitting corrosion and noises in crude oil storage tank by acoustic emission

    International Nuclear Information System (INIS)

    Shukri Mohd; Latif, N.A.; Azhar Mohd Sinin; Mohamad Daud; Abd Nasir Ibrahim

    2008-01-01

    The damage mechanisms associated with crude oil storage tanks can be complex and varied and include pitting corrosion due to presence of species such as sulphate reducing bacteria. Acoustic Emission (AE) could be used to characterise the pitting corrosion signal in crude oil storage tanks but it is extremely difficult to simulate the pitting corrosion in the laboratory using crude oil as electrolyte because crude oil is considered as non corrosive medium. In this study, induced current have been introduced onto a surface ASTM 516 steel as an electrical source to simulate the electrical noise produced during pitting corrosion process and AE sensor have been used to detect this current. It is found that AE system could detect AE signal release during current induction this current and is expected that if the exact simulation of the current magnitude produced during pitting corrosion process is made available, AE characterisation of pitting corrosion in such tank could be made possible. (Author)

  16. Nonliner analysis techniques for use in the assessment of high-level waste storage tank structures

    International Nuclear Information System (INIS)

    Moore, C.J.; Julyk, L.J.; Fox, G.L.; Dyrness, A.D.

    1991-09-01

    Reinforced concrete in combination with a steel liner has had a wide application to structures containing hazardous material. The buried double-shell waste storage tanks at the US Department of Energy's Hanford Site use this construction method. The generation and potential ignition of combustible gases within the primary tank is postulated to develop beyond-design-basis internal pressure and possible impact loading. The scope of this paper includes the illustration of analysis techniques for the assessment of these beyond-design-basis loadings. The analysis techniques include the coupling of the gas dynamics with the structural response, the treatment of reinforced concrete in regimes of inelastic behavior, and the treatment of geometric nonlinearities. The techniques and software tools presented provide a powerful nonlinear analysis capability for storage tanks. 10 refs., 13 figs., 1 tab

  17. Experimental study of temperature stratification in an integrated collector-storage solar water heater with two horizontal tanks

    Energy Technology Data Exchange (ETDEWEB)

    Madhlopa, A. [Department of Physics and Biochemical Sciences, Malawi Polytechnic, P/Bag 303, Blantyre 3 (Malawi); Mgawi, R. [Department of Mechanical Engineering, Malawi Polytechnic, P/Bag 303, Blantyre 3 (Malawi); Taulo, J. [Malawi Industrial Research and Technology Development Centre, P.O. Box 357, Blantyre (Malawi)

    2006-08-15

    The effect of tank-interconnection geometry on temperature stratification in an integrated collector-storage solar water (ICSSW) heater with two horizontal cylindrical tanks has been studied. The tanks were parallel to each other, and separated horizontally and vertically, with the lower tank fitted directly below a glass cover, and half of the upper tank insulated. In addition, a truncated parabolic concentrator was fitted below the tanks, with its focal line along the axis of the upper tank. The heater was tested outdoors with the two tanks connected in parallel (P), and S1- and S2-series configurations, with and without hot water draw-off. Water temperature was monitored during solar collection and hot water draw-offs. For the heat charging process, it was found that only the lower tank exhibited temperature stratification in the P- and S1-tank modes of operation. There was satisfactory temperature stratification in both tanks in the S2-tank configuration. For the hot water draining process, the P-tank configuration exhibited some degree of stratification in both tanks. A significant loss of stratification was observed in the lower tank, with the upper tank exhibiting practical stratification, when the system was operated in the S1-tank mode. The S2-tank interconnection maintained a satisfactory degree of temperature stratification in both tanks. So, the S2-tank mode of operation was most effective in promoting practical temperature stratification in both tanks during solar collection and hot water draw-offs. Other results are presented and discussed in this paper. (author)

  18. Simplified design and evaluation of liquid storage tanks relative to earthquake loading

    Energy Technology Data Exchange (ETDEWEB)

    Poole, A.B.

    1994-06-01

    A summary of earthquake-induced damage in liquid storage tanks is provided. The general analysis steps for dynamic response of fluid-filled tanks subject to horizontal ground excitation are discussed. This work will provide major attention to the understanding of observed tank-failure modes. These modes are quite diverse in nature, but many of the commonly appearing patterns are believed to be shell buckling. A generalized and simple-to-apply shell loading will be developed using Fluegge shell theory. The input to this simplified analysis will be horizontal ground acceleration and tank shell form parameters. A dimensionless parameter will be developed and used in predictions of buckling resulting from earthquake-imposed loads. This prediction method will be applied to various tank designs that have failed during major earthquakes and during shaker table tests. Tanks that have not failed will also be reviewed. A simplified approach will be discussed for early design and evaluation of tank shell parameters and materials to provide a high confidence of low probability of failure during earthquakes.

  19. Oak Ridge National Laboratory Melton Valley Storage Tanks Waste Filtration Process Evaluation

    International Nuclear Information System (INIS)

    Walker, B.W.

    1998-01-01

    Cross-flow filtration is being evaluated as a pretreatment in the proposed treatment processes for aqueous high-level radioactive wastes at Oak Ridge National Laboratory (ORNL) to separate insoluble solids from aqueous waste from the Melton Valley Storage Tanks (MVST)

  20. The use of solar energy for heating an asphalt storage tank.

    Science.gov (United States)

    1984-01-01

    10,000 gal. asphalt storage tank was equipped with a solar heating system and instrumented to determine its effectiveness over a 12.5-month period. An evaluation of the data indicated that the solar system conserved 25,126 kWh of electrical power dur...

  1. 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 ...

  2. 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

  3. 76 FR 46798 - Compatibility of Underground Storage Tank Systems With Biofuel Blends; Correction

    Science.gov (United States)

    2011-08-03

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-UST-2010-0651; FRL-9447-3] Compatibility of Underground Storage Tank Systems With Biofuel Blends; Correction AGENCY: Environmental Protection Agency (EPA). ACTION: Notice; correction. SUMMARY: This document contains a typographical correction to the guidance which was...

  4. 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

  5. 18 CFR 1304.405 - Fuel storage tanks and handling facilities.

    Science.gov (United States)

    2010-04-01

    ... used to contain a regulated substance (such as a petroleum product) and has 10 percent or more of its... or remedy pollution or violations of law, including removal of the UST system, with costs charged to... flammable and combustible liquids storage tanks at marine service stations. (d) Fuel handling on private...

  6. Control of a long reach manipulator with suspension cables for waste storage tank remediation. Final report

    International Nuclear Information System (INIS)

    Wang, S.L.

    1994-01-01

    A long reach manipulator will be used for waste remediation in large underground storage tanks. The manipulator's slenderness makes it flexible and difficult to control. A low-cost and effective method to enhance the manipulator's stiffness is proposed in this research by using suspension cables. These cables can also be used to accurately measure the position of the manipulator's wrist

  7. Double variable frequency pendulum isolator for seismic isolation of liquid storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Soni, D.P., E-mail: soni_svit@yahoo.co [Civil Engineering Department, Sardar Vallabhbhai Patel Institute of Technology, Vasad 388 306, Gujarat (India); Mistry, B.B., E-mail: bbm_7@yahoo.co.i [Engineering College, Tuwa 389 001 (India); Panchal, V.R., E-mail: vijay_svit@yahoo.co.i [Civil Engineering Department, Sardar Vallabhbhai Patel Institute of Technology, Vasad 388 306, Gujarat (India)

    2011-03-15

    Research highlights: The seismic response of liquid storage tanks isolated by the DVFPI is investigated. Four DVFPI design cases are considered by varying properties of the both surfaces. Criterion to optimize its performance is proposed based on minimum responses. Different stiffness of top and bottom surfaces optimizes the DVFPI for a slender tank. Equal stiffness of top and bottom surfaces optimizes the DVFPI for a broad tank. - Abstract: The paper describes the behaviour of liquid storage slender and broad tanks isolated by the double variable frequency pendulum isolator (DVFPI). The DVFPI is a double sliding isolation system having elliptical sliding surfaces. The geometry and coefficient of friction of top and bottom sliding surfaces can be unequal. The governing equations of motion and energy balance equation of the tank-isolation system subjected to bilateral ground excitation are derived and solved in the incremental form. In order to investigate the behaviour of the DVFPI, the response is obtained under different parametric variations for a set of 20 far-field earthquake ground motions. Four different combinations of the DVFPI design cases having different isolator geometry and coefficient friction at top and bottom sliding surfaces are studied and the criterion to optimize its performance is proposed based on minimum responses and energy quantities. Further, influences of the initial time period, coefficient of friction and frequency variation factors at the two sliding surfaces and the tank aspect ratio are investigated. It is found that the performance of the DVFPI can be optimized by designing the top sliding surface with high initial stiffness relative to the bottom one and the coefficient of friction of both sliding surfaces to be equal for a slender tank whereas both surfaces should be designed with equal initial stiffness and coefficient of friction for a broad tank.

