Sample records for shell tank closure

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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 closuremore » 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.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    2012-01-10

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

  3. TANK FARM CLOSURE - A NEW TWIST ON REGULATORY STRATEGIES FOR CLOSURE OF WASTE TANK RESIDUALS FOLLOWING NUREG

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    LEHMAN LL

    2008-01-23

    Waste from a number of single-shell tanks (SST) at the U.S. Department of Energy's (DOE) Hanford Site has been retrieved by CH2M HILL Hanford Group to fulfill the requirements of the 'Hanford Federal Facility Agreement and Consent Order (HFFACO) [1]. Laboratory analyses of the Hanford tank residual wastes have provided concentration data which will be used to determine waste classification and disposal options for tank residuals. The closure of tank farm facilities remains one of the most challenging activities faced by the DOE. This is due in part to the complicated regulatory structures that have developed. These regulatory structures aremore » different at each of the DOE sites, making it difficult to apply lessons learned from one site to the next. During the past two years with the passage of the Section 3116 of the 'Ronald Reagan Defense Authorization Act of 2005' (NDAA) [2] some standardization has emerged for Savannah River Site and the Idaho National Laboratory tank residuals. Recently, with the issuance of 'NRC Staff Guidance for Activities Related to US. Department of Energy Waste Determinations' (NUREG-1854) [3] more explicit options may be considered for Hanford tank residuals than are presently available under DOE Orders. NUREG-1854, issued in August 2007, contains several key pieces of information that if utilized by the DOE in the tank closure process, could simplify waste classification and streamline the NRC review process by providing information to the NRC in their preferred format. Other provisions of this NUREG allow different methods to be applied in determining when waste retrieval is complete by incorporating actual project costs and health risks into the calculation of 'technically and economically practical'. Additionally, the NUREG requires a strong understanding of the uncertainties of the analyses, which given the desire of some NRC/DOE staff may increase the likelihood of using probabilistic approaches to uncertainty analysis. The purpose of this paper is to discuss implications of NUREG-1854 and to examine the feasibility and potential benefits of applying these provisions to waste determinations and supporting documents such as future performance assessments for tank residuals.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Freeman-Pollard, J.R.

    1994-03-02

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

  5. Tank Riser Pit Decontamination System (Pit Viper) Return on Investment and Break-Even Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Young, Joan K.; Weimar, Mark R.; Balducci, Patrick J.

    2003-06-30

    This study assessed the cost benefit of Pit Viper deployment for 80 tank farm pits between October 1, 2003 and September 30, 2012 under the technical baseline for applicable double-shell tank (DST) and single-shell tank (SST) projects. After this assessment had been completed, the U.S. Department of Energy (DOE) Richland Operations Office (RL) and Office of River Protection (ORP) published the Hanford Performance Management Plan (August 2003), which accelerated the schedule for SST retrieval. Then, DOE/CH2M HILL contract modification M064 (October 2002) and The Integrated Mission Acceleration Plan (March 2003) further accelerated SST retrieval and closure schedules. Twenty-six to 40more » tanks must be retrieved by 2006. Thus the schedule for SST pit entries is accelerated and the number of SST pit entries is increased. This study estimates the return on investment (ROI) and the number of pits where Pit Viper deployment would break even or save money over current manual practices. The results of the analysis indicate a positive return on the federal investment for deployment of the Pit Viper provided it is used on a sufficient number of pits.« less

  6. Citizen Contributions to the Closure of High-Level Waste (HLW) Tanks 18 and 19 at the Department of Energy's (DOE) Savannah River Site (SRS) - 13448

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lawless, W.F.

    2013-07-01

    Citizen involvement in DOE's decision-making for the environmental cleanup from DOE's management of its nuclear wastes across the DOE complex has had a positive effect on the cleanup of its SRS site, characterized by an acceleration of cleanup not only for the Transuranic wastes at SRS, but also for DOE's first two closures of HLW tanks, both of which occurred at SRS. The Citizens around SRS had pushed successfully for the closures of Tanks 17 and 20 in 1997, becoming the first closures of HLW tanks under regulatory guidance in the USA. However, since then, HLW tank closures ceased duemore » to a lawsuit, the application of new tank clean-up technology, interagency squabbling between DOE and NRC over tank closure criteria, and finally and almost fatally, from budget pressures. Despite an agreement with its regulators for the closure of Tanks 18 and 19 by the end of calendar year 2012, the outlook in Fall 2011 to close these two tanks had dimmed. It was at this point that the citizens around SRS became reengaged with tank closures, helping DOE to reach its agreed upon milestone. (authors)« less

  7. Groundwater quality assessment plan for single-shell waste management area B-BX-BY at the Hanford Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    SM Narbutovskih

    2000-03-31

    Pacific Northwest National Laboratory conducted a first determination groundwater quality assessment at the Hanford Site. This work was performed for the US Department of Energy, Richland Operations Office, in accordance with the Federal Facility Compliance Agreement during the time period 1996--1998. The purpose of the assessment was to determine if waste from the Single-Shell Tank (SST) Waste Management Area (WMA) B-BX-BY had entered the groundwater at levels above the drinking water standards (DWS). The resulting assessment report documented evidence demonstrating that waste from the WMA has, most likely, impacted groundwater quality. Based on 40 CFR 265.93 [d] paragraph (7), themore » owner-operator must continue to make the minimum required determinations of contaminant level and of rate/extent of migrations on a quarterly basis until final facility closure. These continued determinations are required because the groundwater quality assessment was implemented prior to final closure of the facility.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1998-02-01

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

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.more » 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.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.”

  11. Fracture mechanics analyses of partial crack closure in shell structures

    NASA Astrophysics Data System (ADS)

    Zhao, Jun

    2007-12-01

    This thesis presents the theoretical and finite element analyses of crack-face closure behavior in shells and its effect on the stress intensity factor under a bending load condition. Various shell geometries, such as spherical shell, cylindrical shell containing an axial crack, cylindrical shell containing a circumferential crack and shell with double curvatures, are all studied. In addition, the influence of material orthotropy on the crack closure effect in shells is also considered. The theoretical formulation is developed based on the shallow shell theory of Delale and Erdogan, incorporating the effect of crack-face closure at the compressive edges. The line-contact assumption, simulating the crack-face closure at the compressive edges, is employed so that the contact force at the closure edges is introduced, which can be translated to the mid-plane of the shell, accompanied by an additional distributed bending moment. The unknown contact force is computed by solving a mixed-boundary value problem iteratively, that is, along the crack length, either the normal displacement of the crack face at the compressive edges is equal to zero or the contact pressure is equal to zero. It is found that due to the curvature effects crack closure may not always occur on the entire length of the crack, depending on the direction of the bending load and the geometry of the shell. The crack-face closure influences significantly the magnitude of the stress intensity factors; it increases the membrane component but decreases the bending component. The maximum stress intensity factor is reduced by the crack-face closure. The significant influence of geometry and material orthotropy on rack closure behavior in shells is also predicted based on the analytical solutions. Three-dimensional FEA is performed to validate the theoretical solutions. It demonstrates that the crack face closure occurs actually over an area, not on a line, but the theoretical solutions of the stress intensity factor and the FEA solutions are in good agreement, because the contact area is very small compared with the shell thickness.

  12. Environmental Assessment for the Closure of the High-Level Waste Tanks in F- & H-Areas at the Savannah River Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    N /A

    1996-07-31

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the closure of 51 high-level radioactive waste tanks and tank farm ancillary equipment (including transfer lines, evaporators, filters, pumps, etc) at the Savannah River Site (SRS) located near Aiken, South Carolina. The waste tanks are located in the F- and H-Areas of SRS and vary in capacity from 2,839,059 liters (750,000 gallons) to 4,921,035 liters (1,300,000 gallons). These in-ground tanks are surrounded by soil to provide shielding. The F- and H-Area High-Level Waste Tanks are operated under the authoritymore » of Industrial Wastewater Permits No.17,424-IW; No.14520, and No.14338 issued by the South Carolina Department of Health and Environmental Control (SCDHEC). In accordance with the Permit requirements, DOE has prepared a Closure Plan (DOE, 1996) and submitted it to SCDHEC for approval. The Closure Plan identifies all applicable or relevant and appropriate regulations, statutes, and DOE Orders for closing systems operated under the Industrial Wastewater Permits. When approved by SCDHEC, the Closure Plan will present the regulatory process for closing all of the F- and H-Area High Level Waste Tanks. The Closure Plan establishes performance objectives or criteria to be met prior to closing any tank, group of tanks, or ancillary tank farm equipment. The proposed action is to remove the residual wastes from the tanks and to fill the tanks with a material to prevent future collapse and bind up residual waste, to lower human health risks, and to increase safety in and around the tanks. If required, an engineered cap consisting of clay, backfill (soil), and vegetation as the final layer to prevent erosion would be applied over the tanks. The selection of tank system closure method will be evaluated against the following Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) criteria described in 40 CFR 300.430(e)(9): ( 1) overall protection of human health and the environment; (2) compliance with applicable or relevant and appropriated requirement: (ARARs); (3) long-term effectiveness and permanence; (4) reduction of toxicity, mobility, or volume through treatment; (5) short-term effectiveness; (6) implementability; (7) cost; (8) state acceptable; and (9) community acceptance. Closure of each tank involves two separate operations after bulk waste removal has been accomplished: (1) cleaning of the tank (i.e., removing the residual contaminants), and (2) the actual closure or filling of the tank with an inert material, (e.g., grout). This process would continue until all the tanks and ancillary equipment and systems have been closed. This is expected to be about year 2028 for Type I, II, and IV tanks and associated systems. Subsequent to that, Type III tanks and systems will be closed.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    MACKEY, T.C.

    2006-03-17

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

  14. 49 CFR 179.100-17 - Closures for openings.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100-17 Closures for...

  15. 49 CFR 179.100-17 - Closures for openings.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100-17 Closures for...

  16. 49 CFR 179.100-17 - Closures for openings.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100-17 Closures for...

  17. 49 CFR 179.220-22 - Closure for openings.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-22 Closure for openings...

  18. 49 CFR 179.200-21 - Closures for openings.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-21 Closures for openings...

  19. 49 CFR 179.220-22 - Closure for openings.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-22 Closure for openings...

  20. 49 CFR 179.200-21 - Closures for openings.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-21 Closures for openings...

  1. 49 CFR 179.200-15 - Closures for manways.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-15 Closures for manways...

  2. 49 CFR 179.200-21 - Closures for openings.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-21 Closures for openings...

  3. 49 CFR 179.200-15 - Closures for manways.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-15 Closures for manways...

  4. 49 CFR 179.200-15 - Closures for manways.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-15 Closures for manways...

  5. EXTRACTION APPARATUS

    DOEpatents

    Ballard, A.E.; Brigham, H.R.

    1958-10-28

    An apparatus whereby relatlvely volatile solvents may be contacted with volatile or non-volatile material without certaln attendant hazards is described. A suitable apparatus for handling relatively volatlle liqulds may be constructed comprising a tank, and a closure covering the tank and adapted to be securely attached to an external suppont. The closure is provided with a rigidly mounted motor-driven agitator. This agitator is connected from the driving motor lnto the lnterlor of the tank through a gland adapted to be cooled witb inert gas thereby eliminating possible hazard due to frictional heat. The closure is arranged so that the tank may be removed from it without materially dlsturbing the closure which, as described, carrles the motor driven agitator and other parts.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Restoration

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

  7. Method for Detecting Perlite Compaction in Large Cryogenic Tanks

    NASA Technical Reports Server (NTRS)

    Youngquist, Robert

    2010-01-01

    Perlite is the most typical insulating powder used to separate the inner and outer shells of cryogenic tanks. The inner tank holds the low-temperature commodity, while the outer shell is exposed to the ambient temperature. Perlite minimizes radiative energy transfer between the two tanks. Being a powder, perlite will settle over time, leading to the danger of transferring any loads from the inner shell to the outer shell. This can cause deformation of the outer shell, leading to damaged internal fittings. The method proposed is to place strain or displacement sensors on several locations of the outer shell. Loads induced on the shell by the expanding inner shell and perlite would be monitored, providing an indication of the location and degree of compaction.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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. Communicating Performance Assessments Results - 13609

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Layton, Mark

    2013-07-01

    The F-Area Tank Farms (FTF) and H-Area Tank Farm (HTF) are owned by the U.S. Department of Energy (DOE) and operated by Savannah River Remediation LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF and HTF are active radioactive waste storage and treatment facilities consisting of 51 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. Performance Assessments (PAs) for each Tank Farm have been prepared to support the eventual closure of the underground radioactive waste tanks and ancillary equipment. PAs provide the technical bases and results to bemore » used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of the Tank Farms. The Tank Farms are subject to a number of regulatory requirements. The State regulates Tank Farm operations through an industrial waste water permit and through a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Closure documentation will include State-approved Tank Farm Closure Plans and tank-specific closure modules utilizing information from the PAs. For this reason, the State of South Carolina and the EPA must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. PAs are performance-based, risk-informed analyses of the fate and transport of FTF and HTF residual wastes following final closure of the Tank Farms. Since the PAs serve as the primary risk assessment tools in evaluating readiness for closure, it is vital that PA conclusions be communicated effectively. In the course of developing the FTF and HTF PAs, several lessons learned have emerged regarding communicating PA results. When communicating PA results it is important to stress that the primary goal of the PA results is to provide risk understanding, recognizing the magnitude of risk and identifying the conceptual model decisions and critical assumptions that most impact the results. Conceptual models that describe reality using simplified, mathematical approaches, and their roles in arriving at the PA results, must also be communicated. When presenting PA results, evaluations will typically be focused on a single baseline (or Base Case) to provide a foundation for discussion. The PA results are supplemented by other studies (alternate configurations, uncertainty analyses, and sensitivity analyses) which provide a breadth of modeling to supplement the Base Case. The suite of information offered by the various modeling cases and studies provides confidence that the overall risk is understood along with the underlying parameters and conditions that contribute to risk. (author)« less

  10. Preliminary Sizing Study of Ares-I and Ares-V Liquid Hydrogen Tanks

    NASA Technical Reports Server (NTRS)

    Oliver, Stanley T.; Harper, David W.