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

    Energy Technology Data Exchange (ETDEWEB)

    Alfred Wickline

    2009-03-01

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

  9. Energy system investment model incorporating heat pumps with thermal storage in buildings and buffer tanks

    International Nuclear Information System (INIS)

    Hedegaard, Karsten; Balyk, Olexandr

    2013-01-01

    Individual compression heat pumps constitute a potentially valuable resource in supporting wind power integration due to their economic competitiveness and possibilities for flexible operation. When analysing the system benefits of flexible heat pump operation, effects on investments should be taken into account. In this study, we present a model that facilitates analysing individual heat pumps and complementing heat storages in integration with the energy system, while optimising both investments and operation. The model incorporates thermal building dynamics and covers various heat storage options: passive heat storage in the building structure via radiator heating, active heat storage in concrete floors via floor heating, and use of thermal storage tanks for space heating and hot water. It is shown that the model is well qualified for analysing possibilities and system benefits of operating heat pumps flexibly. This includes prioritising heat pump operation for hours with low marginal electricity production costs, and peak load shaving resulting in a reduced need for peak and reserve capacity investments. - Highlights: • Model optimising heat pumps and heat storages in integration with the energy system. • Optimisation of both energy system investments and operation. • Heat storage in building structure and thermal storage tanks included. • Model well qualified for analysing system benefits of flexible heat pump operation. • Covers peak load shaving and operation prioritised for low electricity prices

  10. Implications of the modelling of stratified hot water storage tanks in the simulation of CHP plants

    Energy Technology Data Exchange (ETDEWEB)

    Campos Celador, A., E-mail: alvaro.campos@ehu.es [ENEDI Research Group-University of the Basque Country, Departamento de Maquinas y Motores Termicos, E.T.S.I. de Bilbao Alameda de Urquijo, s/n 48013 Bilbao, Bizkaia (Spain); Odriozola, M.; Sala, J.M. [ENEDI Research Group-University of the Basque Country, Departamento de Maquinas y Motores Termicos, E.T.S.I. de Bilbao Alameda de Urquijo, s/n 48013 Bilbao, Bizkaia (Spain)

    2011-08-15

    Highlights: {yields} Three different modelling approaches for simulation of hot water tanks are presented. {yields} The three models are simulated within a residential cogeneration plant. {yields} Small differences in the results are found by an energy and exergy analysis. {yields} Big differences between the results are found by an advanced exergy analysis. {yields} Results on the feasibility study are explained by the advanced exergy analysis. - Abstract: This paper considers the effect that different hot water storage tank modelling approaches have on the global simulation of residential CHP plants as well as their impact on their economic feasibility. While a simplified assessment of the heat storage is usually considered in the feasibility studies of CHP plants in buildings, this paper deals with three different levels of modelling of the hot water tank: actual stratified model, ideal stratified model and fully mixed model. These three approaches are presented and comparatively evaluated under the same case of study, a cogeneration plant with thermal storage meeting the loads of an urbanisation located in the Bilbao metropolitan area (Spain). The case of study is simulated by TRNSYS for each one of the three modelling cases and the so obtained annual results are analysed from both a First and Second-Law-based viewpoint. While the global energy and exergy efficiencies of the plant for the three modelling cases agree quite well, important differences are found between the economic results of the feasibility study. These results can be predicted by means of an advanced exergy analysis of the storage tank considering the endogenous and exogenous exergy destruction terms caused by the hot water storage tank.

  11. WVNS Tank Farm Process Support: Experimental evaluation of an inert gas (nitrogen) to mitigate external corrosion of high-level waste storage tanks

    International Nuclear Information System (INIS)

    Elmore, M.R.

    1996-02-01

    Corrosion of the carbon steel waste storage tanks at West Valley Nuclear Services continues to be of concern, especially as the planned duration of waste storage time increases and sludge washing operations are conducted. The external surfaces of Tanks 8D-1 and 8D-2 have been exposed for more than 10 years to water that has intruded into the tank vaults. Visual inspection of the external tank surfaces using a remote video camera has shown indications of heavy corrosion in localized areas on the tank walls. Tests on mild steel specimens under simulated tank vault conditions showed that corrosion is related to the availability of oxygen for the corrosion reactions; consequently, removing oxygen as one of the reactants should effectively eliminate corrosion. In terms of the waste tanks, excluding oxygen from the annular vault space, such as by continuous flushing with an inert gas, should substantially decrease corrosion of the external surfaces of the mild steel tanks (100% exclusion of oxygen is probably not practicable). Laboratory corrosion testing was conducted at Pacific Northwest National Laboratory to give a preliminary assessment of the ability of nitrogen-inerting to reduce steel corrosion. This report summarizes test results obtained after 18-month corrosion tests comparing open-quotes nitrogen-inertedclose quotes corrosion with open-quotes air-equilibratedclose quotes corrosion under simulated tank vault conditions

  12. TANK FARM INTERIM SURFACE BARRIER MATERIALS AND RUNOFF ALTERNATIVES STUDY

    Energy Technology Data Exchange (ETDEWEB)

    HOLM MJ

    2009-06-25

    This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

  13. Tank Farm Interim Surface Barrier Materials And Runoff Alternatives Study

    International Nuclear Information System (INIS)

    Holm, M.J.

    2009-01-01

    This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

  14. FTA of loss of cooling to a HALW storage tank

    International Nuclear Information System (INIS)

    Nomura, Yasushi

    1991-10-01

    A fault tree analysis consisting of assumption of accident scenarios, construction of fault trees, and performing of analyses is given for a loss of cooling accident in a HALW (High Activity Liquid Waste) tank of a typical reprocessing facility. A systematic method is developed to avoid 'missing scenarios', and 'confused scenarios' which are major problems in these analyses. Model plant data, basic failure frequency data and a fault tree analysis code named FTL have been introduced from NUKEM GmbH, Germany. The analyzed occurrence frequencies for the assumed scenarios of the loss of cooling accident are discussed to show a design improvement measure to attain a more reliable system. These results are compared with general requirements to be selected as DBE (design basis event) used in the safety assessment of the facility design. DBE is an event which is considered to have relatively high occurrence probabilities and considerable effects on environment. (author)

  15. Investigating and modeling of the effects of condensate storage tank fire in a refinery

    Directory of Open Access Journals (Sweden)

    Mohammad Kamaei

    2015-12-01

    Full Text Available Background & objective: Oil storage tanks are major industrial facilities which always pose risks of toxic substance release, fires and explosions. Fire has been recognized as the most common risk associated with such facilities, while explosion is the most important one in terms of ability to claim human lives and damage property. The current study aimed at investigating and modeling the effects of fires occurring in a gas condensate tank farm, according to which the level of possible emergencies were specified using the guidelines provided by the Center for Chemical Process Safety. Lastly, control measures were recommended. Methods: In the present study, the release and leakage of gas condensate from floating roof tanks were assessed using HAZOP method. Then, using PHAST software, the amount of radiation intensity received by the surrounding environment was determined, safe boundaries were computed, and according to the CCPS standard the emergency levels were determined. Results: modeling was performed based on the maximum capacity of tanks for both cold and hot seasons. The results revealed that safe distance for a maximum amount of irradiation density (4 KW/m2 related to a sudden release were 60 and 140 meters, respectively. Conclusion: according to the current condition of the plants and storage tanks, a plan was recommended for emergency management and practical suggestions were provided to improve the reliability and consistency.

  16. Cathodic protection simulation of above ground storage tank bottom: Experimental and numerical results

    Energy Technology Data Exchange (ETDEWEB)

    Schultz, Marcelo [Inspection Department, Rio de Janeiro Refinery - REDUC, Petrobras, Rio de Janeiro (Brazil); Brasil, Simone L.D.C. [Chemistry School, Federal University of Rio de Janeiro, UFRJ, Rio de Janeiro (Brazil); Baptista, Walmar [Corrosion Department, Research Centre - CENPES, Petrobras (Brazil); Miranda, Luiz de [Materials and Metallurgical Engineering Program, COPPE, UFRJ, Rio de Janeiro (Brazil); Brito, Rosane F. [Corrosion Department, Research Centre, CENPES, Petrobras, Rio de Janeiro (Brazil)

    2004-07-01

    The deterioration history of Above ground Storage Tanks (AST) of Petrobras' refineries - shows that the great incidence of corrosion in the AST bottom is at the external side. This is a problem in the disposability of storage crude oil and other final products. At this refinery, all AST's are built over a concrete base with a lot of pile to support the structure and distribute the charge homogeneously. Because of this it is very difficult to use cathodic protection as an anti-corrosive method for each one of these tanks. This work presents an alternative cathodic protection system to protect the external side of the tank bottom using a new metallic bottom, placed at different distance from the original one. The space between the two bottoms was filled with one of two kinds of soils, sand or clay, more conductive than the concrete. Using a prototype tank it was studied the potential distributions over the new tank bottom for different system parameters, as soil resistivity, number and position of anodes localized in the old bottom. These experimental results were compared to numerical simulations, carried out using a software based on the Boundary Element Method. The computer simulation validates this protection method, confirming to be a very useful tool to define the optimized cathodic protection system configuration. (authors)

  17. CSER 94-004: Criticality safety of double-shell waste storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.A.

    1994-09-22

    This criticality safety evaluation covers double-shell waste storage tanks (DSTs), double-contained receiver tanks (DCRTs), vault tanks, and the 242-A Evaporator located in the High Level Waste (HLW) Tank Farms on the Hanford Site. Limits and controls are specified and the basis for ensuring criticality safety is discussed. A minimum limit of 1,000 is placed upon the solids/plutonium mass ratio in incoming waste. The average solids/Pu mass ratio over all waste in tank farms is estimated to be about 74,500, about 150 times larger than required to assure subcriticality in homogeneous waste. PFP waste in Tank-102-SY has an estimated solids/Pu mass ratio of 10,000. Subcriticality is assured whenever the plutonium concentration is less than 2.6 g. The median reported plutonium concentration for 200 samples of waste solids is about 0.01 g (0.038 g/gal). A surveillance program is proposed to increase the knowledge of the waste and provide added assurance of the high degree of subcriticality.