    2012-01-01

    A preliminary sizing study of two cryogenic propellant tanks was performed using a FORTRAN optimization program to determine weight efficient orthogrid designs for the tank barrels sections only. Various tensile and compressive failure modes were considered, including general buckling of cylinders with a shell buckling knockdown factor. Eight independent combinations of three design requirements were also considered and their effects on the tanks weight. The approach was to investigate each design case with a variable shell buckling knockdown factor, determining the most weight efficient combination of orthogrid design parameters. Numerous optimization analyses were performed, and the results presented herein compare the effects of the different design requirements and shell buckling knockdown factor. Through a series of comparisons between design requirements or shell buckling knockdown factors, the relative change in overall tank barrel weights is shown. The findings indicate that the design requirements can substantually increase the tank weight while a less conservative shell buckling knockdown factor can modestly reduce the tank weight.

  11. Hanford Double-Shell Tank Inspection Annual Report Calendar Year 2012

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Petermann, Tasha M.; Boomer, Kayle D.; Washenfelder, D. J.

    2013-12-02

    The double-shell tanks (DSTs) were constructed between 1968 and 1986. They will have exceeded their design life before the waste can be removed and trasferred to the Waste Treatment and Immobilization Plant for vitrification. The Double-Shell Tank Integrity Project has been established to evaluate tank aging, and ensure that each tank is structurally sound for continued use. This is the first issue of the Double-Shell Tank Inspection Annual Report. The purpose of this issue is to summarize the results of DST inspections conducted from the beginnng of the inspection program through the end of CY2012. Hereafter, the report will bemore » updated annually with summaries of the past year's DST inspection activities.« less

  12. 49 CFR 178.338-1 - General requirements.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... outer shell or jacket, with insulation between the inner vessel and outer shell or jacket, and having... specification, tank means inner vessel and jacket means either the outer shell or insulation cover. (c) Each.... (1) Each cargo tank must have an insulation system that will prevent the tank pressure from exceeding...

  13. 49 CFR 178.338-1 - General requirements.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... outer shell or jacket, with insulation between the inner vessel and outer shell or jacket, and having... specification, tank means inner vessel and jacket means either the outer shell or insulation cover. (c) Each.... (1) Each cargo tank must have an insulation system that will prevent the tank pressure from exceeding...

  14. 49 CFR 178.338-1 - General requirements.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... outer shell or jacket, with insulation between the inner vessel and outer shell or jacket, and having... specification, tank means inner vessel and jacket means either the outer shell or insulation cover. (c) Each.... (1) Each cargo tank must have an insulation system that will prevent the tank pressure from exceeding...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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 themore » 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 the concrete tanks, looking for cracks and other surface conditions that may indicate signs of structural distress. The condition of the concrete and rebar of the Hanford Single-Shell Tanks is currently being tested and planned for additional activities in the near future. Concrete and rebar removed from the dome of a 65 year old tank was tested for mechanics properties and condition. Results indicated stronger than designed concrete with additional Petrographic examination and rebar completed. Material properties determined from previous efforts combined with current testing and construction document review will help to generate a database that will provide indication of Hanford Single-Shell Tank structural integrity.« less

  16. The Integration of the 241-Z Building Decontamination and Decommissioning Under Cercla with RCRA Closure at the Plutonium Finishing Plant

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mattlin, E.; Charboneau, S.; Johnston, G.

    2007-07-01

    The 241-Z treatment and storage tanks, a hazardous waste Treatment, Storage and Disposal (TSD) unit permitted pursuant to the Resource Conservation and Recovery Act of 1976 (RCRA) and Washington State Hazardous Waste Management Act, RCW 70.105, , have been deactivated and are being actively decommissioned under the provisions of the Hanford Federal Facility Agreement and Consent Order (HFFACO), RCRA and Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) 42 U.S.C. 9601 et seq. The 241-Z TSD unit managed non-listed radioactive contaminated waste water, containing trace RCRA characteristic constituents. The 241-Z TSD unit consists of below grade tanks (D-4,more » D-5, D-7, D-8, and an overflow tank) located in a concrete containment vault, sample glovebox GB-2-241-ZA, and associated ancillary piping and equipment. The tank system is located beneath the 241-Z building. The 241-Z building is not a portion of the TSD unit. The sample glovebox is housed in the above-grade building. Waste managed at the TSD unit was received via underground piping from Plutonium Finishing Plant (PFP) sources. Tank D-6, located in the D-6 vault cell, is a past-practice tank that was taken out of service in 1972 and has never operated as a portion of the RCRA TSD unit. CERCLA actions will address Tank D-6, its containment vault cell, and soil beneath the cell that was potentially contaminated during past-practice operations and any other potential past-practice contamination identified during 241-Z closure, while outside the scope of the Hanford Facility Dangerous Waste Closure Plan, 241-Z Treatment and Storage Tanks. Under the RCRA closure plan, the 241-Z TSD unit is anticipated to undergo clean closure to the performance standards of the State of Washington with respect to dangerous waste contamination from RCRA operations. The TSD unit will be clean closed if physical closure activities identified in the plan achieve clean closure standards for all 241-Z locations. Clean closed 241-Z treatment and storage tanks, equipment and/or structures will remain after RCRA clean closure for future disposition in conjunction with PFP decommissioning activities which are integrated with CERCLA. (authors)« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Washenfelder, Dennis J.

    2014-04-10

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

  18. 40 CFR 280.71 - Permanent closure and changes-in-service.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.71 Permanent closure and changes... sludges. All tanks taken out of service permanently must also be either removed from the ground or filled with an inert solid material. (c) Continued use of an UST system to store a non-regulated substance is...

  19. 40 CFR 280.71 - Permanent closure and changes-in-service.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.71 Permanent closure and changes... sludges. All tanks taken out of service permanently must also be either removed from the ground or filled with an inert solid material. (c) Continued use of an UST system to store a non-regulated substance is...

  20. 40 CFR 280.71 - Permanent closure and changes-in-service.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.71 Permanent closure and changes... sludges. All tanks taken out of service permanently must also be either removed from the ground or filled with an inert solid material. (c) Continued use of an UST system to store a non-regulated substance is...

  1. 40 CFR 280.71 - Permanent closure and changes-in-service.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.71 Permanent closure and changes... sludges. All tanks taken out of service permanently must also be either removed from the ground or filled with an inert solid material. (c) Continued use of an UST system to store a non-regulated substance is...

  2. 49 CFR 178.338-11 - Discharge control devices.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... water capacity, remote means of automatic closure must be installed at the ends of the cargo tank in at... control system. (ii) On a cargo tank motor vehicle of 3,500 gallons water capacity or less, at least one remote means of automatic closure must be installed on the end of the cargo tank farthest away from the...

  3. 78 FR 75913 - Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-13

    ... Subtitle C barrier, a multi-layer barrier designed to provide 500-year protection. \\2\\ Under Tank Closure..., which means the tanks, ancillary equipment, and contaminated soil would be removed, and the remaining... Hanford barrier, a multi- layer barrier designed to provide 1,000-year protection. Alternative 6: All...

  4. 49 CFR 179.221 - Individual specification requirements applicable to tank car tanks consisting of an inner...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Individual specification requirements applicable to tank car tanks consisting of an inner container supported within an outer shell. 179.221 Section... within an outer shell. ...

  5. Commercial Submersible Mixing Pump For SRS Tank Waste Removal - 15223

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hubbard, Mike; Herbert, James E.; Scheele, Patrick W.

    The Savannah River Site Tank Farms have 45 active underground waste tanks used to store and process nuclear waste materials. There are 4 different tank types, ranging in capacity from 2839 m 3 to 4921 m 3 (750,000 to 1,300,000 gallons). Eighteen of the tanks are older style and do not meet all current federal standards for secondary containment. The older style tanks are the initial focus of waste removal efforts for tank closure and are referred to as closure tanks. Of the original 51 underground waste tanks, six of the original 24 older style tanks have completed waste removalmore » and are filled with grout. The insoluble waste fraction that resides within most waste tanks at SRS requires vigorous agitation to suspend the solids within the waste liquid in order to transfer this material for eventual processing into glass filled canisters at the Defense Waste Processing Facility (DWPF). SRS suspends the solid waste by use of recirculating mixing pumps. Older style tanks generally have limited riser openings which will not support larger mixing pumps, since the riser access is typically 58.4 cm (23 inches) in diameter. Agitation for these tanks has been provided by four long shafted standard slurry pumps (SLP) powered by an above tank 112KW (150 HP) electric motor. The pump shaft is lubricated and cooled in a pressurized water column that is sealed from the surrounding waste in the tank. Closure of four waste tanks has been accomplished utilizing long shafted pump technology combined with heel removal using multiple technologies. Newer style waste tanks at SRS have larger riser openings, allowing the processing of waste solids to be accomplished with four large diameter SLPs equipped with 224KW (300 HP) motors. These tanks are used to process the waste from closure tanks for DWPF. In addition to the SLPs, a 224KW (300 HP) submersible mixer pump (SMP) has also been developed and deployed within older style tanks. The SMPs are product cooled and product lubricated canned motor pumps designed to fit within available risers and have significant agitation capabilities to suspend waste solids. Waste removal and closure of two tanks has been accomplished with agitation provided by 3 SMPs installed within the tanks. In 2012, a team was assembled to investigate alternative solids removal technologies to support waste removal for closing tanks. The goal of the team was to find a more cost effective approach that could be used to replace the current mixing pump technology. This team was unable to identify an alternative technology outside of mixing pumps to support waste agitation and removal from SRS waste tanks. However, the team did identify a potentially lower cost mixing pump compared to the baseline SLPs and SMPs. Rather than using the traditional procurement using an engineering specification, the team proposed to seek commercially available submersible mixer pumps (CSMP) as alternatives to SLPs and SMPs. SLPs and SMPs have a high procurement cost and the actual cost of moving pumps between tanks has shown to be significantly higher than the original estimates that justified the reuse of SMPs and SLPs. The team recommended procurement of “off-the-shelf” industry pumps which may be available for significant savings, but at an increased risk of failure and reduced operating life in the waste tank. The goal of the CSMP program is to obtain mixing pumps that could mix from bulk waste removal through tank closure and then be abandoned in place as part of tank closure. This paper will present the development, progress and relative advantages of the CSMP.« less

  6. 49 CFR 179.220 - General specifications applicable to nonpressure tank car tanks consisting of an inner container...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false General specifications applicable to nonpressure tank car tanks consisting of an inner container supported within an outer shell (class DOT-115). 179... within an outer shell (class DOT-115). ...

  7. 49 CFR 179.220 - General specifications applicable to nonpressure tank car tanks consisting of an inner container...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false General specifications applicable to nonpressure tank car tanks consisting of an inner container supported within an outer shell (class DOT-115). 179... within an outer shell (class DOT-115). ...

  8. F-Tank Farm Performance Assessment Updates through the Special Analysis Process at Savannah River Site - 12169

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Layton, Mark H.

    2012-07-01

    The F-Area Tank Farm (FTF) is owned by the U.S. Department of Energy and operated by Savannah River Remediation, LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF is in the north-central portion of the SRS and occupies approximately 22 acres within F-Area. The FTF is an active radioactive waste storage facility consisting of 22 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. An FTF Performance Assessment (PA) was prepared to support the eventual closure of the FTF underground radioactive waste tanks and ancillary equipment. The PA providesmore » the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified below for final closure of FTF. The FTank Farm is subject to a state industrial waste water permit and Federal Facility Agreement. Closure documentation will include an F-Tank Farm Closure Plan and tank-specific closure modules utilizing information from the performance assessment. For this reason, the State of South Carolina and the Environmental Protection Agency must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. The projected waste tank inventories in the FTF PA provide reasonably bounding FTF inventory projections while taking into account uncertainties in the effectiveness of future tank cleaning technologies. As waste is removed from the FTF waste tanks, the residual contaminants will be sampled and the remaining residual inventory is characterized. In this manner, tank specific data for the tank inventories at closure will be available to supplement the waste tank inventory projections currently used in the FTF PA. For FTF, the new tank specific data will be evaluated through the Special Analysis process. The FTF Special Analyses process will be utilized to evaluate information regarding the final residual waste that will be grouted in place in the FTF Tanks and assess the potential impact the new inventory information has on the FTF PA assumptions and results. The Special Analysis can then be used to inform decisions regarding FTF tank closure documents. The purpose of this paper is to discuss the Special Analysis process and share insights gained while implementing this process. An example of an area of interest in the revision process is balancing continuous improvement versus configuration control of agreed upon methodologies. Other subjects to be covered include: 1) defining the scope of the revisions included in the Special Analysis, 2) determining which PA results should be addressed in the Special Analysis, and 3) deciding whether the Special Analysis should utilize more qualitative or quantitative assessments. For the SRS FTF, an FTF PA has been prepared to provide the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of FTF. The FTF Special Analyses process will be utilized to evaluate the impact new information has on the FTF PA assumptions and results. The Special Analysis can then be used to inform decisions regarding FTF tank closure documents. In preparing SAs, it is crucial that the scope of the SA be well defined within the SA, since the specific scope will vary from SA to SA. Since the SAs are essentially addendums to the PA, the SA scope should utilize the PA as the baseline from which the SA scope is defined. The SA needs to focus on evaluating the change associated with the scope, and not let other changes interfere with the ability to perform that evaluation by masking the impact of the change. In preparing the SA, it is also important to let the scope determine whether the Special Analysis should utilize more qualitative or quantitative assessments and also which results from the PA should be addressed in the Special Analysis. These decisions can vary from SA and should not be predetermined. (author)« less

  9. Assessment of single-shell tank residual-liquid issues at Hanford Site, Washington

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Murthy, K.S.; Stout, L.A.; Napier, B.A.