  18. Repairs to leaky central shaft and seismic qualification of emergency water storage tank of Cirus

    International Nuclear Information System (INIS)

    Khanijo, R.N.; Subudhi, D.; Marik, S.K.

    2006-01-01

    Emergency cooling water storage tank of CIRUS reactor is made of prestressed concrete and is a spherical structure which is used to store 38.6 x 10 5 liters of demineralised water. This water is used for emergency core cooling and shut down core cooling of the reactor. This tank was commissioned in 1960 and since then it had been in continuous service till 1997 when refurbishing of CIRUS was undertaken. Water leakage was observed from the bottom section of the central inspection shaft of the tank in 1976. Attempts were made to rectify the leak by low pressure grouting of cement. but the leak could not be arrested. The leak rate increased to some extent initially and then stabilized at a steady rate. During the long outage of the reactor for refurbishment. all the water leaks were rectified. This emergency cooling water storage tank is supposed to perform satisfactorily even during seismic conditions. This tank was designed prior to 1960 for seismic requirements prevailing at that time. Presently the seismic design parameters have been revised and it was required to qualify the tank structure as per the current standards. In view of above detailed seismic analysis of the tank structure was carried out. The stresses at bottom joint area of central inspection shaft were found to be more than the permissible limits as per applicable codes. To bring down the stresses within the specified limits various methods of seismic retrofitting were considered. After due discussions it was decided to strengthen the central inspection shaft and its bottom joint area by installing 3.15 mm thick mild steel liner plates upto top of the shaft on its wet side and upto 2 meters height on dry side of the shaft including bottom joint area with liner plate spanning 2 meters radially on both sides of water containing cupola slab. The gap in between the concrete inspection shaft and the mild steel liner plate was proposed to be filled by, injecting Epoxy compound to make it a monolithic

  19. Behavior of ruthenium in the case of shutdown of the cooling system of HLLW storage tanks

    International Nuclear Information System (INIS)

    Philippe, M.; Mercier, J.P.; Gue, J.P.

    1990-01-01

    The consequences of the failure of the cooling system of fission product storage tanks over a variable period were investigated as part of the safety analysis of the La Hague spent fuel reprocessing plant. Due to the considerable heat release, induced by the fission products, a prolonged shutdown of the tank cooling system could cause the progressive evaporation of the solutions to dryness, and culminate in the formation of volatile species of ruthenium and their release in the tank venting circuit. To determine the fraction of ruthenium likely to be transferred from the storage tanks in volatile or aerosol form during the failure, evaporation tests were conducted by evaporating samples of actual nitric acid solutions of fission products, obtained on the laboratory scale after the reprocessing of several kilograms of MOX fuels irradiated to 30,000 MWday.t -1 . A distillation apparatus was designed to operate with small volume solution samples, reproducing the heating conditions existing in the reprocessing plant within a storage tank for fission products. The main conclusions drawn from these experiments are as follows: - ruthenium is only volatilized in the final phase of evaporation, just before desiccation, - for a final temperature limited to 160 0 C, the total fraction of volatilized ruthenium reaches 12%, in the presence of H 2 0, HN0 3 , N0 x and 0 2 , the volatilized ruthenium recombines mainly in the form of ruthenium nitrosyl nitrates, or decomposes into ruthenium oxide on the walls of the apparatus. Assuming a heating power density of 10 W/liter of concentrate, and a perfectly adiabatic storage system, the minimum time required to reach dryness can be estimated at 90 h, allowing substantial time to take action to restore a cooling source

  20. Behavior of ruthenium in the case of shutdown of the cooling system of HLLW storage tanks

    International Nuclear Information System (INIS)

    Philippe, M.; Mercier, J.P.; Gue, J.P.

    1991-01-01

    The consequences of the failure of the cooling system of fission product storage tanks over a variable period were investigated as part of the safety analysis of the La Hague spent fuel reprocessing plant. Due to the considerable heat release, induced by the fission products, a prolonged shutdown of the tank cooling system could cause the progressive evaporation of the solutions to dryness, and culminate in the formation of volatile species of ruthenium and their release in the tank venting circuit. To determine the fraction of ruthenium likely to be transferred from the storage tanks in volatile or aerosol form during the failure, evaporation tests were conducted by evaporating samples of actual nitric acid solutions of fission products, obtained on the laboratory scale after the reprocessing of several kilograms of MOX fuels irradiated to 30,000 MW day·t -1 . A distillation apparatus was designed to operate with small-volume solution samples, reproducing the heating conditions existing in the reprocessing plant within a storage tank for fission products. The main conclusions drawn from these experiments are as follows: ruthenium is only volatilized in the final phase of evaporation, just before desiccation; for a final temperature limited to 160 degree C, the total fraction of volatilized ruthenium reaches 12%; in the presence of H 2 O, HNO 3 , NO x and O 2 , the volatilized ruthenium recombines mainly in the form of ruthenium nitrosyl nitrates, or decomposes into ruthenium oxide (probably RuO 2 ) on the walls of the apparatus. Assuming a heating power density of 10 W/liter of concentrate, and a perfectly adiabatic storage system, the minimum time required to reach dryness can be estimated at 90 h, allowing substantial time to take action to restore a cooling source

  1. Behaviour of ruthenium in the case of shutdown of the cooling system of HLLW storage tanks

    International Nuclear Information System (INIS)

    Philippe, M.; Gue, J.P.; Mercier, J.P.

    1990-12-01

    The consequences of the failure of the cooling system of fission product storage tanks over a variable period were investigated as part of the safety analysis of the La Hague spent fuel reprocessing plant. Due to the considerable heat release, induced by the fission products, a prolonged shutdown of the tank cooling system could cause the progressive evaporation of the solutions to dryness, and culminate in the formation of volatile species of ruthenium and their release in the tank venting circuit. To determine the fraction of ruthenium likely to be transferred from the storage tanks in volatile or aerosol form during the failure, evaporation tests were conducted by evaporating samples of actual nitric acid solutions of fission products, obtained on the laboratory scale after the reprocessing of several kilograms of MOX fuels irradiated to 30.000 MW day ·t -1 . A distillation apparatus was designed to operate with small-volume solution samples, reproducing the heating conditions existing in the reprocessing plant within a storage tank for fission products. The main conclusions drawn from these experiments are as follows: - ruthenium is only volatilized in the final phase of evaporation, just before desiccation, - for a final temperature limited to 160 deg. C, the total fraction of volatilized ruthenium reaches 12%, - in the presence of H 2 O, HNO 3 , NO x and O 2 , the volatilized ruthenium recombines mainly in the form of ruthenium nitrosyl nitrates, or decomposes into ruthenium oxide (probably RuO 2 ) on the walls of the apparatus. Assuming a heating power density of 10 W/liter of concentrate, and a perfectly adiabatic storage system, the minimum time required to reach dryness can be estimated at 90 h, allowing substantial time to take action to restore a cooling source. It is probable that, in an industrial storage tank, the heat losses from the tank and the offgas discharge ducts will cause recondensation and internal reflux, which will commensurately delay

  2. Atmospheric Pressure Effects on Cryogenic Storage Tank Boil-Off

    Science.gov (United States)

    Sass, J. P.; Frontier, C. R.

    2007-01-01

    The Cryogenics Test Laboratory (CTL) at the Kennedy Space Center (KSC) routinely utilizes cryostat test hardware to evaluate comparative and absolute thermal conductivities of a wide array of insulation systems. The test method is based on measurement of the flow rate of gas evolved due to evaporative boil-off of a cryogenic liquid. The gas flow rate typically stabilizes after a period of a couple of hours to a couple of days, depending upon the test setup. The stable flow rate value is then used to calculate the thermal conductivity for the insulation system being tested. The latest set of identical cryostats, 1,000-L spherical tanks, exhibited different behavior. On a macro level, the flow rate did stabilize after a couple of days; however the stable flow rate was oscillatory with peak to peak amplitude of up to 25 percent of the nominal value. The period of the oscillation was consistently 12 hours. The source of the oscillation has been traced to variations in atmospheric pressure due to atmospheric tides similar to oceanic tides. This paper will present analysis of this phenomenon, including a calculation that explains why other cryostats are not affected by it.

  3. Hanford underground storage tank waste filtration process evaluation

    International Nuclear Information System (INIS)

    Walker, B.W.; McCabe, D.J.