    1983-06-01

    This report provides an assessment of the overall effectiveness and implications of jet pumping the interstitial liquids (IL) from single-shell tanks at Hanford. The jet-pumping program, currently in progress at Hanford, involves the planned removal of IL contained in 89 of the 149 single-shell tanks and its transfer to double-shell tanks after volume reduction by evaporation. The purpose of this report is to estimate the public and worker doses associated with (1) terminating pumping immediately, (2) pumping to a 100,000-gal limit per tank, (3) pumping to a 50,000-gal limit per tank, and (4) pumping to the maximum practical liquid removalmore » level of 30,000 gal. Assessment of the cost-effectiveness of these various levels of pumping in minimizing any undue health and safety risks to the public or worker is also presented.« less

  10. 49 CFR 179.220-25 - Stamping.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ...: Material ASTM A240-316L. Shell thickness Shell 0.167 in. Head thickness Head 0.150 in. Tank builders initials ABC. Date of original test 00-0000. Outer shell: Material ASTM A285-C. Tank builders initials WYZ...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Feero, Amie J.; Washenfelder, Dennis J.; Johnson, Jeremy M.

    2013-11-14

    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.

  12. Expert Panel Recommendations for Hanford Double-Shell Tank Life Extension

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stewart, Charles W; Bush, Spencer H; Berman, Herbert Stanton

    2001-06-29

    Expert workshops were held in Richland in May 2001 to review the Hanford Double-Shell Tank Integrity Project and make recommendations to extend the life of Hanford's double-shell waste tanks. The workshop scope was limited to corrosion of the primary tank liner, and the main areas for review were waste chemistry control, tank inspection, and corrosion monitoring. Participants were corrosion experts from Hanford, Savannah River Site, Brookhaven National Lab., Pacific Northwest National Lab., and several consultants. This report describes the current state of the three areas of the program, the final recommendations of the workshop, and the rationale for their selection.

  13. Ecological Data in Support of the Tank Closure and Waste Management Environmental Impact Statement. Part 2: Results of Spring 2007 Field Surveys

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sackschewsky, Michael R.; Downs, Janelle L.

    2007-05-31

    This review provides an evaluation of potential impacts of actions that have been proposed under various alternatives to support the closure of the high level waste tanks on the Hanford Site. This review provides a summary of data collected in the field during the spring of 2007 at all of the proposed project sites within 200 East and 200 West Areas, and at sites not previously surveyed. The primary purpose of this review is to provide biological data that can be incorporated into or used to support the Tank Closure and Waste Management Environmental Impact Statement.

  14. Dawning of the N =32 Shell Closure Seen through Precision Mass Measurements of Neutron-Rich Titanium Isotopes

    NASA Astrophysics Data System (ADS)

    Leistenschneider, E.; Reiter, M. P.; Ayet San Andrés, S.; Kootte, B.; Holt, J. D.; Navrátil, P.; Babcock, C.; Barbieri, C.; Barquest, B. R.; Bergmann, J.; Bollig, J.; Brunner, T.; Dunling, E.; Finlay, A.; Geissel, H.; Graham, L.; Greiner, F.; Hergert, H.; Hornung, C.; Jesch, C.; Klawitter, R.; Lan, Y.; Lascar, D.; Leach, K. G.; Lippert, W.; McKay, J. E.; Paul, S. F.; Schwenk, A.; Short, D.; Simonis, J.; Somà, V.; Steinbrügge, R.; Stroberg, S. R.; Thompson, R.; Wieser, M. E.; Will, C.; Yavor, M.; Andreoiu, C.; Dickel, T.; Dillmann, I.; Gwinner, G.; Plaß, W. R.; Scheidenberger, C.; Kwiatkowski, A. A.; Dilling, J.

    2018-02-01

    A precision mass investigation of the neutron-rich titanium isotopes Ti-5551 was performed at TRIUMF's Ion Trap for Atomic and Nuclear science (TITAN). The range of the measurements covers the N =32 shell closure, and the overall uncertainties of the Ti-5552 mass values were significantly reduced. Our results conclusively establish the existence of the weak shell effect at N =32 , narrowing down the abrupt onset of this shell closure. Our data were compared with state-of-the-art ab initio shell model calculations which, despite very successfully describing where the N =32 shell gap is strong, overpredict its strength and extent in titanium and heavier isotones. These measurements also represent the first scientific results of TITAN using the newly commissioned multiple-reflection time-of-flight mass spectrometer, substantiated by independent measurements from TITAN's Penning trap mass spectrometer.

  15. Technical Review of Retrieval and Closure Plans for the INEEL INTEC Tank Farm Facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bamberger, Judith A; Burks, Barry L; Quigley, Keith D

    2001-09-28

    The purpose of this report is to document the conclusions of a technical review of retrieval and closure plans for the Idaho National Energy and Environmental Laboratory (INEEL) Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility. In addition to reviewing retrieval and closure plans for these tanks, the review process served as an information exchange mechanism so that staff in the INEEL High Level Waste (HLW) Program could become more familiar with retrieval and closure approaches that have been completed or are planned for underground storage tanks at the Oak Ridge National Laboratory (ORNL) and Hanford sites. Thismore » review focused not only on evaluation of the technical feasibility and appropriateness of the approach selected by INEEL but also on technology gaps that could be addressed through utilization of technologies or performance data available at other DOE sites and in the private sector. The reviewers, Judith Bamberger of Pacific Northwest National Laboratory (PNNL) and Dr. Barry Burks of The Providence Group Applied Technology, have extensive experience in the development and application of tank waste retrieval technologies for nuclear waste remediation.« less

  16. 49 CFR 178.345-7 - Circumferential reinforcements.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... stiffeners which prevent visual inspection of the cargo tank shell are prohibited on cargo tank motor... PACKAGINGS Specifications for Containers for Motor Vehicle Transportation § 178.345-7 Circumferential reinforcements. (a) A cargo tank with a shell thickness of less than 3/8 inch must be circumferentially...

  17. 49 CFR 178.345-7 - Circumferential reinforcements.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... stiffeners which prevent visual inspection of the cargo tank shell are prohibited on cargo tank motor... PACKAGINGS Specifications for Containers for Motor Vehicle Transportation § 178.345-7 Circumferential reinforcements. (a) A cargo tank with a shell thickness of less than 3/8 inch must be circumferentially...

  18. 49 CFR 178.345-7 - Circumferential reinforcements.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... stiffeners which prevent visual inspection of the cargo tank shell are prohibited on cargo tank motor... PACKAGINGS Specifications for Containers for Motor Vehicle Transportation § 178.345-7 Circumferential reinforcements. (a) A cargo tank with a shell thickness of less than 3/8 inch must be circumferentially...

  19. 49 CFR 178.345-7 - Circumferential reinforcements.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... stiffeners which prevent visual inspection of the cargo tank shell are prohibited on cargo tank motor... PACKAGINGS Specifications for Containers for Motor Vehicle Transportation § 178.345-7 Circumferential reinforcements. (a) A cargo tank with a shell thickness of less than 3/8 inch must be circumferentially...

  20. 49 CFR 178.345-7 - Circumferential reinforcements.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... stiffeners which prevent visual inspection of the cargo tank shell are prohibited on cargo tank motor... PACKAGINGS Specifications for Containers for Motor Vehicle Transportation § 178.345-7 Circumferential reinforcements. (a) A cargo tank with a shell thickness of less than 3/8 inch must be circumferentially...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.

  2. Software For Design And Analysis Of Tanks And Cylindrical Shells

    NASA Technical Reports Server (NTRS)

    Luz, Paul L.; Graham, Jerry B.

    1995-01-01

    Skin-stringer Tank Analysis Spreadsheet System (STASS) computer program developed for use as preliminary design software tool that enables quick-turnaround design and analysis of structural domes and cylindrical barrel sections in propellant tanks or other cylindrical shells. Determines minimum required skin thicknesses for domes and cylindrical shells to withstand material failure due to applied pressures (ullage and/or hydrostatic) and runs buckling analyses on cylindrical shells and skin-stringers. Implemented as workbook program, using Microsoft Excel v4.0 on Macintosh II. Also implemented using Microsoft Excel v4.0 for Microsoft Windows v3.1 IBM PC.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.

  5. Investigation of residual stresses in tank car shells in the vicinity of weld ends

    DOT National Transportation Integrated Search

    1997-01-01

    A large number of cracks which develop in railroad tank car : shells form near the ends of skip welds which are used to attach : stiffeners to the tank. The development and growth of these cracks in : fatigue are affected by the presence of residual ...

  6. Treatment options for tank farms long-length contaminated equipment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Josephson, W.S.

    1995-10-16

    This study evaluated a variety of treatment and disposal technologies for mixed waste (MW) meeting the following criteria: 1. Single-Shell and Double-Shell Tank System (tank farms) equipment and other debris; 2. length greater than 12 feet; and contaminated with listed MW from the tank farms. This waste stream, commonly referred to as tank farms long-length contaminated equipment (LLCE), poses a unique and costly set of challenges during all phases of the waste management lifecycle.

  7. 49 CFR 178.337-6 - Closure for manhole.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Containers for Motor Vehicle Transportation § 178.337-6 Closure for manhole. (a) Each cargo tank marked or...), except that a cargo tank constructed of NQT steel having a capacity of 3,500 water gallons or less may be provided with an inspection opening conforming to paragraph UG-46 and other applicable requirements of the...

  8. 49 CFR 178.337-6 - Closure for manhole.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Containers for Motor Vehicle Transportation § 178.337-6 Closure for manhole. (a) Each cargo tank marked or...), except that a cargo tank constructed of NQT steel having a capacity of 3,500 water gallons or less may be provided with an inspection opening conforming to paragraph UG-46 and other applicable requirements of the...

  9. 49 CFR 178.337-6 - Closure for manhole.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Containers for Motor Vehicle Transportation § 178.337-6 Closure for manhole. (a) Each cargo tank marked or...), except that a cargo tank constructed of NQT steel having a capacity of 3,500 water gallons or less may be provided with an inspection opening conforming to paragraph UG-46 and other applicable requirements of the...

  10. 49 CFR 178.337-6 - Closure for manhole.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Containers for Motor Vehicle Transportation § 178.337-6 Closure for manhole. (a) Each cargo tank marked or...), except that a cargo tank constructed of NQT steel having a capacity of 3,500 water gallons or less may be provided with an inspection opening conforming to paragraph UG-46 and other applicable requirements of the...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Martin, Todd M.; Gunter, Jason R.; Boomer, Kayle D.

    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.

  12. Annual Report, Fall 2016: Identifying Cost Effective Tank Waste Characterization Approaches

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reboul, S. H.; DiPrete, D. P.

    2016-12-12

    This report documents the activities that were performed during the second year of a project undertaken to improve the cost effectiveness and timeliness of SRNL’s tank closure characterization practices. The activities performed during the first year of the project were previously reported in SRNL-STI-2015-00144. The scope of the second year activities was divided into the following three primary tasks: 1) develop a technical basis and strategy for improving the cost effectiveness and schedule of SRNL’s tank closure characterization program; 2) initiate the design and assembly of a new waste removal system for improving the throughput and reducing the personnel dosemore » associated with extraction chromatography radiochemical separations; and 3) develop and perform feasibility testing of three alternative radiochemical separation protocols holding promise for improving high resource demand/time consuming tank closure sample analysis methods.« less

  13. Engineering Task Plan for the Ultrasonic Inspection of Hanford Double Shell Tanks (DST) FY2000

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    JENSEN, C.E.

    2000-01-10

    This document facilitates the ultrasonic examination of Hanford double-shell tanks. Included are a plan for engineering activities (individual responsibilities), plan for performance demonstration testing, and a plan for field activities (tank inspection). Also included are a Statement of Work for contractor performance of the work and a protocol to be followed should tank flaws that exceed the acceptance criteria be discovered.

  14. Tank tread assemblies with track-linking mechanism

    NASA Technical Reports Server (NTRS)

    Collins, Earl R., Jr. (Inventor)

    1986-01-01

    The proposed tank tread assembly has adjacent tank tread segments joined by a link bearing tapered pins retained by clips inserted through the tread shells perpendicular to the axes of the pin. It also has highway pads attached by a release rod bearing tapered, grooved cams which interlockingly engage tabs inserted into the tread shells.

  15. 49 CFR 178.345-1 - General requirements.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... a fillet weld joining the tank shell to a flange shaped to fit the shell contour. (d) A manufacturer... be constructed with the cargo tanks made to the same specification or to different specifications...) Specification DOT 406, DOT 407 and DOT 412 cargo tank motor vehicles must conform to the requirements of this...

  16. Measuring Air Leaks into the Vacuum Space of Large Liquid Hydrogen Tanks

    NASA Technical Reports Server (NTRS)

    Youngquist, Robert; Starr, Stanley; Nurge, Mark

    2012-01-01

    Large cryogenic liquid hydrogen tanks are composed of inner and outer shells. The outer shell is exposed to the ambient environment while the inner shell holds the liquid hydrogen. The region between these two shells is evacuated and typically filled with a powderlike insulation to minimize radiative coupling between the two shells. A technique was developed for detecting the presence of an air leak from the outside environment into this evacuated region. These tanks are roughly 70 ft (approx. equal 21 m) in diameter (outer shell) and the inner shell is roughly 62 ft (approx. equal 19 m) in diameter, so the evacuated region is about 4 ft (approx. equal 1 m) wide. A small leak's primary effect is to increase the boil-off of the tank. It was preferable to install a more accurate fill level sensor than to implement a boil-off meter. The fill level sensor would be composed of an accurate pair of pressure transducers that would essentially weigh the remaining liquid hydrogen. This upgrade, allowing boil-off data to be obtained weekly instead of over several months, is ongoing, and will then provide a relatively rapid indication of the presence of a leak.

  17. Hanford Double-Shell Tank Extent-of-Condition Review - 15498

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Johnson, J. M.; Baide, D. D.; Barnes, T. J.

    2014-11-19

    During routine visual inspections of Hanford double-shell waste tank 241-AY-102 (AY-102), anomalies were identified on the annulus floor which resulted in further evaluations. Following a formal leak assessment in October 2012, Washington River Protection Solutions, LLC (WRPS) determined that the primary tank of AY-102 was leaking. A formal leak assessment, documented in RPP-ASMT-53793, Tank 241-AY-102 Leak Assessment Report, identified first-of-a-kind construction difficulties and trial-and-error repairs as major contributing factors to tank failure.1 To determine if improvements in double-shell tank (DST) construction occurred after construction of tank AY-102, a detailed review and evaluation of historical construction records was performed for Hanford’smore » remaining twenty-seven DSTs. Review involved research of 241 boxes of historical project documentation to better understand the condition of the Hanford DST farms, noting similarities in construction difficulties/issues to tank AY-102. Information gathered provides valuable insight regarding construction difficulties, future tank operations decisions, and guidance of the current tank inspection program. Should new waste storage tanks be constructed in the future, these reviews also provide valuable lessons-learned.« less

  18. Effect Of N = 40 Shell Closure On Barrier Distributions In 18O+58,60Ni Reactions

    NASA Astrophysics Data System (ADS)

    Danu, L. S.; Nayak, B. K.; Saxena, A.; Biswas, D. C.; John, B. V.; Thomas, R. G.; Gupta, Y. K.; Choudhury, R. K.

    2009-03-01

    The quasi-elastic scattering measurements for 18O+58,62Ni systems have been carried out at Θlab = 150° around Coulomb barrier energies to investigate the effect of nuclear shell closure on the barrier distributions. The 18O+58Ni system leads to N = 40 neutron shell closure and 18O+62Ni system is having N = 44 in the compound system. It is observed that target 2+ and 3-, projectile 2+ inelastic and 2n-transfer couplings are required in coupled-channels fusion model (CCFULL) calculations to get good comparison with the experimental barrier distribution of 18O+62Ni system, whereas projectile 2+ inelastic state coupling is not required for 18O+58Ni system. However, the low energy structure observed in the barrier distribution of 18O+58Ni system is not reproduced by coupled-channels calculations. This suggests, a possible additional effect due to N = 40 shell closure in the compound system not accounted for in coupled-channels calculations.

  19. 49 CFR 179.100-17 - Closures for openings.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION HAZARDOUS MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100...

  20. 241-AY Double Shell Tanks (DST) Integrity Assessment Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    JENSEN, C.E.

    1999-09-21

    This report presents the results of the integrity assessment of the 241-AY double-shell tank farm facility located in the 200 East Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations. are made to ensure the continued safe operation of the tanks.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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. Themore » 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 a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard. 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 8 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs.« less

  2. 49 CFR 179.200-21 - Closures for openings.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION HAZARDOUS MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-21...

  3. 49 CFR 179.200-15 - Closures for manways.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION HAZARDOUS MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.200-15...

  4. ICPP tank farm closure study. Volume 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Spaulding, B.C.; Gavalya, R.A.; Dahlmeir, M.M.

    1998-02-01

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

  5. HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT SEISMIC ANALYSIS IN SUPPORT OF INCREASED LIQUID LEVEL IN 241-AP TANK FARMS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    MACKEY TC; ABBOTT FG; CARPENTER BG

    2007-02-16

    The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST System at Hanford. The "Double-Shell Tank (DST) Integrity Project - DST Thermal and Seismic Project" is in support of Tri-Party Agreement Milestone M-48-14.

  6. 49 CFR 179.400-10 - Sump or siphon bowl.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... of weldable quality metal that is compatible with the inner tank shell; (b) The stress in any orientation under any condition does not exceed the circumferential stress in the inner tank shell; and (c...

  7. Study on collision resistance characteristics of the side tanks with water inside

    NASA Astrophysics Data System (ADS)

    Liu, Yuxi; Hu, Jinwen; Liu, Ting; Wu, Can

    2018-05-01

    When we evaluate the safety performance of ships against external events, one of the most important indicator is the collision resistance to which water inside the side tanks also make some contributions because of the water effect. To further analyze the interaction mechanism, different collision velocities and side tank waterlines are set for the analysis model. Results indicate the outside shell and the inner shell of the side structure significantly enhanced the collision resistance performance to a certain extension. The water effect on the failure of the outside shell is unobvious, while, it performs a great influence on the destructive reaction force of the inner shell. When the velocity of the coming bulbous bow gradually increases, the destructive reaction forces of the outside shell and the inner shell increase with a decreasing rate. Besides, water influence the collision characteristics of the inner shell a lot when the waterlines are below the upper rib of the strong frame.

  8. 49 CFR 179.400-10 - Sump or siphon bowl.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... metal that is compatible with the inner tank shell; (b) The stress in any orientation under any condition does not exceed the circumferential stress in the inner tank shell; and (c) The wall thickness is...

  9. 49 CFR 179.400-10 - Sump or siphon bowl.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... metal that is compatible with the inner tank shell; (b) The stress in any orientation under any condition does not exceed the circumferential stress in the inner tank shell; and (c) The wall thickness is...

  10. 49 CFR 179.400-10 - Sump or siphon bowl.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... metal that is compatible with the inner tank shell; (b) The stress in any orientation under any condition does not exceed the circumferential stress in the inner tank shell; and (c) The wall thickness is...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Venetz, Theodore J.; Johnson, Jeremy M.; Gunter, Jason R.

    2013-11-14

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

  12. Semi-analytical approach to estimate railroad tank car shell puncture

    DOT National Transportation Integrated Search

    2011-03-16

    This paper describes the development of engineering-based equations to estimate the puncture resistance of railroad tank cars under a generalized shell or side impact scenario. Resistance to puncture is considered in terms of puncture velocity, which...

  13. Analysis of full-scale tank car shell impact tests

    DOT National Transportation Integrated Search

    2007-09-11

    This paper describes analyses of a railroad tank car : impacted at its side by a ram car with a rigid punch. This : generalized collision, referred to as a shell impact, is examined : using nonlinear finite element analysis (FEA) and threedimensional...

  14. Lateral Earth Pressure at Rest and Shear Modulus Measurements on Hanford Sludge Simulants

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wells, Beric E.; Jenks, Jeromy WJ; Boeringa, Gregory K.

    2010-09-30

    This report describes the equipment, techniques, and results of lateral earth pressure at rest and shear modulus measurements on kaolin clay as well as two chemical sludge simulants. The testing was performed in support of the problem of hydrogen gas retention and release encountered in the double- shell tanks (DSTs) at the Hanford Site near Richland, Washington. Wastes from single-shell tanks (SSTs) are being transferred to double-shell tanks (DSTs) for safety reasons (some SSTs are leaking or are in danger of leaking), but the available DST space is limited.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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 waysmore » 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.« less

  16. 33 CFR 155.815 - Tank vessel integrity.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Tank vessel integrity. 155.815..., Procedures, Equipment, and Records § 155.815 Tank vessel integrity. (a) Except as provided in paragraph (b) of this section, a tank vessel underway or at anchor must have all closure mechanisms on the...

  17. 33 CFR 155.815 - Tank vessel integrity.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Tank vessel integrity. 155.815..., Procedures, Equipment, and Records § 155.815 Tank vessel integrity. (a) Except as provided in paragraph (b) of this section, a tank vessel underway or at anchor must have all closure mechanisms on the...

  18. 49 CFR 179.201-6 - Manways and manway closures.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION HAZARDOUS MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.201-6... in AAR Specifications for Tank Cars, appendix M, M3.03 (IBR, see § 171.7 of this subchapter). [Amdt...

  19. Tanks focus area multiyear program plan FY97-FY99

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1996-08-01

    The U.S. Department of Energy (DOE) continues to face a major tank remediation problem with approximately 332 tanks storing over 378,000 ml of high-level waste (HLW) and transuranic (TRU) waste across the DOE complex. Most of the tanks have significantly exceeded their life spans. Approximately 90 tanks across the DOE complex are known or assumed to have leaked. Some of the tank contents are potentially explosive. These tanks must be remediated and made safe. How- ever, regulatory drivers are more ambitious than baseline technologies and budgets will support. Therefore, the Tanks Focus Area (TFA) began operation in October 1994. Themore » focus area manages, coordinates, and leverages technology development to provide integrated solutions to remediate problems that will accelerate safe and cost-effective cleanup and closure of DOE`s national tank system. The TFA is responsible for technology development to support DOE`s four major tank sites: Hanford Site (Washington), INEL (Idaho), Oak Ridge Reservation (ORR) (Tennessee), and Savannah River Site (SRS) (South Carolina). Its technical scope covers the major functions that comprise a complete tank remediation system: safety, characterization, retrieval, pretreatment, immobilization, and closure.« less

  20. Analysis of railroad tank car shell impacts using finite element method

    DOT National Transportation Integrated Search

    2008-04-22

    This paper examines impacts to the side of railroad tank : cars by a ram car with a rigid indenter using dynamic, : nonlinear finite element analysis (FEA). Such impacts are : referred to as shell impacts. Here, nonlinear means elasticplastic : mater...

  1. Chemical composition of Hanford Tank SY-102

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Birnbaum, E.; Agnew, S.; Jarvinen, G.

    1993-12-01

    The US Department of Energy established the Tank Waste Remediation System (TWRS) to safely manage and dispose of the radioactive waste, both current and future, stored in double-shell and single-shell tanks at the Hanford sites. One major program element in TWRS is pretreatment which was established to process the waste prior to disposal using the Hanford Waste Vitrification Plant. In support of this program, Los Alamos National Laboratory has developed a conceptual process flow sheet which will remediate the entire contents of a selected double-shelled underground waste tank, including supernatant and sludge, into forms that allow storage and final disposalmore » in a safe, cost-effective and environmentally sound manner. The specific tank selected for remediation is 241-SY-102 located in the 200 West Area. As part of the flow sheet development effort, the composition of the tank was defined and documented. This database was built by examining the history of liquid waste transfers to the tank and by performing careful analysis of all of the analytical data that have been gathered during the tank`s lifetime. In order to more completely understand the variances in analytical results, material and charge balances were done to help define the chemistry of the various components in the tank. This methodology of defining the tank composition and the final results are documented in this report.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Venetz, Theodore J.; Washenfelder, Dennis J.; Boomer, Kayle D.

    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 Changemore » Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement.« less

  3. Application of welded steel sandwich panels for tank car shell impact protection.

    DOT National Transportation Integrated Search

    2013-04-01

    This report describes research conducted to examine the application of sandwich structure technology to provide protection against the threat of an indenter striking the side or shell of a tank car in the event of an accident. This research was condu...

  4. Application of welded steel sandwich panels for tank car shell impact protection

    DOT National Transportation Integrated Search

    2013-04-30

    This report describes research conducted to examine the application of sandwich structure technology to provide protection against the threat of an indenter striking the side or shell of a tank car in the event of an accident. This research was condu...