    1997-01-01

    The purpose of this filter study was to evaluate cross-flow filtration as effective solid-liquid separation technology for treating Hanford wastes, outline operating conditions for equipment, examine the expected filter flow rates, and determine proper cleaning. Two Hanford waste processing applications have been identified as candidates for the use of cross-flow filtration. The first of the Hanford applications involves filtration of the decanted supernate from sludge leaching and washing operations. This process involves the concentration and removal of dilute (0.05 wt percent) fines from the bulk of the supernate. The second application involves filtration to wash and concentrate the sludge during out-of-tank processing. This process employs a relatively concentrated (8 wt percent) solids feed stream. Filter studies were conducted with simulants to evaluate whether 0.5 micron cross-flow sintered metal Mott filters and 0.1 micron cross-flow Graver filters can perform solid-liquid separation of the solid/liquid waste streams effectively. In cross-flow filtration the fluid to be filtered flows in parallel to the membrane surface and generates shearing forces and/or turbulence across the filter medium. This shearing influences formation of filter cake stabilizing the filtrate flow rate

  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. 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.

  6. A mounded spherical storage tank at Papeete; Une sphere sous talus a Papeete

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2003-09-01

    Because demand for liquid petroleum gas (LPG) in French Polynesia is burgeoning, deliveries of the product are on the rise, in particular from New Zealand. In consideration of this, Gaz de Tahiti has had a mounded 1.800 m{sup 3} spherical propane storage tank built by the Tissot group. The new tank joins the ranks of the standard 2.500 m{sup 3} spherical butane tank that Gaz de Tahiti already has at its Papeete site. The slope consists of earth-filled gabions, which are at least one metre thick at any point of the steel structure. The project is proof once again that Gaz de Tahiti has no reason to envy European companies when it comes to technology and development. (authors)

  7. 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

  8. Guidelines for development of structural integrity programs for DOE high-level waste storage tanks

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-01-01

    Guidelines are provided for developing programs to promote the structural integrity of high-level waste storage tanks and transfer lines at the facilities of the Department of Energy. Elements of the program plan include a leak-detection system, definition of appropriate loads, collection of data for possible material and geometric changes, assessment of the tank structure, and non-destructive examination. Possible aging degradation mechanisms are explored for both steel and concrete components of the tanks, and evaluated to screen out nonsignificant aging mechanisms and to indicate methods of controlling the significant aging mechanisms. Specific guidelines for assessing structural adequacy will be provided in companion documents. Site-specific structural integrity programs can be developed drawing on the relevant portions of the material in this document.

  9. Feasibility of applying cathodic protection to double-wall waste storage tanks

    International Nuclear Information System (INIS)

    Moore, E.L.

    1977-01-01

    A study was conducted to determine the feasibility of applying impressed current cathodic protection to double-wall storage tanks containing terminal waste solutions. Norton Corrosion Limited concluded that such a system could be designed for installation on the tanks. Under their direction, Battelle Northwest Laboratories conducted a laboratory study to develop necessary data for design of the system. A separate study conducted by Battelle Columbus Laboratories indicated that, while terminal waste solutions by themselves do not promote stress corrosion cracking, cathodic protection may promote this type of corrosion under certain conditions. As a result of these findings, the recommendation was made not to install cathodic protection on the double-wall tanks containing terminal waste solutions

  10. 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.

  11. Oak Ridge National Laboratory Melton Valley Storage Tanks Waste filtration process evaluation

    International Nuclear Information System (INIS)

    Walker, B.W.; McCabe, D.J.

    1997-01-01

    The purpose of this filter study was to evaluate cross-flow filtration as effective solid-liquid separation technology for treating Oak Ridge National Laboratory wastes, outline operating conditions for equipment, examine the expected filter flow rates, and determine proper cleaning.The Gunite Tanks at the Oak Ridge National Laboratory contain heels which are a mixture of sludge, wash water, and bentonite clay. The tanks are to be cleaned out with a variety of flushing techniques and the dilute mixture transferred to another storage tank. One proposal is to transfer this mixture into existing Melton Valley Storage Tanks (MVST), which already contain a large amount of sludge and supernate. The mixed aqueous phase will then be transferred to new MVST, which are prohibited from containing insoluble solids. To separate the solid from the liquid and thereby prevent solids transfer into the new MVST, a technique is needed that can cleanly separate the sludge and bentonite clay from the supernate. One proposed method for solid liquid separation is cross-flow filtration. Cross-flow filtration has been used at the Savannah River and West Valley sites for treatment of tank waste, and is being tested for applicability at other sites. The performance of cross-flow filters with sludge has been tested, but the impact of sludge combined with bentonite clay has not. The objective of this test was to evaluate the feasibility of using cross-flow filters to perform the solid liquid separation required for the mixture of Gunite and MVST tank wastes

  12. Radiological assessment of worker doses during sludge mobilization and removal at the Melton Valley storage tanks

    International Nuclear Information System (INIS)

    Kerr, G.D.; Coleman, R.L.; Kocher, D.C.; Wynn, C.C.

    1996-01-01

    This report presents an assessment of potential radiation doses to workers during mobilization and removal of contaminated sludges from the Melton Valley Storage Tanks at Oak Ridge National Laboratory. The assessment is based on (1) measurements of radionuclide concentrations in sludge and supernatant liquid samples from the waste storage tanks, (2) measurements of gamma radiation levels in various areas that will be accessed by workers during normal activities, (3) calculations of gamma radiation levels for particular exposure situations, especially when the available measurements are not applicable, and (4) assumed scenarios for worker activities in radiation areas. Only doses from external exposure are estimated in this assessment. Doses from internal exposure are assumed to be controlled by containment of radioactive materials or respiratory protection of workers and are not estimated

  13. Radiological assessment of worker doses during sludge mobilization and removal at the Melton Valley storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Kerr, G.D.; Coleman, R.L.; Kocher, D.C.; Wynn, C.C.

    1996-12-17

    This report presents an assessment of potential radiation doses to workers during mobilization and removal of contaminated sludges from the Melton Valley Storage Tanks at Oak Ridge National Laboratory. The assessment is based on (1) measurements of radionuclide concentrations in sludge and supernatant liquid samples from the waste storage tanks, (2) measurements of gamma radiation levels in various areas that will be accessed by workers during normal activities, (3) calculations of gamma radiation levels for particular exposure situations, especially when the available measurements are not applicable, and (4) assumed scenarios for worker activities in radiation areas. Only doses from external exposure are estimated in this assessment. Doses from internal exposure are assumed to be controlled by containment of radioactive materials or respiratory protection of workers and are not estimated.

  14. Sampling and analysis plan for site assessment during the closure or replacement of nonradioactive underground storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Gitt, M.J.

    1990-08-01

    The Tank Management Program is responsible for closure or replacement of nonradioactive underground storage tanks throughout the Idaho National Engineering Laboratory (INEL). A Sampling and Analysis Plan (SAP) has been developed that complies with EPA regulations and with INEL Tank Removal Procedures for sampling activities associated with site assessment during these closure or replacement activities. The SAP will ensure that all data are valid, and it also will function as a Quality Assurance Project Plan. 18 refs., 8 figs., 11 tabs.

  15. Characterization and leaching study of sludge from Melton Valley Storage Tank W-25

    International Nuclear Information System (INIS)

    Collins, J.L.; Egan, B.Z.; Beahm, E.C.; Chase, C.W.; Anderson, K.K.

    1997-08-01

    One of the greatest challenges facing the Department of Energy (DOE) is the remediation of the 100 million gallons of high-level and low-level radioactive waste in the underground storage tanks at its Hanford, Savannah River, Oak Ridge, Idaho, and Fernald sites. Bench-scale batch tests have been conducted with sludge from the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to evaluate separation processes for use in a comprehensive sludge-processing flow sheet for concentrating the radionuclides and reducing the volumes of storage tanks wastes for final disposal. This report discusses the hot cell apparatus, the characterization of the sludge, and the results obtained from a variety of basic and acidic leaching tests of samples of sludge. Approximately 5 L of sludge/supernate from MVST W-25 was retrieved and transferred to a stainless steel tank for mixing and storage in a hot cell. Samples were centrifuged to separate the sludge liquid and the sludge solids. Air-dried samples of sludge were analyzed to determine the concentrations of radionuclides, other metals, and anions. Based upon the air-dried weight, about 41% of the centrifuged, wet sludge solids was water. The major alpha-, gamma-, and beta-emitting radionuclides in the centrifuged, wet sludge solids were 137 Cs, 60 Co, 154 Eu, 241 Am, 244 Cm, 90 Sr, Pu, U, and Th. The other major metals (in addition to the U and Th) and the anions were Na, Ca, Al, K, Mg, NO 3 - , CO 3 2- , OH - , and O 2- . The organic carbon content was 3.0 ± 1.0%. The pH was 13

  16. Characterization and leaching study of sludge from Melton Valley Storage Tank W-25

    Energy Technology Data Exchange (ETDEWEB)

    Collins, J.L.; Egan, B.Z.; Beahm, E.C.; Chase, C.W.; Anderson, K.K.