  5. AT on Buried LPG Tanks Over 13 m3: An Innovative and Practical Solution

    NASA Astrophysics Data System (ADS)

    Di Fratta, Crescenzo; Ferraro, Antonio; Tscheliesnig, Peter; Lackner, Gerald; Correggia, Vincenzo; Altamura, Nicola

    In Italy, since 2005, techniques based on Acoustic Emission have been introduced for testing of underground LPG tanks up to 13 m3, according to the European standard EN 12818:2004. The testing procedure for these tanks plans to install one or more pairs of sensors inside the "dome" suited for the access to the valves and fittings of the tank, directly on the accessible metal shell. This methodology is not applicable for the underground LPG buried tanks, where it is necessary to install a larger number of AE sensors, in order to cover at 100% the whole tank shell, even at very deep positions. Already in 2004, the European standard EN 12820 (Appendix C - Informative)give the possibility to use Acoustic Emission testing of LPG underground or buried tanks with a capacity exceeding 13 m3, but no technique was specified for the application. In 2008, TÜV AUSTRIA ITALIA - BLU SOLUTIONS srl - Italian company of TÜV AUSTRIA Group - has developed a technique to get access at tank shell, where tank capacity is greater than 13 m3 and its' diameter greater than 3,5 m. This methodology was fully in comply with the provisions of the European Standard EN 12819:2010, becoming an innovative solution widely appreciated and is used in Italy since this time. Currently, large companies and petrochemical plants, at the occurrence of the tank's requalification, have engaged TÜV AUSTRIA ITALIA - BLU SOLUTIONS to install such permanent predispositions, which allow access to the tank shell - test object - with diameters from 4 to 8 m. Through this access, you can install the AE sensors needed to cover at 100% the tank surface and then to perform AE test. In an economic crisis period, this technique is proving a valid and practically applicable answer, in order to reduce inspection costs and downtime by offering a technically advanced solution (AT), increasing the safety of the involved operators, protecting natural resources and the environment.

  6. EFFECTS OF CHEMISTRY AND OTHER VARIABLES ON CORROSION AND STRESS CORROSION CRACKING IN HANFORD DOUBLE SHELL TANKS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BROWN MH

    2008-11-13

    Laboratory testing was performed to develop a comprehensive understanding of the corrosivity of the tank wastes stored in Double-Shell Tanks using simulants primarily from Tanks 241-AP-105, 241-SY-103 and 241-AW-105. Additional tests were conducted using simulants of the waste stored in 241-AZ-102, 241-SY-101, 241-AN-107, and 241-AY-101. This test program placed particular emphasis on defining the range of tank waste chemistries that do not induce the onset of localized forms of corrosion, particularly pitting and stress corrosion cracking. This document summarizes the key findings of the research program.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cantrell, Kirk J.; Zachara, John M.; Dresel, P. Evan

    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).

  8. DOE Office of Scientific and Technical Information (OSTI.GOV)

    SAMS TL; GUILLOT S

    Scoping laboratory scale tests were performed at the Chemical Engineering Department of the Georgia Institute of Technology (Georgia Tech), and the Hanford 222-S Laboratory, involving double-shell tank (DST) and single-shell tank (SST) Hanford waste simulants. These tests established the viability of the Lithium Hydrotalcite precipitation process as a solution to remove aluminum and recycle sodium hydroxide from the Hanford tank waste, and set the basis of a validation test campaign to demonstrate a Technology Readiness Level of 3.

  9. THE INTEGRATION OF THE 241-Z BUILDING DECONTAMINATION & DECOMMISSIONING (D&D) UNDER COMPREHENSIVE ENVIRONMENTAL RESPONSE COMPENSATION & LIABILITY ACT (CERCLA) WITH RESOURCE CONSERVATION & RECOVERY ACT (RCRA) CLOSURE AT THE PLUTONIUM FINISHING PLANT (PFP)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    HOPKINS, A.M.

    2007-02-20

    The 241-Z treatment and storage tanks, a hazardous waste Treatment, Storage and Disposal (TSD) unit permitted pursuant to the ''Resource Conservation and Recovery Act of 1976'' (RCRA) and Washington State ''Hazardous Waste Management Act, RCW 70.105'', have been deactivated and are being actively decommissioned. The 241-Z TSD unit managed non-listed radioactive contaminated waste water, containing trace RCRA characteristic constituents. The 241-Z TSD unit consists of below grade tanks (D-4, D-5, D-7, D-8, and an overflow tank) located in a concrete containment vault, sample glovebox GB-2-241-ZA, and associated ancillary piping and equipment. The tank system is located beneath the 241-Z building.more » The 241-Z building is not a portion of the TSD unit. The sample glovebox is housed in the above-grade building. Waste managed at the TSD unit was received via underground mining from Plutonium Finishing Plant (PFP) sources. Tank D-6, located in the D-6 vault cell, is a past-practice tank that was taken out of service in 1972 and has never operated as a portion of the RCRA TSD unit. CERCLA actions address Tank D-6, its containment vault cell, and soil beneath the cell that was potentially contaminated during past-practice operations and any other potential past-practice contamination identified during 241-Z closure, while outside the scope of the ''Hanford Facility Dangerous Waste Closure Plant, 241-Z Treatment and Storage Tanks''.« less

  10. 49 CFR 179.221 - Individual specification requirements applicable to tank car tanks consisting of an inner...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.221 Individual specification... to tank car tanks consisting of an inner container supported within an outer shell. 179.221 Section...

  11. 49 CFR 179.221 - Individual specification requirements applicable to tank car tanks consisting of an inner...

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.221 Individual specification... to tank car tanks consisting of an inner container supported within an outer shell. 179.221 Section...

  12. 49 CFR 178.345-1 - General requirements.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ...) All specification requirements are minimum requirements. (c) Definitions. See § 178.320(a) for the... flange, or by a fillet weld joining the tank shell to a flange shaped to fit the shell contour. (d) A... be constructed with the cargo tanks made to the same specification or to different specifications...

  13. 78 FR 14122 - Revocation of Permanent Variances

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-04

    ... these tanks involves attaching curved steel plates together to form the outer surface of a tank. After attaching a horizontal layer (ring) of steel plates around the circumference of the existing shell, employees raise the scaffolds to attach the next ring of steel plates onto the existing shell. Steel mills...

  14. Evaluation of semi-empirical analyses for tank car puncture velocity, part II : correlations with engineering analyses

    DOT National Transportation Integrated Search

    2001-11-01

    This report is the second in a series focusing on methods to determine the puncture velocity of railroad tank car shells. In this context, puncture velocity refers to the impact velocity at which a coupler will completely pierce the shell and punctur...

  15. Evaluation of semi-empirical analyses for railroad tank car puncture velocity, part 2 : correlations with engineering analysis

    DOT National Transportation Integrated Search

    2001-11-01

    This report is the second in a series focusing on methods to determine the puncture velocity of railroad tank car shells. In this : context, puncture velocity refers to the impact velocity at which a coupler will completely pierce the shell and punct...

  16. Enterobacteriaceae and related organisms recovered from biofilms in a commercial shell egg processing facility.

    USDA-ARS?s Scientific Manuscript database

    During six visits, biofilms from egg contact and non-contact surfaces in a commercial shell egg processing facility were sampled. Thirty-five different sample sites were selected: Pre-wash and wash tanks (lids, screens, tank interiors, nozzle guards), post-wash spindles, blower filters, belts (far...

  17. Evaluation of Flygt Propeller Xixers for Double Shell Tank (DST) High Level Waste Auxiliary Solids Mobilization

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    PACQUET, E.A.

    The River Protection Project (RPP) is planning to retrieve radioactive waste from the single-shell tanks (SST) and double-shell tanks (DST) underground at the Hanford Site. This waste will then be transferred to a waste treatment plant to be immobilized (vitrified) in a stable glass form. Over the years, the waste solids in many of the tanks have settled to form a layer of sludge at the bottom. The thickness of the sludge layer varies from tank to tank, from no sludge or a few inches of sludge to about 15 ft of sludge. The purpose of this technology and engineeringmore » case study is to evaluate the Flygt{trademark} submersible propeller mixer as a potential technology for auxiliary mobilization of DST HLW solids. Considering the usage and development to date by other sites in the development of this technology, this study also has the objective of expanding the knowledge base of the Flygt{trademark} mixer concept with the broader perspective of Hanford Site tank waste retrieval. More specifically, the objectives of this study delineated from the work plan are described.« less

  18. 49 CFR 179.201-6 - Manways and manway closures.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.201-6 Manways and manway... Specifications for Tank Cars, appendix M, M3.03 (IBR, see § 171.7 of this subchapter). [Amdt. 179-10, 36 FR 21353...

  19. 49 CFR 179.201-6 - Manways and manway closures.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.201-6 Manways and manway... Specifications for Tank Cars, appendix M, M3.03 (IBR, see § 171.7 of this subchapter). [Amdt. 179-10, 36 FR 21353...

  20. 49 CFR 179.201-6 - Manways and manway closures.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.201-6 Manways and manway... Specifications for Tank Cars, appendix M, M3.03 (IBR, see § 171.7 of this subchapter). [Amdt. 179-10, 36 FR 21353...

  1. Staged depressurization system

    DOEpatents

    Schulz, T.L.

    1993-11-02

    A nuclear reactor having a reactor vessel disposed in a containment shell is depressurized in stages using depressurizer valves coupled in fluid communication with the coolant circuit. At least one sparger submerged in the in-containment refueling water storage tank which can be drained into the containment sump communicates between one or more of the valves and an inside of the containment shell. The depressurizer valves are opened in stages, preferably at progressively lower coolant levels and for opening progressively larger flowpaths to effect depressurization through a number of the valves in parallel. The valves can be associated with a pressurizer tank in the containment shell, coupled to a coolant outlet of the reactor. At least one depressurization valve stage openable at a lowest pressure is coupled directly between the coolant circuit and the containment shell. The reactor is disposed in the open sump in the containment shell, and a further valve couples the open sump to a conduit coupling the refueling water storage tank to the coolant circuit for adding water to the coolant circuit, whereby water in the containment shell can be added to the reactor from the open sump. 4 figures.

  2. Staged depressurization system

    DOEpatents

    Schulz, Terry L.

    1993-01-01

    A nuclear reactor having a reactor vessel disposed in a containment shell is depressurized in stages using depressurizer valves coupled in fluid communication with the coolant circuit. At least one sparger submerged in the in-containment refueling water storage tank which can be drained into the containment sump communicates between one or more of the valves and an inside of the containment shell. The depressurizer valves are opened in stages, preferably at progressively lower coolant levels and for opening progressively larger flowpaths to effect depressurization through a number of the valves in parallel. The valves can be associated with a pressurizer tank in the containment shell, coupled to a coolant outlet of the reactor. At least one depressurization valve stage openable at a lowest pressure is coupled directly between the coolant circuit and the containment shell. The reactor is disposed in the open sump in the containment shell, and a further valve couples the open sump to a conduit coupling the refueling water storage tank to the coolant circuit for adding water to the coolant circuit, whereby water in the containment shell can be added to the reactor from the open sump.

  3. 40 CFR 280.74 - Closure records.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... following ways: (a) By the owners and operators who took the UST system out of service; (b) By the current... STANDARDS AND CORRECTIVE ACTION REQUIREMENTS FOR OWNERS AND OPERATORS OF UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.74 Closure records. Owners and operators must maintain...

  4. 40 CFR 280.74 - Closure records.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... following ways: (a) By the owners and operators who took the UST system out of service; (b) By the current... STANDARDS AND CORRECTIVE ACTION REQUIREMENTS FOR OWNERS AND OPERATORS OF UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.74 Closure records. Owners and operators must maintain...

  5. 40 CFR 280.74 - Closure records.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... following ways: (a) By the owners and operators who took the UST system out of service; (b) By the current... STANDARDS AND CORRECTIVE ACTION REQUIREMENTS FOR OWNERS AND OPERATORS OF UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.74 Closure records. Owners and operators must maintain...

  6. 40 CFR 280.74 - Closure records.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... following ways: (a) By the owners and operators who took the UST system out of service; (b) By the current... STANDARDS AND CORRECTIVE ACTION REQUIREMENTS FOR OWNERS AND OPERATORS OF UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.74 Closure records. Owners and operators must maintain...

  7. 40 CFR 280.74 - Closure records.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... following ways: (a) By the owners and operators who took the UST system out of service; (b) By the current... STANDARDS AND CORRECTIVE ACTION REQUIREMENTS FOR OWNERS AND OPERATORS OF UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.74 Closure records. Owners and operators must maintain...

  8. 49 CFR 179.220 - General specifications applicable to nonpressure tank car tanks consisting of an inner container...

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... tank car tanks consisting of an inner container supported within an outer shell (class DOT-115). 179... AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220...

  9. Old and New Magic Numbers

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Talmi, Igal

    2008-11-11

    The discovery of magic numbers led to the shell model. They indicated closure of major shells and are robust: proton magic numbers are rather independent of the occupation of neutron orbits and vice versa. Recently the magic property became less stringent and we hear a lot about the discovery of new magic numbers. These, however, indicate sub-shell closures and strongly depend on occupation numbers and hence, may be called quasi-magic numbers. Some of these have been known for many years and the mechanism for their appearance as well as disappearance, was well understood within the simple shell model. The situationmore » will be illustrated by a few examples which demonstrate the simple features of the shell model. Will this simplicity emerge from the complex computations of nuclear many-body theory?.« less

  10. 1999 Leak Detection and Monitoring and Mitigation Strategy Update

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    OHL, P.C.

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

  11. Hanford Double-Shell Tank AY-102 Radioactive Waste Leak Investigation Update - 15302

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Washenfelder, D. J.; Johnson, J. M.

    2014-12-22

    Tank AY-102 was the first of 28 double-shell radioactive waste storage tanks constructed at the U. S. Department of Energy’s Hanford Site, near Richland, WA. The tank was completed in 1970, and entered service in 1971. In August, 2012, an accumulation of material was discovered at two sites on the floor of the annulus that separates the primary tank from the secondary liner. The material was sampled and determined to originate from the primary tank. This paper summarizes the changes in leak behavior that have occurred during the past two years, inspections to determine the capability of the secondary linermore » to continue safely containing the leakage, and the initial results of testing to determine the leak mechanism.« less

  12. Properties of r-process nuclei near N=82 shell closure

    NASA Astrophysics Data System (ADS)

    Farhan, A. R.; Sharma, M. M.

    2004-10-01

    We have studied properties of nuclei in r-process region near N=82 shell closure with the RMF calculations in a deformed basis using the force NL-SV1 that includes vector self-coupling of w meson. It is shown that nuclei above N=82 in several isotopic chains in the r-process region exhibit an onset of deformation beyond the drip line. Consequently, induced by the deformation these nuclei show an extra stability above the shell closure. This stability of nuclei is expected to contribute to the r-process nucleosynthesis of nuclei below the abundance peak at A ˜130. A comparison with the mass formulae shows that our microscopic calculations with NL-SV1 show a decrease of shell strength with increase in isospin. This is in contrast to the strong shell effects shown by FRDM and ETF-SI in going to the drip line. The stiffness of the shell structure with FRDM and ETF-SI is known to lead to a shortfall in the r-process abundances. This shortcoming of the above mass formulae has inspired an ad-hoc inclusion of shell quenching in the mass formula ETF-SI(Q) with a view to better reproduce the r-process abundances. In comparison, our model shows a decrease of the shell strength in going from the r-process path to the drip line. Therefore, this represents a natural behaviour as required by r-process abundances. It may, however, be confirmed in network chain calculations using inputs from our microscopic model.

  13. Ring stability of underground toroidal tanks

    NASA Astrophysics Data System (ADS)

    Lubis, Asnawi; Su'udi, Ahmad

    2017-06-01

    The design of pressure vessels subjected to internal pressure is governed by its strength, while the design of pressure vessels subjected to external pressure is governed by its stability, which is for circular cross-section is called the ring stability. This paper presented the results of finite element study of ring stability of circular toroidal tank without stiffener under external pressure. The tank was placed underground and external pressure load from soil was simulated as pressure at the top of the vessel along 30° circumferentially. One might ask the reason for choosing toroidal rather than cylindrical tank. Preliminary finite element studies showed that toroidal shells can withstand higher external pressure than cylindrical shells. In this study, the volume of the tank was fixed for 15,000 litters. The buckling external pressure (pL) was calculated for radius ratio (R/r) of 2, 3, and 4. The corresponding cross-section radiuses were 724.3 mm, 632.7 mm, and 574.9 mm, respectively. The selected element type was SHELL 281 from the ANSYS element library. To obtain the buckling load, the arc-length method was used in the nonlinear analysis. Both material and geometric nonlinearities were activated during the analysis. The conclusion of this study is that short-radius and thin-walled toroidal shell produces higher buckling load.

  14. Nuclear shapes: Quest for triaxiality in 86Ge and the shape of 98Zr

    NASA Astrophysics Data System (ADS)

    Werner, V.; Lettmann, M.; Lizarazo, C.; Witt, W.; Cline, D.; Carpenter, M.; Doornenbal, P.; Obertelli, A.; Pietralla, N.; Savard, G.; Söderström, P.-A.; Wu, C.-Y.; Zhu, S.

    2018-05-01

    The region of neutron-rich nuclei above the N = 50 magic neutron shell closure encompasses a rich variety of nuclear structure, especially shapeevolutionary phenomena. This can be attributed to the complexity of sub-shell closures, their appearance and disappearance in the region, such as the N = 56 sub shell or Z = 40 for protons. Structural effects reach from a shape phase transition in the Zr isotopes, over shape coexistence between spherical, prolate, and oblate shapes, to possibly rigid triaxial deformation. Recent experiments in this region and their main physics viewpoints are summarized.

  15. 46 CFR 64.41 - Stop valve closure.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Stop valve closure. 64.41 Section 64.41 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) MARINE ENGINEERING MARINE PORTABLE TANKS AND CARGO HANDLING SYSTEMS Standards for an MPT § 64.41 Stop valve closure. A stop valve that operates by a screwed...

  16. 100-N Area underground storage tank closures

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stefanko, D.; Langton, C.

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

  18. Testing and recommended practices to improve nurse tank safety, phase I : [research brief].

    DOT National Transportation Integrated Search

    2013-10-01

    This study focuses on determining causes and possible inspection remediation strategies to reduce the occurrence of anhydrous ammonia (NH3) nurse tank failures. Nurse tanks are cylindrical steel tank shells with hemispherical or elliptical end caps r...

  19. THERMALLY SHIELDED MOISTURE REMOVAL DEVICE

    DOEpatents

    Miller, O.E.

    1958-08-26

    An apparatus is presented for removing moisture from the air within tanks by condensation upon a cartridge containing liquid air. An insulating shell made in two halves covers the cartridge within the evacuated system. The shell halves are hinged together and are operated by a system of levers from outside the tank with the motion translated through a sylphon bellows to cover and uncover the cartridge. When the condensation of moisture is in process, the insulative shell is moved away from the liquid air cartridge, and during that part of the process when there is no freezing out of moisture, the shell halves are closed on the cell so thnt the accumulated frost is not evaporated. This insulating shell greatly reduces the consumption of liquid air in this condensation process.

  20. 49 CFR 179.200-22 - Test of tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... evidence of distress. All rivets and closures, except safety relief valves or safety vents, shall be in place when test is made. (b) Insulated tanks shall be tested before insulation is applied. (c) Rubber-lined tanks shall be tested before rubber lining is applied. (d) Caulking of welded joints to stop leaks...

  1. 49 CFR 179.200-22 - Test of tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... evidence of distress. All rivets and closures, except safety relief valves or safety vents, shall be in place when test is made. (b) Insulated tanks shall be tested before insulation is applied. (c) Rubber-lined tanks shall be tested before rubber lining is applied. (d) Caulking of welded joints to stop leaks...

  2. 49 CFR 179.200-22 - Test of tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... evidence of distress. All rivets and closures, except safety relief valves or safety vents, shall be in place when test is made. (b) Insulated tanks shall be tested before insulation is applied. (c) Rubber-lined tanks shall be tested before rubber lining is applied. (d) Caulking of welded joints to stop leaks...

  3. 49 CFR 179.200-22 - Test of tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... evidence of distress. All rivets and closures, except safety relief valves or safety vents, shall be in place when test is made. (b) Insulated tanks shall be tested before insulation is applied. (c) Rubber-lined tanks shall be tested before rubber lining is applied. (d) Caulking of welded joints to stop leaks...

  4. 40 CFR 63.902 - Standards-Tank fixed roof.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... section joints or between the interface of the roof edge and the tank wall. (3) Each opening in the fixed... closure devices shall include: organic vapor permeability, the effects of any contact with the liquid or its vapors managed in the tank; the effects of outdoor exposure to wind, moisture, and sunlight; and...

  5. 40 CFR 63.902 - Standards-Tank fixed roof.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... section joints or between the interface of the roof edge and the tank wall. (3) Each opening in the fixed... closure devices shall include: organic vapor permeability, the effects of any contact with the liquid or its vapors managed in the tank; the effects of outdoor exposure to wind, moisture, and sunlight; and...

  6. 40 CFR 63.902 - Standards-Tank fixed roof.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... section joints or between the interface of the roof edge and the tank wall. (3) Each opening in the fixed... closure devices shall include: organic vapor permeability, the effects of any contact with the liquid or its vapors managed in the tank; the effects of outdoor exposure to wind, moisture, and sunlight; and...

  7. 40 CFR 63.902 - Standards-Tank fixed roof.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... section joints or between the interface of the roof edge and the tank wall. (3) Each opening in the fixed... closure devices shall include: organic vapor permeability, the effects of any contact with the liquid or its vapors managed in the tank; the effects of outdoor exposure to wind, moisture, and sunlight; and...

  8. Hanford Tanks 241-C-203 and 241-C-204: Residual Waste Contaminant Release Model and Supporting Data

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    This report describes the development of release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. Key results from this work are (1) future releases from the tanks of the primary contaminants of concern (99Tc and 238U) can be represented by relatively simple solubility relationships between infiltrating water and solid phases containing the contaminants; and (2) high percentages of technetium-99 in the sludges (20 wt% in C-203 and 75more » wt% in C-204) are not readily water leachable, and, in fact, are very recalcitrant. This is similar to results found in related studies of sludges from Tank AY-102. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for the U.S. Department of Energy.« less

  9. Hanford immobilized low-activity tank waste performance assessment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mann, F.M.

    1998-03-26

    The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plansmore » to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis to set requirements on the waste form and the facility design that will protect the long-term public health and safety and protect the environment.« less

  10. Chemical Safety Alert: Catastrophic Failure of Storage Tanks

    EPA Pesticide Factsheets

    Aboveground, atmospheric storage tanks can fail when flammable vapors in the tank explode and break either the shell-to-bottom or side seam, resulting in hazardous release accidents. Proper maintenance practices can help prevent accidents.

  11. Closure Report for Corrective Action Unit 563: Septic Systems, Nevada Test Site, Nevada

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Restoration

    2010-02-28

    Corrective Action Unit (CAU) 563 is identified in the Federal Facility Agreement and Consent Order (FFACO) as “Septic Systems” and consists of the following four Corrective Action Sites (CASs), located in Areas 3 and 12 of the Nevada Test Site: · CAS 03-04-02, Area 3 Subdock Septic Tank · CAS 03-59-05, Area 3 Subdock Cesspool · CAS 12-59-01, Drilling/Welding Shop Septic Tanks · CAS 12-60-01, Drilling/Welding Shop Outfalls Closure activities were conducted from September to November 2009 in accordance with the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 563. The corrective action alternatives includedmore » No Further Action and Clean Closure.« less

  12. Toxic chemical considerations for tank farm releases

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Van Keuren, J.C.; Davis, J.S., Westinghouse Hanford

    1996-08-01

    This topical report contains technical information used to determine the accident consequences of releases of toxic chemical and gases for the Tank Farm Final Safety Analysis report (FSAR).It does not provide results for specific accident scenarios but does provide information for use in those calculations including chemicals to be considered, chemical concentrations, chemical limits and a method of summing the fractional contributions of each chemical. Tank farm composites evaluated were liquids and solids for double shell tanks, single shell tanks, all solids,all liquids, headspace gases, and 241-C-106 solids. Emergency response planning guidelines (ERPGs) were used as the limits.Where ERPGs weremore » not available for the chemicals of interest, surrogate ERPGs were developed. Revision 2 includes updated sample data, an executive summary, and some editorial revisions.« less

  13. TECHNICAL ASPECTS OF UNDERGROUND STORAGE TANK CLOSURE

    EPA Science Inventory

    The overall objective of the study was to develop a deeper understanding of UST residuals at closure: their quantities, origins, physical/chemical properties, ease of removal by various cleaning methods, and their environmental mobility and persistence. The investigation covered ...

  14. 46 CFR 38.05-10 - Installation of cargo tanks-general-TB/ALL.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... prevent the tanks from shifting when subjected to external forces. Each tank shall be so supported as to prevent the concentration of excessive loads on the supporting portions of the shell or head as prescribed... consider the resonance of the cargo tank, or parts thereof, and the vibratory forces, found in the tank...

  15. 46 CFR 38.05-10 - Installation of cargo tanks-general-TB/ALL.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... prevent the tanks from shifting when subjected to external forces. Each tank shall be so supported as to prevent the concentration of excessive loads on the supporting portions of the shell or head as prescribed... consider the resonance of the cargo tank, or parts thereof, and the vibratory forces, found in the tank...

  16. 46 CFR 38.05-10 - Installation of cargo tanks-general-TB/ALL.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... prevent the tanks from shifting when subjected to external forces. Each tank shall be so supported as to prevent the concentration of excessive loads on the supporting portions of the shell or head as prescribed... consider the resonance of the cargo tank, or parts thereof, and the vibratory forces, found in the tank...

  17. 46 CFR 38.05-10 - Installation of cargo tanks-general-TB/ALL.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... prevent the tanks from shifting when subjected to external forces. Each tank shall be so supported as to prevent the concentration of excessive loads on the supporting portions of the shell or head as prescribed... consider the resonance of the cargo tank, or parts thereof, and the vibratory forces, found in the tank...

  18. 46 CFR 38.05-10 - Installation of cargo tanks-general-TB/ALL.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... prevent the tanks from shifting when subjected to external forces. Each tank shall be so supported as to prevent the concentration of excessive loads on the supporting portions of the shell or head as prescribed... consider the resonance of the cargo tank, or parts thereof, and the vibratory forces, found in the tank...

  19. Slurry growth, gas retention, and flammable gas generation by Hanford radioactive waste tanks: Synthetic waste studies, FY 1991

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bryan, S.A.; Pederson, L.R.; Ryan, J.L.

    1992-08-01

    Of 177 high-level waste storage tanks on the Hanford Site, 23 have been placed on a safety watch list because they are suspected of producing flammable gases in flammable or explosive concentrate. One tankin particular, Tank 241-SY-101 (Tank 101-SY), has exhibited slow increases in waste volume followed by a rapid decrease accompanied by venting of large quantities of gases. The purpose of this study is to help determine the processes by which flammable gases are produced, retained, and eventually released from Tank 101-SY. Waste composition data for single- and double-shell waste tanks on the flammable gas watch listare critically reviewed.more » The results of laboratory studies using synthetic double-shell wastes are summarized, including physical and chemical properties of crusts that are formed, the stoichiometry and rate ofgas generation, and mechanisms responsible for formation of a floating crust.« less

  20. Thermocryogenic buckling and stress analyses of a partially filled cryogenic tank subjected to cylindrical strip heating

    NASA Technical Reports Server (NTRS)

    Ko, William L.