    1997-08-01

    One of the greatest challenges facing the Department of Energy (DOE) is the remediation of the 100 million gallons of high-level and low-level radioactive waste in the underground storage tanks at its Hanford, Savannah River, Oak Ridge, Idaho, and Fernald sites. Bench-scale batch tests have been conducted with sludge from the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to evaluate separation processes for use in a comprehensive sludge-processing flow sheet for concentrating the radionuclides and reducing the volumes of storage tanks wastes for final disposal. This report discusses the hot cell apparatus, the characterization of the sludge, and the results obtained from a variety of basic and acidic leaching tests of samples of sludge. Approximately 5 L of sludge/supernate from MVST W-25 was retrieved and transferred to a stainless steel tank for mixing and storage in a hot cell. Samples were centrifuged to separate the sludge liquid and the sludge solids. Air-dried samples of sludge were analyzed to determine the concentrations of radionuclides, other metals, and anions. Based upon the air-dried weight, about 41% of the centrifuged, wet sludge solids was water. The major alpha-, gamma-, and beta-emitting radionuclides in the centrifuged, wet sludge solids were {sup 137}Cs, {sup 60}Co, {sup 154}Eu, {sup 241}Am, {sup 244}Cm, {sup 90}Sr, Pu, U, and Th. The other major metals (in addition to the U and Th) and the anions were Na, Ca, Al, K, Mg, NO{sub 3}{sup {minus}}, CO{sub 3}{sup 2{minus}}, OH{sup {minus}}, and O{sub 2{minus}}. The organic carbon content was 3.0 {+-} 1.0%. The pH was 13.

  17. Calculus of cathodic protection system for a storage tank of 42,500 m3

    International Nuclear Information System (INIS)

    Arganis J, C. R.; Mondragon C, L.

    2009-10-01

    This work presents the calculations carried out to install a cathodic protection system for a storage tank of 42,500 m 3 , including the methodology, the taken data of supplier catalogs and finally the realized adjustments at to install the system in field. Also, the data of electrochemical potential in field at to carry out the installation are included, as well as the interference between a system of galvanic current and other of printed current. (Author)

  18. Equipment design guidance document for flammable gas waste storage tank new equipment

    International Nuclear Information System (INIS)

    Smet, D.B.

    1996-01-01

    This document is intended to be used as guidance for design engineers who are involved in design of new equipment slated for use in Flammable Gas Waste Storage Tanks. The purpose of this document is to provide design guidance for all new equipment intended for application into those Hanford storage tanks in which flammable gas controls are required to be addressed as part of the equipment design. These design criteria are to be used as guidance. The design of each specific piece of new equipment shall be required, as a minimum to be reviewed by qualified Unreviewed Safety Question evaluators as an integral part of the final design approval. Further Safety Assessment may be also needed. This guidance is intended to be used in conjunction with the Operating Specifications Documents (OSDs) established for defining work controls in the waste storage tanks. The criteria set forth should be reviewed for applicability if the equipment will be required to operate in locations containing unacceptable concentrations of flammable gas

  19. Algorithms for the interpretation of continuous measurement of the slurry level in storage tanks

    Directory of Open Access Journals (Sweden)

    Fabrizio Mazzetto

    2012-06-01

    Full Text Available This paper describes a device for monitoring the slurry level in storage tanks. In particular, it describes the inference engine used within the StorEyes software. This software was developed by the Authors to interpret and manage data collected from measurements taken by ultrasonic or pressure sensors mounted on slurry tanks for continuous monitoring of the stored effluent level. The monitoring device consists of a data-logger that uses a GPRS device for the wireless transmission of data to a Farm Information System server, a buffer for the temporary storage of data in case of malfunction of the farm network, and a GPS receiver. The inference engine consists of a set of algorithms used to derive from raw measurements (usually in V intelligible information about the loading/unloading events in storage facilities. The inference engine has been tested and calibrated through two years of acquisitions at two pilot farms with different slurry tank loading and unloading management systems.

  20. Technical assessment of compressed hydrogen storage tank systems for automotive applications.

    Energy Technology Data Exchange (ETDEWEB)

    Hua, T. Q.; Ahluwalia, R. K.; Peng, J. K.; Kromer, M.; Lasher, S.; McKenney, K.; Law, K.; Sinha, J. (Nuclear Engineering Division); (TIAX, LLC)

    2011-02-09

    The performance and cost of compressed hydrogen storage tank systems has been assessed and compared to the U.S. Department of Energy (DOE) 2010, 2015, and ultimate targets for automotive applications. The on-board performance and high-volume manufacturing cost were determined for compressed hydrogen tanks with design pressures of 350 bar ({approx}5000 psi) and 700 bar ({approx}10,000 psi) capable of storing 5.6 kg of usable hydrogen. The off-board performance and cost of delivering compressed hydrogen was determined for hydrogen produced by central steam methane reforming (SMR). The main conclusions of the assessment are that the 350-bar compressed storage system has the potential to meet the 2010 and 2015 targets for system gravimetric capacity but will not likely meet any of the system targets for volumetric capacity or cost, given our base case assumptions. The 700-bar compressed storage system has the potential to meet only the 2010 target for system gravimetric capacity and is not likely to meet any of the system targets for volumetric capacity or cost, despite the fact that its volumetric capacity is much higher than that of the 350-bar system. Both the 350-bar and 700-bar systems come close to meeting the Well-to-Tank (WTT) efficiency target, but fall short by about 5%. These results are summarized.

  1. 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

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

    International Nuclear Information System (INIS)

    Sherwood, D.J.

    1994-03-01

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

  3. Resource Conservation and Recovery Act Closure Plan for the Y-12 9409-5 Tank Storage Facility

    International Nuclear Information System (INIS)

    1995-02-01

    This document presents information on the closure of the Y-12 9409-5 Tank Storage Facility. Topics discussed include: facility description; closure history; closure performance standard; partial closure; maximum waste inventory; closure activities; schedule; and postclosure care

  4. AX Tank Farm tank removal study

    Energy Technology Data Exchange (ETDEWEB)

    SKELLY, W.A.

    1999-02-24

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

  5. Performance of a solid oxide fuel cell CHP system coupled with a hot water storage tank for single household

    DEFF Research Database (Denmark)

    Liso, Vincenzo; Zhao, Yingru; Yang, Wenyuan

    2014-01-01

    of heat used for thermal loads of the residence. Two fuels are considered, namely syngas and natural gas. The tank model considers the temperature gradients over the tank height. The results of the numerical simulation is used to size the SOFC system and storage heat tank to provide energy for a small...... of delivering hot water for the household and returning the coldest fluid back to SOFC heat recovery heat-exchanger. A model of the SOFC system is developed to determine the energy required to meet the hourly average electric load of the residence. The model evaluates the amount of heat generated and the amount......In this paper a solid oxide fuel cell (SOFC) system for cogeneration of heat and power integrated with a stratified heat storage tank is studied. Thermal stratification in the tank increases the heat recovery performance as it allows existence of a temperature gradient with the benefit...

  6. Closure report for underground storage tank 161-R1U1 and its associated underground piping

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-05-01

    Underground storage tank (UST) 161-31 R at the Lawrence Livermore National Laboratory (LLNL) was registered with the State Water Resources Control Board on June 27, 1984. UST 161-31R was subsequently renamed UST 161-R1U1 (Fig. A-1, Appendix A). UST 161-R1U1 was installed in 1976, and had a capacity of 383 gallons. This tank system consisted of a fiberglass reinforced plastic tank, approximately 320 feet of polyvinyl chloride (PVC) underground piping from Building 161, and approximately 40 feet of PVC underground piping from Building 160. The underground piping connected laboratory drains and sinks inside Buildings 160 and 161 to UST 161-R1U1. The wastewater collected in UST 161-R1U1, contained organic solvents, metals, inorganic acids, and radionuclides, most of which was produced within Building 161. On June 28, 1989, the UST 161-R1U1 piping system.around the perimeter of Building 161 failed a precision test performed by Gary Peters Enterprises (Appendix B). The 161-R1U1 tank system was removed from service after the precision test. In July 1989, additional hydrostatic tests and helium leak detection tests were performed (Appendix B) to determine the locations of the piping failures in the Building 161 piping system. The locations of the piping system failures are shown in Figure A-2 (Appendix A). On July 11, 1989, LLNL submitted an Unauthorized Release Report to Alameda County Department of Environmental Health (ACDEH), Appendix C.

  7. Demand-Based Optimal Design of Storage Tank with Inerter System

    Directory of Open Access Journals (Sweden)

    Shiming Zhang

    2017-01-01

    Full Text Available A parameter optimal design method for a tank with an inerter system is proposed in this study based on the requirements of tank vibration control to improve the effectiveness and efficiency of vibration control. Moreover, a response indicator and a cost control indicator are selected based on the control targets for liquid storage tanks for simultaneously minimizing the dynamic response and controlling costs. These indicators are reformulated through a random vibration analysis under virtual excitation. The problem is then transformed from a multiobjective optimization problem to a single-objective nonlinear problem using the ε-constraint method, which is consistent with the demand-based method. White noise excitation can be used to design the tank with the inerter system under seismic excitation to simplify the calculation. Subsequently, a MATLAB-based calculation program is compiled, and several optimization cases are examined under different excitation conditions. The effectiveness of the demand-based method is proven through a time history analysis. The results show that specific vibration control requirements can be met at the lowest cost with a simultaneous reduction in base shears and overturning base moments.