    1994-01-01

    Thermocryogenic buckling and stress analyses were conducted on a horizontally oriented cryogenic tank using the finite element method. The tank is a finite-length circular cylindrical shell with its two ends capped with hemispherical shells. The tank is subjected to cylindrical strip heating in the region above the liquid-cryogen fill level and to cryogenic cooling below the fill level (i.e., under thermocryogenic loading). The effects of cryogen fill level on the buckling temperature and thermocryogenic stress field were investigated in detail. Both the buckling temperature and stress magnitudes were relatively insensitive to the cryogen fill level. The buckling temperature, however, was quite sensitive to the radius-to-thickness ratio. A mechanical stress analysis of the tank also was conducted when the tank was under: (1) cryogen liquid pressure loading; (2) internal pressure loading; and (3) tank-wall inertia loading. Deformed shapes of the cryogenic tanks under different loading conditions were shown, and high-stress domains were mapped on the tank wall for the strain-gage installations. The accuracies of solutions from different finite element models were compared.

  1. Double shell tanks (DST) chemistry control data quality objectives

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BANNING, D.L.

    2001-10-09

    One of the main functions of the River Protection Project is to store the Hanford Site tank waste until the Waste Treatment Plant (WTP) is ready to receive and process the waste. Waste from the older single-shell tanks is being transferred to the newer double-shell tanks (DSTs). Therefore, the integrity of the DSTs must be maintained until the waste from all tanks has been retrieved and transferred to the WTP. To help maintain the integrity of the DSTs over the life of the project, specific chemistry limits have been established to control corrosion of the DSTs. These waste chemistry limitsmore » are presented in the Technical Safety Requirements (TSR) document HNF-SD-WM-TSR-006, Sec. 5 . IS, Rev 2B (CHG 200 I). In order to control the chemistry in the DSTs, the Chemistry Control Program will require analyses of the tank waste. This document describes the Data Quality Objective (DUO) process undertaken to ensure appropriate data will be collected to control the waste chemistry in the DSTs. The DQO process was implemented in accordance with Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. Ib, Vol. IV, Section 4.16, (Banning 2001) and the U.S. Environmental Protection Agency EPA QA/G4, Guidance for the Data Quality Objectives Process (EPA 1994), with some modifications to accommodate project or tank specific requirements and constraints.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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 ofmore » 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.« less

  3. Neutrinoless double-β decay of 48Ca in the shell model: Closure versus nonclosure approximation

    NASA Astrophysics Data System (ADS)

    Sen'kov, R. A.; Horoi, M.

    2013-12-01

    Neutrinoless double-β decay (0νββ) is a unique process that could reveal physics beyond the Standard Model. Essential ingredients in the analysis of 0νββ rates are the associated nuclear matrix elements. Most of the approaches used to calculate these matrix elements rely on the closure approximation. Here we analyze the light neutrino-exchange matrix elements of 48Ca 0νββ decay and test the closure approximation in a shell-model approach. We calculate the 0νββ nuclear matrix elements for 48Ca using both the closure approximation and a nonclosure approach, and we estimate the uncertainties associated with the closure approximation. We demonstrate that the nonclosure approach has excellent convergence properties which allow us to avoid unmanageable computational cost. Combining the nonclosure and closure approaches we propose a new method of calculation for 0νββ decay rates which can be applied to the 0νββ decay rates of heavy nuclei, such as 76Ge or 82Se.

  4. Attenuation of standing waves in a large water tank using arrays of large tethered encapsulated bubbles.

    PubMed

    Lee, Kevin M; Wilson, Preston S; Wochner, Mark S

    2014-04-01

    The use of bubble resonance effects to attenuate low-frequency underwater sound was investigated experimentally in a large water tank. A compact electromechanical sound source was used to excite standing wave fields at frequencies ranging between 50 and 200 Hz in the tank. The source was then surrounded by a stationary array of tethered encapsulated air bubbles, and reduction in standing wave amplitude by as much as 26 dB was observed. The bubbles consisted of either thin-shelled latex balloons with approximately 5 cm radii or thicker-shelled vinyl boat fenders with 6.9 cm radii. The effects of changing the material and thickness of the bubble shells were found to be in qualitative agreement with predictions from Church's model for sound propagation in a liquid containing encapsulated bubbles [J. Acoust. Soc. Am. 97, 1510-1521 (1995)]. Although demonstrated here for low frequency noise abatement within a tank, which is useful for quieting acoustic test facilities and large tanks used for marine life husbandry, the eventual aim of this work is to use stationary arrays of large tethered encapsulated bubbles to abate low frequency underwater noise from anthropogenic sources in the marine environment.

  5. SECONDARY WASTE MANAGEMENT FOR HANFORD EARLY LOW ACTIVITY WASTE VITRIFICATION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    UNTERREINER BJ

    2008-07-18

    More than 200 million liters (53 million gallons) of highly radioactive and hazardous waste is stored at the U.S. Department of Energy's Hanford Site in southeastern Washington State. The DOE's Hanford Site River Protection Project (RPP) mission includes tank waste retrieval, waste treatment, waste disposal, and tank farms closure activities. This mission will largely be accomplished by the construction and operation of three large treatment facilities at the Waste Treatment and Immobilization Plant (WTP): (1) a Pretreatment (PT) facility intended to separate the tank waste into High Level Waste (HLW) and Low Activity Waste (LAW); (2) a HLW vitrification facilitymore » intended to immobilize the HLW for disposal at a geologic repository in Yucca Mountain; and (3) a LAW vitrification facility intended to immobilize the LAW for shallow land burial at Hanford's Integrated Disposal Facility (IDF). The LAW facility is on target to be completed in 2014, five years prior to the completion of the rest of the WTP. In order to gain experience in the operation of the LAW vitrification facility, accelerate retrieval from single-shell tank (SST) farms, and hasten the completion of the LAW immobilization, it has been proposed to begin treatment of the low-activity waste five years before the conclusion of the WTP's construction. A challenge with this strategy is that the stream containing the LAW vitrification facility off-gas treatment condensates will not have the option of recycling back to pretreatment, and will instead be treated by the Hanford Effluent Treatment Facility (ETF). Here the off-gas condensates will be immobilized into a secondary waste form; ETF solid waste.« less

  6. 78 FR 42818 - SafetyAlert: Safety Alert: Risks Associated With Liquid Petroleum (LP) Gas Odor Fade

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-17

    ... stakeholders from industry, fire fighter associations, and other regulatory agencies in order to better... tanks are used. New or recently cleaned tanks may absorb the odorant into the metal shell of these tanks...

  7. Think Tank.

    ERIC Educational Resources Information Center

    Governick, Heather; Wellington, Thom

    1998-01-01

    Examines the options for upgrading, replacing, and removal or closure of underground storage tanks (UST). Reveals the diverse regulatory control involving USTs, the Environmental Protection Agency's interest in pursuing violators, and stresses the need for administrators to be knowledgeable about state and local agency definitions of regulated…

  8. Report to Congress on a Compliance Plan for the Underground Storage Tank Program

    EPA Pesticide Factsheets

    Learn about identification of USTs that are not in compliance with Subtitle I of the Solid Waste Disposal Act or are in temporary closure, and determine the ownership of USTs not in compliance or in temporary closure

  9. Closure Report for Corrective Action Unit 151: Septic Systems and Discharge Area, Nevada Test Site, Nevada

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Restoration

    2008-04-01

    Corrective Action Unit (CAU) 151 is identified in the Federal Facility Agreement and Consent Order (FFACO) as Septic Systems and Discharge Area. CAU 151 consists of the following eight Corrective Action Sites (CASs), located in Areas 2, 12, and 18 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada: (1) CAS 02-05-01, UE-2ce Pond; (2) CAS 12-03-01, Sewage Lagoons (6); (3) CAS 12-04-01, Septic Tanks; (4) CAS 12-04-02, Septic Tanks; (5) CAS 12-04-03, Septic Tank; (6) CAS 12-47-01, Wastewater Pond; (7) CAS 18-03-01, Sewage Lagoon; and (8) CAS 18-99-09, Sewer Line (Exposed). CAU 151 closure activitiesmore » were conducted according to the FFACO (FFACO, 1996; as amended February 2008) and the Corrective Action Plan for CAU 151 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007) from October 2007 to January 2008. The corrective action alternatives included no further action, clean closure, and closure in place with administrative controls. CAU 151 closure activities are summarized in Table 1. Closure activities generated liquid remediation waste, sanitary waste, hydrocarbon waste, and mixed waste. Waste generated was appropriately managed and disposed. Waste that is currently staged onsite is being appropriately managed and will be disposed under approved waste profiles in permitted landfills. Waste minimization activities included waste characterization sampling and segregation of waste streams. Some waste exceeded land disposal restriction limits and required offsite treatment prior to disposal. Other waste meeting land disposal restrictions was disposed of in appropriate onsite or offsite landfills. Waste disposition documentation is included as Appendix C.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1994-05-01

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

  11. 78 FR 10163 - Notice of Availability of Draft Section 3116 Basis for Determination for Closure of H Tank Farm...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-13

    ... isolation in a deep geologic repository for spent fuel or high-level radioactive waste; (2) has had highly... in 10 CFR Part 61, Subpart C and pursuant to a State approved closure plan or State-issued permit; or... with the performance objectives of 10 CFR Part 61, Subpart C; pursuant to a State approved closure plan...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.

  13. Recent Direct Reaction Experimental Studies with Radioactive Tin Beams

    DOE PAGES

    Jones, K. L.; Ahn, S.; Allmond, J. M.; ...

    2015-01-01

    Direct reaction techniques are powerful tools to study the single-particle nature of nuclei. Performing direct reactions on short-lived nuclei requires radioactive ion beams produced either via fragmentation or the Isotope Separation OnLine (ISOL) method. Some of the most interesting regions to study with direct reactions are close to the magic numbers where changes in shell structure can be tracked. These changes can impact the final abundances of explosive nucleosynthesis. The structure of the chain of tin isotopes is strongly influenced by the Z = 50 proton shell closure, as well as the neutron shell closures lying in the neutron-rich, Nmore » = 82, and neutron-deficient, N = 50, regions. Here, we present two examples of direct reactions on exotic tin isotopes. The first uses a one-neutron transfer reaction and a low-energy reaccelerated ISOL beam to study states in Sn-131 from across the N = 82 shell closure. The second example utilizes a one-neutron knockout reaction on fragmentation beams of neutron-deficient Sn- 106,108Sn. In conclusion, In both cases, measurements of γ rays in coincidence with charged particles proved to be invaluable.« less

  14. Novel Architecture for a Long-Life, Lightweight Venus Lander

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bugby, D.; Seghi, S.; Kroliczek, E.

    2009-03-16

    This paper describes a novel concept for an extended lifetime, lightweight Venus lander. Historically, to operate in the 480 deg. C, 90 atm, corrosive, mostly CO{sub 2} Venus surface environment, previous landers have relied on thick Ti spherical outer shells and thick layers of internal insulation. But even the most resilient of these landers operated for only about 2 hours before succumbing to the environment. The goal on this project is to develop an architecture that extends lander lifetime to 20-25 hours and also reduces mass compared to the Pioneer Venus mission architecture. The idea for reducing mass is to:more » (a) contain the science instruments within a spherical high strength lightweight polymer matrix composite (PMC) tank; (b) surround the PMC tank with an annular shell of high performance insulation pre-pressurized to a level that (after landing) will exceed the external Venus surface pressure; and (c) surround the insulation with a thin Ti outer shell that contains only a net internal pressure, eliminating buckling overdesign mass. The combination of the PMC inner tank and thin Ti outer shell is lighter than a single thick Ti outer shell. The idea for extending lifetime is to add the following three features: (i) an expendable water supply that is placed within the insulation or is contained in an additional vessel within the PMC tank; (ii) a thin spherical evaporator shell placed within the insulation a short radial distance from the outer shell; and (iii) a thin heat-intercepting liquid cooled shield placed inboard of the evaporator shell. These features lower the temperature of the insulation below what it would have been with the insulation alone, reducing the internal heat leak and lengthening lifetime. The use of phase change materials (PCMs) inside the PMC tank is also analyzed as a lifetime-extending design option. The paper describes: (1) analytical modeling to demonstrate reduced mass and extended life; (2) thermal conductivity testing of high performance insulation as a function of temperature and pressure; (3) a bench-top ambient pressure thermal test of the evaporation system; and (4) a higher fidelity test, to be conducted in a high pressure, high temperature inert gas test chamber, of a small-scale Venus lander prototype (made from two hemispherical interconnecting halves) that includes all of the aforesaid features.22 CFR 125.4(b)(13) applicable.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lockie, K.A.; Suttora, L.C.; Quigley, K.D.