  8. Water level response measurement in a steel cylindrical liquid storage tank using image filter processing under seismic excitation

    Science.gov (United States)

    Kim, Sung-Wan; Choi, Hyoung-Suk; Park, Dong-Uk; Baek, Eun-Rim; Kim, Jae-Min

    2018-02-01

    Sloshing refers to the movement of fluid that occurs when the kinetic energy of various storage tanks containing fluid (e.g., excitation and vibration) is continuously applied to the fluid inside the tanks. As the movement induced by an external force gets closer to the resonance frequency of the fluid, the effect of sloshing increases, and this can lead to a serious problem with the structural stability of the system. Thus, it is important to accurately understand the physics of sloshing, and to effectively suppress and reduce the sloshing. Also, a method for the economical measurement of the water level response of a liquid storage tank is needed for the exact analysis of sloshing. In this study, a method using images was employed among the methods for measuring the water level response of a liquid storage tank, and the water level response was measured using an image filter processing algorithm for the reduction of the noise of the fluid induced by light, and for the sharpening of the structure installed at the liquid storage tank. A shaking table test was performed to verify the validity of the method of measuring the water level response of a liquid storage tank using images, and the result was analyzed and compared with the response measured using a water level gauge.

  9. Modelling of a solid oxide fuel cell CHP system coupled with a hot water storage tank for a single household

    DEFF Research Database (Denmark)

    Liso, Vincenzo; Zhao, Yingru; Yang, Wenyuan

    2015-01-01

    is low (for instance during the night), taking advantage of thermal stratification to increases the heat recovery performance. A model of the SOFC system is presented to estimate the energy required to meet the average electric energy demand of the residence. Two fuels are considered, namely syngas...... produced by gasification and natural gas. The tank model considers the temperature gradients over the tank height. The results of the numerical simulation are used to size the SOFC system and storage heat tank to provide energy for a small household using two different fuels. In particular it was shown...... that in the case of syngas, due to larger system heat output, a larger tank volume was required in order to accumulate unused heat over the night. The detailed description of the tank model will be useful to energy system modelers when sizing hot water tanks. Problem formulation is reported also using a Matlab...

  10. The Seismic Fragility Analysis of a Condensate Storage Tank with Age-Related Degradation

    International Nuclear Information System (INIS)

    Choun, Young Sun; Kim, Min Kyu; Choi, In Kil; Nie, Jinsuo; Braverman, Joseph I.; Hofmayer, Charles H.

    2011-01-01

    The rate of age-related degradation in nuclear power plants (NPPs) is not significantly large but increasing as the plants get older. The slow but increasing rate of degradation of structures and passive components (SPCs) can potentially affect the safety of the older plants and become an important factor in decision making in the current trend of extending the operating license period of the plants. This paper investigates the seismic fragility capacity of the condensate storage tank (CST) for five cases: (1) a baseline analysis where the design condition (undegraded) is assumed, (2) a scenario with degraded stainless steel tank shell, (3) a scenario with degraded anchor bolts, (4) a scenario with anchorage concrete cracking, and (5) a perfect correlation of the above three degradation scenarios

  11. 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

  12. Risk Based Inspection Methodology and Software Applied to Atmospheric Storage Tanks

    Science.gov (United States)

    Topalis, P.; Korneliussen, G.; Hermanrud, J.; Steo, Y.

    2012-05-01

    A new risk-based inspection (RBI) methodology and software is presented in this paper. The objective of this work is to allow management of the inspections of atmospheric storage tanks in the most efficient way, while, at the same time, accident risks are minimized. The software has been built on the new risk framework architecture, a generic platform facilitating efficient and integrated development of software applications using risk models. The framework includes a library of risk models and the user interface is automatically produced on the basis of editable schemas. This risk-framework-based RBI tool has been applied in the context of RBI for above-ground atmospheric storage tanks (AST) but it has been designed with the objective of being generic enough to allow extension to the process plants in general. This RBI methodology is an evolution of an approach and mathematical models developed for Det Norske Veritas (DNV) and the American Petroleum Institute (API). The methodology assesses damage mechanism potential, degradation rates, probability of failure (PoF), consequence of failure (CoF) in terms of environmental damage and financial loss, risk and inspection intervals and techniques. The scope includes assessment of the tank floor for soil-side external corrosion and product-side internal corrosion and the tank shell courses for atmospheric corrosion and internal thinning. It also includes preliminary assessment for brittle fracture and cracking. The data are structured according to an asset hierarchy including Plant, Production Unit, Process Unit, Tag, Part and Inspection levels and the data are inherited / defaulted seamlessly from a higher hierarchy level to a lower level. The user interface includes synchronized hierarchy tree browsing, dynamic editor and grid-view editing and active reports with drill-in capability.

  13. The Safe Removal of Frozen Air from the Annulus of an LH2 Storage Tank

    Science.gov (United States)

    Krenn, A.; Starr, S.; Youngquist, R.; Nurge, M.; Sass, J.; Fesmire, J.; Cariker, C.; Bhattacharya, A.

    2015-01-01

    Large Liquid Hydrogen (LH2) storage tanks are vital infrastructure for NASA. Eventually, air may leak into the evacuated and perlite filled annular region of these tanks. Although the vacuum level is monitored in this region, the extremely cold temperature causes all but the helium and neon constituents of air to freeze. A small, often unnoticeable pressure rise is the result. As the leak persists, the quantity of frozen air increases, as does the thermal conductivity of the insulation system. Consequently, a notable increase in commodity boil-off is often the first indicator of an air leak. Severe damage can result from normal draining of the tank. The warming air will sublimate which will cause a pressure rise in the annulus. When the pressure increases above the triple point, the frozen air will begin to melt and migrate downward. Collection of liquid air on the carbon steel outer shell may chill it below its ductility range, resulting in fracture. In order to avoid a structural failure, as described above, a method for the safe removal of frozen air is needed. A thermal model of the storage tank has been created using SINDA/FLUINT modeling software. Experimental work is progressing in an attempt to characterize the thermal conductivity of a perlite/frozen nitrogen mixture. A statistical mechanics model is being developed in parallel for comparison to experimental work. The thermal model will be updated using the experimental/statistical mechanical data, and used to simulate potential removal scenarios. This paper will address methodologies and analysis techniques for evaluation of two proposed air removal methods.

  14. Tank waste remediation system integrated technology plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P. [eds.] [Pacific Northwest Lab., Richland, WA (United States)

    1995-02-28

    The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m{sup 3} (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program.

  15. Tank waste remediation system integrated technology plan. Revision 2

    International Nuclear Information System (INIS)

    Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P.

    1995-01-01

    The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m 3 (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program

  16. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, Caustic Wash Tank And Caustic Storage Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 6 Operations

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B.

    2013-10-01

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Caustic Storage Tank (CST) samples from several of the ''microbatches'' of Integrated Salt Disposition Project (ISDP) Salt Batch (''Macrobatch'') 6 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The results from the current microbatch samples are similar to those from comparable samples in Macrobatch 5. From a bulk chemical point of view, the ICPES results do not vary considerably between this and the previous macrobatch. The titanium results in the DSSHT samples continue to indicate the presence of Ti, when the feed material does not have detectable levels. This most likely indicates that leaching of Ti from MST in ARP continues to occur. Both the CST and CWT samples indicate that the target Free OH value of 0.03 has been surpassed. While at this time there is no indication that this has caused an operational problem, the CST should be adjusted into specification. The {sup 137}Cs results from the SRNL as well as F/H lab data indicate a potential decline in cesium decontamination factor. Further samples will be carefully monitored to investigate this.

  17. Fluid dynamic studies for a simulated Melton Valley Storage Tank slurry

    International Nuclear Information System (INIS)

    Hylton, T.D.; Youngblood, E.L.; Cummins, R.L.

    1994-07-01

    The Melton Valley Storage Tanks (MVSTs), are used for the collection and storage of remote-handled radioactive liquid wastes. These wastes, which were typically acidic when generated, were neutralized with the addition of sodium hydroxide to protect the storage tanks from corrosion, but this caused the transuranic and heavy metals to precipitate. These wastes will eventually need to be removed from the tanks for ultimate disposal. The objective of the research activities discussed in this report is to support the design of a pipeline transport system between the MVSTs and a treatment facility. Since the wastes in the MVSTs are highly radioactive, a surrogate slurry was developed for this study. Rheological properties of the simulated slurry were determined in a test loop in which the slurry was circulated through three pipeline viscometers of different diameters. Pressure drop data at varying flow rates were used to obtain shear stress and shear rate data. The data were analyzed, and the slurry rheological properties were analyzed by the Power Law model and the Bingham plastic model. The plastic viscosity and yield stress data obtained from the rheological tests were used as inputs for a piping design software package, and the pressure drops predicted by the software compared well with the pressure drop data obtained from the test loop. The minimum transport velocity was determine for the slurry by adding known nominal sizes of glass spheres to the slurry. However, it was shown that the surrogate slurry exhibited hindered settling, which may substantially decrease the minimum transport velocity. Therefore, it may be desired to perform additional tests with a surrogate with a lower concentration of suspended solids to determine the minimum transport velocity

  18. Corrosion resistance of tank material for flock storage in the Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sano, Yuichi; Anbai, Hiromu; Takeuchi, Masayuki; Ogino, Hideki; Koizumi, Kenji

    2014-01-01

    The installation of the storage tank made of SS400 is under planning in the Fukushima Daiichi nuclear power plant for the flock which was generated in the coagulation process for radioactive contaminated water. The flock contains the seawater and has a possibility to make a crevice and local corrosion on the surface of the tank. Air agitation will be applied in the storage tank to prevent the accumulation of the flock and hydrogen generated by radiolysis, which will increase the diffusion of oxygen and the corrosion of SS400. In addition, the effect of radiation from the flock on the corrosion should be considered. In this study, we investigated the corrosion behavior of SS400 in the flock under the aeration-agitation condition with γ-ray irradiation. Based on the flock storage condition announced by Tokyo Electric Power Company (TEPCO), immersion tests were performed with SS400 coupons under several conditions and corrosion rates were estimated by the weight loss of the coupons. After the immersion tests, the surfaces of the coupons were observed by microscopy for evaluating the local corrosion. To evaluate corrosion mechanism in detail, electrochemical tests were also carried out. In all of these tests, the non-radioactive flock as a surrogate and artificial seawater were used. Corrosion rates of SS400 increased significantly with aeration flow rates in the seawater with/without the flock, but this tendency was weaker in the seawater with the flock, especially under the condition where coupons were buried in the flock. The electrochemical tests indicated the suppression of the cathodic reaction, i.e. dissolved oxygen reduction, in the seawater with the flock. The effect of γ-ray irradiation on the corrosion rates was not remarkable under the assumed dose rate. Microscopic analysis of the immersed coupons showed no severe corrosion including local corrosion occurred. The corrosion rate could be decreased effectively by suppressing the dissolved oxygen reduction

  19. Standard practice for examination of liquid-Filled atmospheric and Low-pressure metal storage tanks using acoustic emission

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2007-01-01

    1.1 This practice covers guidelines for acoustic emission (AE) examinations of new and in-service aboveground storage tanks of the type used for storage of liquids. 1.2 This practice will detect acoustic emission in areas of sensor coverage that are stressed during the course of the examination. For flat-bottom tanks these areas will generally include the sidewalls (and roof if pressure is applied above the liquid level). The examination may not detect flaws on the bottom of flat-bottom tanks unless sensors are located on the bottom. 1.3 This practice may require that the tank experience a load that is greater than that encountered in normal use. The normal contents of the tank can usually be used for applying this load. 1.4 This practice is not valid for tanks that will be operated at a pressure greater than the examination pressure. 1.5 It is not necessary to drain or clean the tank before performing this examination. 1.6 This practice applies to tanks made of carbon steel, stainless steel, aluminum and oth...

  20. Earthquake and welded structures 5: Earthquake damages and anti-earthquake measures of oil storage tanks; 5 kikenbutsu chozo tank no jishin higai to taishin taisaku

    Energy Technology Data Exchange (ETDEWEB)

    Kawano, K. [Chiyoda Chemical Engineering and Construction Co. Ltd., Tokyo (Japan)

    1997-09-05

    The result of field investigation carried out on the state of damages of 236 hazardous material storage tanks out of 687 caused by the Hyogoken Nambu Earthquake in 1995 is introduced together with the cases of damage and the description of the countermeasures. The events of inclination and settlement of tank bodies were confirmed in 44% among those investigated in particular with tanks having a capacity of less than 1000kl and as for the basement and ground settlement, the fact that sand spouted as a result of their fluidization was witnessed as much as 81% among those investigated and the area surrounding tanks was roughly agreed with the area where ground crack appeared. A great number of other damages such as cracking of preventive seals against rain water, breakdown of oil defense banks and so forth were also confirmed. In the latter half of the report, aseismatic standards of old and new regulations as well as on the new criterion concerning the outdoor storage tank body, its basement and ground are tabulated and 4 items of anti-earthquake measures such as the final structural check up with regard to an earthquake exceeding the designed permissible stress, consolidation of tank body structure on the basis of the revised seismic coefficient method, assurance of the steadfast basement, prevention of the elevated platform from falling down and strengthening of water-proof seals and oil defense banks are enumerated in accordance with the report of investigation and examination on the resistibility of hazardous material storage equipment against the earthquake. 3 refs., 5 figs., 3 tabs.

  1. Performance improvement by discharge from different levels in solar storage tanks

    DEFF Research Database (Denmark)

    Furbo, Simon; Andersen, Elsa; Thür, Alexander

    2005-01-01

    The thermal advantages by utilizing discharge from different levels in solar storage tanks are investigated, both for a small SDHW system and for a solar combisystem. The investigations showed that it is possible to increase the thermal performance of both types of systems by using two draw......-off levels from the solar tanks instead of one draw-off level at a fixed position. The best position of the second draw-off level is in the middle or just above the middle of the tank. For the investigated small SDHW system with a realistic draw off hot water temperature of 40°C and 45°C and an auxiliary...... volume temperature of 50.5°C the increase of the thermal performance by the second draw-off level is about 6%. For the investigated solar combisystem the extra thermal performance by using one extra draw-off level, either for the domestic hot water heat exchanger or for the heating system, is about 3...

  2. 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

  3. Safety evaluation for packaging transportation of equipment for tank 241-C-106 waste sluicing system

    International Nuclear Information System (INIS)

    Calmus, D.B.

    1994-01-01

    A Waste Sluicing System (WSS) is scheduled for installation in nd waste storage tank 241-C-106 (106-C). The WSS will transfer high rating sludge from single shell tank 106-C to double shell waste tank 241-AY-102 (102-AY). Prior to installation of the WSS, a heel pump and a transfer pump will be removed from tank 106-C and an agitator pump will be removed from tank 102-AY. Special flexible receivers will be used to contain the pumps during removal from the tanks. After equipment removal, the flexible receivers will be placed in separate containers (packagings). The packaging and contents (packages) will be transferred from the Tank Farms to the Central Waste Complex (CWC) for interim storage and then to T Plant for evaluation and processing for final disposition. Two sizes of packagings will be provided for transferring the equipment from the Tank Farms to the interim storage facility. The packagings will be designated as the WSSP-1 and WSSP-2 packagings throughout the remainder of this Safety Evaluation for Packaging (SEP). The WSSP-1 packagings will transport the heel and transfer pumps from 106-C and the WSSP-2 packaging will transport the agitator pump from 102-AY. The WSSP-1 and WSSP-2 packagings are similar except for the length

  4. Closure Report for Corrective Action Unit 121: Storage Tanks and Miscellaneous Sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2008-09-01

    Corrective Action Unit (CAU) 121 is identified in the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended February 2008) as Storage Tanks and Miscellaneous Sites. CAU 121 consists of the following three Corrective Action Sites (CASs) located in Area 12 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada: (1) CAS 12-01-01, Aboveground Storage Tank; (2) CAS 12-01-02, Aboveground Storage Tank; and (3) CAS 12-22-26, Drums; 2 AST's. CAU 121 closure activities were conducted according to the FFACO and the Streamlined Approach for Environmental Restoration Plan for CAU 121 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007). Field work took place from February through September 2008. Samples were collected to determine the path forward to close each site. Closure activities were completed as defined in the plan based on sample analytical results and site conditions. No contaminants of concern (COCs) were present at CAS 12-01-01; therefore, no further action was chosen as the corrective action alternative. As a best management practice (BMP), the empty aboveground storage tank (AST) was removed and disposed as sanitary waste. At CAS 12-01-02, polychlorinated biphenyls (PCBs) were present above the preliminary action level (PAL) in the soil beneath the AST that could possibly have originated from the AST contents. Therefore, PCBs were considered COCs, and the site was clean closed by excavating and disposing of soil containing PCBs. Approximately 5 cubic yards (yd{sup 3}) of soil were excavated and disposed as petroleum hydrocarbon PCB remediation waste, and approximately 13 yd3 of soil were excavated and disposed as PCB remediation waste. Cleanup samples were collected to confirm that the remaining soil did not contain PCBs above the PAL. Other compounds detected in the soil above PALs (i.e., total petroleum hydrocarbons [TPH] and semi-volatile organic compounds [SVOCs

  5. 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

  6. 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

  7. 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

  8. 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

  9. Large-volume heat storage tank made of GFK; Grosswaermespeichertank aus GFK

    Energy Technology Data Exchange (ETDEWEB)

    Buehl, J.; Schultheis, P. [Technische Univ. Ilmenau (Germany). Fachgebiet Technische Thermodynamik

    1998-12-31

    The Technical University of Ilmenau, the company Verbundwerkstoff- und Kunststoffanwendungstechnik Schoenbrunn, the Institute for Aerospace and Light-weight construction of Dresden University with its approved testing facilities for plastics and the Institute for Construction Engineering in Berlin and several other institutions co-operated since 1996 in developing a concept for a series of long-term heat storage tanks up to 6,000 cubic metres storage volume made of plastic (GFK components) with a combined thermal insulation. A model tank (sandwich body with proportional thermal insulation layer and selected mixed laminates) with a volume of 1.5 cubic metres was built and installed in November 1996. The tank has been continuously operated at various test levels. The experiment proves the longevity of the materials used. (orig.) [Deutsch] In Zusammenarbeit der TU Ilmenau mit der Fa. Verbundwerkstoff - und Kunststoffanwendungstechnik Schoenbrunn und dem Institut fuer Luftfahrttechnik und Leichtbau Dresden, seiner akkredierten Pruefstelle fuer Kunststoffe, in Abstimmung mit dem Institut fuer Bautechnik Berlin und weiteren Einrichtungen und Partnern wird seit 1996 an einem Konzept fuer eine Typenreihe Langzeitwaermespeicher bis vorerst 6.000 m{sup 3} Speichervolumen aus Kunststoff (GFK-Komponenten) und kombinierter integrierter thermischer Isolation gearbeitet. Im Vorfeld dieser Entwicklung wurde auf der Basis vorausgewaehlter Materialien und Kompositionen ein Musterspeicher (ein Sandwich - Modellkoerper mit proportionaler Waermedaemmschicht sowie ausgewaehlten Mischlaminaten) mit einem Speichervolumen von 1,5 m{sup 3} realisiert. Dieser Musterspeicher wurde im November 1996 installiert und wird seither kontinuierlich in den entsprechenden Erprobungsstufen betrieben. Der Nachweis der Langlebigkeit der eingesetzten Materialien wurde experimentell erbracht. (orig.)

  10. 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

  11. 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...

  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. Combined cooling and purification system for nuclear reactor spent fuel pit, refueling cavity, and refueling water storage tank

    Science.gov (United States)

    Corletti, Michael M.; Lau, Louis K.; Schulz, Terry L.

    1993-01-01

    The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps.

  14. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

    2003-01-01

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, ''Radioactive Waste Management Manual.'' This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility

  15. Experimental determination of the heat transfer and cold storage characteristics of a microencapsulated phase change material in a horizontal tank

    International Nuclear Information System (INIS)

    Allouche, Yosr; Varga, Szabolcs; Bouden, Chiheb; Oliveira, Armando C.

    2015-01-01

    Highlights: • Cold storage characteristics in latent and sensible heat storage mediums were studied. • Thermo-physical characterization of the phase change material was carried out. • A non-Newtonian shear thickening behavior of the phase change material was observed. • An energy storage enhancement (53%) was observed in the latent heat storage medium. - Abstract: In the present paper, the performance of a microencapsulated phase change material (in 45% w/w concentration) for low temperature thermal energy storage, suitable for air conditioning applications is studied. The results are compared to a sensible heat storage unit using water. Thermo-physical properties such as the specific heat, enthalpy variation, thermal conductivity and density are also experimentally determined. The non-Newtonian shear-thickening behavior of the phase change material slurry is quantified. Thermal energy performance is experimentally determined for a 100 l horizontal tank. The heat transfer between the heat transfer fluid and the phase change material was provided by a tube-bundle heat exchanger inside the tank. The results show that the amount of energy stored using the phase change material is 53% higher than for water after 10 h of charging, for the same storage tank volume. It was found that the heat transfer coefficient between the phase change material and the tube wall increases during the phase change temperature range, however it remains smaller than the values obtained for water

  16. An International Survey of Electric Storage Tank Water Heater Efficiency and Standards

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Alissa; Lutz, James; McNeil, Michael A.; Covary, Theo

    2013-11-13

    Water heating is a main consumer of energy in households, especially in temperate and cold climates. In South Africa, where hot water is typically provided by electric resistance storage tank water heaters (geysers), water heating energy consumption exceeds cooking, refrigeration, and lighting to be the most consumptive single electric appliance in the home. A recent analysis for the Department of Trade and Industry (DTI) performed by the authors estimated that standing losses from electric geysers contributed over 1,000 kWh to the annual electricity bill for South African households that used them. In order to reduce this burden, the South African government is currently pursuing a programme of Energy Efficiency Standards and Labelling (EES&L) for electric appliances, including geysers. In addition, Eskom has a history of promoting heat pump water heaters (HPWH) through incentive programs, which can further reduce energy consumption. This paper provides a survey of international electric storage water heater test procedures and efficiency metrics which can serve as a reference for comparison with proposed geyser standards and ratings in South Africa. Additionally it provides a sample of efficiency technologies employed to improve the efficiency of electric storage water heaters, and outlines programs to promote adoption of improved efficiency. Finally, it surveys current programs used to promote HPWH and considers the potential for this technology to address peak demand more effectively than reduction of standby losses alone

  17. IMPACT ASSESSMENT OF EXISTING VADOSE ZONE CONTAMINATION AT THE HANFORD SITE SX TANK FARM

    International Nuclear Information System (INIS)

    KHALEEL R

    2007-01-01

    The USDOE has initiated an impact assessment of existing vadose zone contamination at the Hanford Site SX tank farm in southeastern Washington State. The assessment followed the Resource Conservation and Recovery Act (RCRA) Corrective Action process to address the impacts of past tank waste releases to the vadose zone at the single-shell tank farm. Numerical models were developed that consider the extent of contamination presently within the vadose zone and predict contaminant movement through the vadose zone to groundwater. The transport of representative mobile (technetium-99) and immobile (cesium-137) constituents was evaluated in modeling. The model considered the accelerated movement of moisture around and beneath single-shell tanks that is attributed to bare, gravel surfaces resulting from the construction of the underground storage tanks. Infiltration, possibly nearing 100 mm yr -1 , is further amplified in the tank farm because of the umbrella effect created by percolating moisture being diverted by the impermeable, sloping surface of the large, 24-m-diameter, buried tank domes. For both the base case (no-action alternative) simulation and a simulation that considered placement of an interim surface barrier to minimize infiltration, predicted, groundwater concentrations for technetium-99 at the SX tank farm boundary were exceedingly high, on the order of 10 6 pCi L -1 . The predicted concentrations are, however, somewhat conservative because of our use of two-dimensional modeling for a three-dimensional problem. A series of simulations were performed, using recharge rates of 50, 30, and 10 mm yr -1 , and compared to the basecase(100 mm yr -1 ) results. As expected, lowering meteoric recharge delayed peak arrival times and reduced peak concentrations at the tank farm boundary

  18. Impact Assessment of Existing Vadose Zone Contamination at the Hanford Site SX Tank Farm

    International Nuclear Information System (INIS)

    Khaleel, Raziuddin; White, Mark D.; Oostrom, Martinus; Wood, Marcus I.; Mann, Frederick M.; Kristofzski, John G.

    2007-01-01

    The USDOE has initiated an impact assessment of existing vadose zone contamination at the Hanford Site SX tank farm in southeastern Washington State. The assessment followed the Resource Conservation and Recovery Act (RCRA) Corrective Action process to address the impacts of past tank waste releases to the vadose zone at the single-shell tank farm. Numerical models were developed that consider the extent of contamination presently within the vadose zone and predict contaminant movement through the vadose zone to groundwater. The transport of representative mobile (technetium-99) and immobile (cesium-137) constituents was evaluated in modeling. The model considered the accelerated movement of moisture around and beneath single-shell tanks that is attributed to bare, gravel surfaces resulting from the construction of the underground storage tanks. Infiltration, possibly nearing 100 mm yr -1 , is further amplified in the tank farm because of the umbrella effect created by percolating moisture being diverted by the impermeable, sloping surface of the large, 24-m-diameter, buried tank domes. For both the base case (no-action alternative) simulation and a simulation that considered placement of an interim surface barrier to minimize infiltration, predicted groundwater concentrations for technetium-99 at the SX tank farm boundary were exceedingly high, on the order of 106 pCi L-1. The predicted concentrations are, however, somewhat conservative because of our use of two-dimensional modeling for a three-dimensional problem. A series of simulations were performed, using recharge rates of 50, 30, and 10 mm yr -1 , and compared to the base case (100 mm yr -1 ) results. As expected, lowering meteoric recharge delayed peak arrival times and reduced peak concentrations at the tank farm boundary.

  19. 40 CFR 63.11087 - What requirements must I meet for gasoline storage tanks if my facility is a bulk gasoline...

    Science.gov (United States)

    2010-07-01

    ... gasoline storage tanks if my facility is a bulk gasoline terminal, pipeline breakout station, or pipeline... CATEGORIES (CONTINUED) National Emission Standards for Hazardous Air Pollutants for Source Category: Gasoline... § 63.11087 What requirements must I meet for gasoline storage tanks if my facility is a bulk gasoline...

  20. Implementation of seismic design and evaluation guidelines for the Department of Energy high-level waste storage tanks and appurtenances

    International Nuclear Information System (INIS)

    Conrads, T.J.

    1993-06-01

    In the fall of 1992, a draft of the Seismic Design and Evaluation Guidelines for the Department of Energy (DOE) High-level Waste Storage Tanks and Appurtenances was issued. The guidelines were prepared by the Tanks Seismic Experts Panel (TSEP) and this task was sponsored by DOE, Environmental Management. The TSEP is comprised of a number of consultants known for their knowledge of seismic ground motion and expertise in the analysis of structures, systems and components subjected to seismic loads. The development of these guidelines was managed by staff from Brookhaven National Laboratory, Engineering Research and Applications Division, Department of Nuclear Energy. This paper describes the process used to incorporate the Seismic Design and Evaluation Guidelines for the DOE High-Level Waste Storage Tanks and Appurtenances into the design criteria for the Multi-Function Waste Tank Project at the Hanford Site. This project will design and construct six new high-level waste tanks in the 200 Areas at the Hanford Site. This paper also discusses the vehicles used to ensure compliance to these guidelines throughout Title 1 and Title 2 design phases of the project as well as the strategy used to ensure consistent and cost-effective application of the guidelines by the structural analysts. The paper includes lessons learned and provides recommendations for other tank design projects which might employ the TSEP guidelines