    2007-07-01

    Significant progress has been made at the U.S. Department of Energy (DOE) Idaho National Laboratory (INL) to clean and close emptied radioactive liquid waste storage tanks at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF). The TFF includes eleven 1,135.6-kL (300,000-gal) underground stainless steel storage tanks and four smaller, 113.5-kL (30,000-gal) stainless steel tanks, along with tank vaults, interconnecting piping, and ancillary equipment. The TFF tanks have historically been used to store a variety of radioactive liquid waste, including wastes associated with past spent nuclear fuel reprocessing. Although four of the large storage tanks remain inmore » use for waste storage, the other seven 1,135.6-kL (300,000-gal) tanks and the four 113.5-kL (30,000-gal) tanks have been emptied of waste and cleaned in preparation of final closure. A water spray cleaning system was developed and deployed to clean internal tank surfaces and remove remaining tank wastes. The cleaning system was effective in removing all but a very small volume of solid residual waste particles. Recent issuance of an Amended Record of Decision (ROD) in accordance with the National Environmental Policy Act, and a Waste Determination complying with Section 3116 of the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, has allowed commencement of grouting activities on the cleaned tanks. In November 2006, three of the 113.5-kL (30,000-gal) tanks were filled with grout to provide long-term stability. It is currently planned that all seven cleaned 1,135.6-kL (300,000-gal) tanks, as well as the four 113.5-kL (30,000-gal) tanks and all associated tank vaults and interconnecting piping, will be stabilized with grout as early as 2008. (authors)« less

  16. 49 CFR 179.220-26 - Stenciling.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-26 Stenciling. (a) The outer shell, or the...

  17. 49 CFR 179.220-26 - Stenciling.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-26 Stenciling. (a) The outer shell, or the...

  18. NESC Review of the 8-Foot High Temperature Tunnel (HTT) Oxygen Storage Pressure Vessel Inspection Requirements

    NASA Technical Reports Server (NTRS)

    Gilbert, Michael; Raju, Ivatury; Piascik, Robert; Cameron, Kenneth; Kirsch, Michael; Hoffman, Eric; Murthy, Pappu; Hopson, George; Greulich, Owen; Frazier, Wayne

    2009-01-01

    The 8-Foot HTT (refer to Figure 4.0-1) is used to conduct tests of air-breathing hypersonic propulsion systems at Mach numbers 4, 5, and 7. Methane, Air, and LOX are mixed and burned in a combustor to produce test gas stream containing 21 percent by volume oxygen. The NESC was requested by the NASA LaRC Executive Safety Council to review the rationale for a proposed change to the recertification requirements, specifically the internal inspection requirements, of the 8-Foot HTT LOX Run Tank and LOX Storage Tank. The Run Tank is an 8,000 gallon cryogenic tank used to provide LOX to the tunnel during operations, and is pressured during the tunnel run to 2,250 pounds per square inch gage (psig). The Storage Tank is a 25,000 gallon cryogenic tank used to store LOX at slightly above atmospheric pressure as a external shell, with space between the shells maintained under vacuum conditions.

  19. Closure Report for Corrective Action Unit 224: Decon Pad and Septic Systems, Nevada Test Site, Nevada

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Restoration

    Corrective Action Unit (CAU) 224 is located in Areas 02, 03, 05, 06, 11, and 23 of the Nevada Test Site, which is situated approximately 65 miles northwest of Las Vegas, Nevada. CAU 224 is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 as Decon Pad and Septic Systems and is comprised of the following nine Corrective Action Sites (CASs): CAS 02-04-01, Septic Tank (Buried); CAS 03-05-01, Leachfield; CAS 05-04-01, Septic Tanks (4)/Discharge Area; CAS 06-03-01, Sewage Lagoons (3); CAS 06-05-01, Leachfield; CAS 06-17-04, Decon Pad and Wastewater Catch; CAS 06-23-01, Decon Pad Discharge Piping; CASmore » 11-04-01, Sewage Lagoon; and CAS 23-05-02, Leachfield. The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASs 02-04-01, 03-05-01, 06-03-01, 11-04-01, and 23-05-02 is no further action. As a best management practice, the septic tanks and distribution box were removed from CASs 02-04-01 and 11-04-01 and disposed of as hydrocarbon waste. The NDEP-approved correction action alternative for CASs 05-04-01, 06-05-01, 06-17-04, and 06-23-01 is clean closure. Closure activities for these CASs included removing and disposing of radiologically and pesticide-impacted soil and debris. CAU 224 was closed in accordance with the NDEP-approved CAU 224 Corrective Action Plan (CAP). The closure activities specified in the CAP were based on the recommendations presented in the CAU 224 Corrective Action Decision Document (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2005). This Closure Report documents CAU 224 closure activities. During closure activities, approximately 60 cubic yards (yd3) of mixed waste in the form of soil and debris; approximately 70 yd{sup 3} of sanitary waste in the form of soil, liquid from septic tanks, and concrete debris; approximately 10 yd{sup 3} of hazardous waste in the form of pesticide-impacted soil; approximately 0.5 yd{sup 3} of universal waste in the form of fluorescent light bulbs; and approximately 0.5 yd{sup 3} of low-level waste in the form of a radiologically impacted fire hose rack were generated, managed, and disposed of appropriately. Waste minimization techniques, such as the utilization of laboratory analysis and field screening to guide the extent of excavations, were employed during the performance of closure work.« less

  20. Flammable gas double shell tank expert elicitation presentations (Part A and Part B)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bratzel, D.R.

    1998-04-17

    This document is a compilation of presentation packages and white papers for the Flammable Gas Double Shell Tank Expert Elicitation Workshop {number_sign}2. For each presentation given by the different authors, a separate section was developed. The purpose for issuing these workshop presentation packages and white papers as a supporting document is to provide traceability and a Quality Assurance record for future reference to these packages.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    VENETZ TJ; BOOMER KD; WASHENFELDER DJ

    2012-01-25

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

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Conner, J.M.

    1997-04-28

    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-basismore » 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.« less

  3. 241-AP Tank Farm Construction Extent of Condition Review for Tank Integrity

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    2014-04-04

    This report provides the results of an extent of condition construction history review for the 241-AP tank farm. The construction history of the 241-AP tank farm has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In the 241-AP tank farm, the sixth double-shell tank farm constructed, tank bottom flatness, refractory material quality, post-weld stress relieving, and primary tank bottom weld rejection were improved.

  4. Design of cryogenic tanks for space vehicles shell structures analytical modeling

    NASA Technical Reports Server (NTRS)

    Copper, Charles; Mccarthy, K.; Pilkey, W. D.; Haviland, J. K.

    1991-01-01

    The initial objective was to study the use of superplastically formed corrugated hat section stringers and frames in place of integrally machined stringers over separate frames for the tanks of large launch vehicles subjected to high buckling loads. The ALS was used as an example. The objective of the follow-on project was to study methods of designing shell structures subjected to severe combinations of structural loads and thermal gradients, with emphasis on new combinations of structural arrangements and materials. Typical applications would be to fuselage sections of high speed civil transports and to cryogenic tanks on the National Aerospace Plane.

  5. Mission analysis report for single-shell tank leakage mitigation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cruse, J.M.

    1994-09-01

    This document provides an analysis of 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 missions of the Westinghouse Hanford Company Tank Waste Remediation System division to remediate the tank waste in a safe and acceptable manner. Systems engineers principles are being applied to this effort. Mission analysis supports early decision making by clearly defining program objectives. This documents identifies the initial conditions and acceptable final conditions, defines the programmatic and physical interfaces and constraints, estimates the resources to carry outmore » the mission, and establishes measures of success. The results of the mission analysis provide a consistent basis for subsequent systems engineering work.« less

  6. Strategy Plan A Methodology to Predict the Uniformity of Double-Shell Tank Waste Slurries Based on Mixing Pump Operation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    J.A. Bamberger; L.M. Liljegren; P.S. Lowery

    This document presents an analysis of the mechanisms influencing mixing within double-shell slurry tanks. A research program to characterize mixing of slurries within tanks has been proposed. The research program presents a combined experimental and computational approach to produce correlations describing the tank slurry concentration profile (and therefore uniformity) as a function of mixer pump operating conditions. The TEMPEST computer code was used to simulate both a full-scale (prototype) and scaled (model) double-shell waste tank to predict flow patterns resulting from a stationary jet centered in the tank. The simulation results were used to evaluate flow patterns in the tankmore » and to determine whether flow patterns are similar between the full-scale prototype and an existing 1/12-scale model tank. The flow patterns were sufficiently similar to recommend conducting scoping experiments at 1/12-scale. Also, TEMPEST modeled velocity profiles of the near-floor jet were compared to experimental measurements of the near-floor jet with good agreement. Reported values of physical properties of double-shell tank slurries were analyzed to evaluate the range of properties appropriate for conducting scaled experiments. One-twelfth scale scoping experiments are recommended to confirm the prioritization of the dimensionless groups (gravitational settling, Froude, and Reynolds numbers) that affect slurry suspension in the tank. Two of the proposed 1/12-scale test conditions were modeled using the TEMPEST computer code to observe the anticipated flow fields. This information will be used to guide selection of sampling probe locations. Additional computer modeling is being conducted to model a particulate laden, rotating jet centered in the tank. The results of this modeling effort will be compared to the scaled experimental data to quantify the agreement between the code and the 1/12-scale experiment. The scoping experiment results will guide selection of parameters to be varied in the follow-on experiments. Data from the follow-on experiments will be used to develop correlations to describe slurry concentration profile as a function of mixing pump operating conditions. This data will also be used to further evaluate the computer model applications. If the agreement between the experimental data and the code predictions is good, the computer code will be recommended for use to predict slurry uniformity in the tanks under various operating conditions. If the agreement between the code predictions and experimental results is not good, the experimental data correlations will be used to predict slurry uniformity in the tanks within the range of correlation applicability.« less

  7. Reanalysis of Plutonium and Americium-241 in the Tank 19F Closure Grab and Core Samples

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Swingle, R.F.

    2003-02-11

    Tank 19F is scheduled to be closed by March 2004. To close this tank, a characterization of the waste remaining in the tank was required to confirm the inventory of various species for input into groundwater transport models. This characterization has been developed by a combination of process knowledge, visual observation and sample analysis. The characterization samples were obtained by High Level Waste Division (HLWD) personnel and characterized by SRTC personnel.

  8. Development and flight test of metal-lined CFRP cryogenic tank for reusable rocket

    NASA Astrophysics Data System (ADS)

    Higuchi, Ken; Takeuchi, Shinsuke; Sato, Eiichi; Naruo, Yoshihiro; Inatani, Yoshifumi; Namiki, Fumiharu; Tanaka, Kohtaro; Watabe, Yoko

    2005-07-01

    A cryogenic tank made of carbon fiber reinforced plastic (CFRP) shell with aluminum thin liner has been designed as a liquid hydrogen (LH2) tank for an ISAS reusable launch vehicle, and the function of it has been proven by repeated flights onboard the test vehicle called reusable vehicle testing (RVT) in October 2003. The liquid hydrogen tank has to be a pressure vessel, because the fuel of the engine of the test vehicle is supplied by fuel pressure. The pressure vessel of a combination of the outer shell of CFRP for strength element at a cryogenic temperature and the inner liner of aluminum for gas barrier has shown excellent weight merit for this purpose. Interfaces such as tank outline shape, bulk capacity, maximum expected operating pressure (MEOP), thermal insulation, pipe arrangement, and measurement of data are also designed to be ready onboard. This research has many aims, not only development of reusable cryogenic composite tank but also the demonstration of repeated operation including thermal cycle and stress cycle, familiarization with test techniques of operation of cryogenic composite tanks, and the accumulation of data for future design of tanks, vehicle structures, safety evaluation, and total operation systems.

  9. 40 CFR 63.906 - Inspection and monitoring requirements.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... between the roof and the tank wall; broken, cracked, or otherwise damaged seals or gaskets on closure devices; and broken or missing hatches, access covers, caps, or other closure devices. (2) The owner or... air pollution control equipment designated as such a written explanation of the reasons why the...

  10. Safety criteria for organic watch list tanks at the Hanford Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Meacham, J.E., Westinghouse Hanford

    1996-08-01

    This document reviews the hazards associated with the storage of organic complexant salts in Hanford Site high-level waste single- shell tanks. The results of this analysis were used to categorize tank wastes as safe, unconditionally safe, or unsafe. Sufficient data were available to categorize 67 tanks; 63 tanks were categorized as safe, and four tanks were categorized as conditionally safe. No tanks were categorized as unsafe. The remaining 82 SSTs lack sufficient data to be categorized.Historic tank data and an analysis of variance model were used to prioritize the remaining tanks for characterization.

  11. 76 FR 78698 - Proposed Revocation of Permanent Variances

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-19

    ... cylindrical steel tanks. Construction of these tanks involves attaching curved steel plates together to form the outer surface of a tank. After attaching a horizontal layer (ring) of steel plates around the circumference of the existing shell, employees raise the scaffolds to attach the next ring of steel plates onto...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Washenfelder, Dennis J.

    2015-02-03

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

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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.

  14. TANK 18-F AND 19-F TANK FILL GROUT SCALE UP TEST SUMMARY

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stefanko, D.; Langton, C.

    2012-01-03

    High-level waste (HLW) tanks 18-F and 19-F have been isolated from FTF facilities. To complete operational closure the tanks will be filled with grout for the purpose of: (1) physically stabilizing the tanks, (2) limiting/eliminating vertical pathways to residual waste, (3) entombing waste removal equipment, (4) discouraging future intrusion, and (5) providing an alkaline, chemical reducing environment within the closure boundary to control speciation and solubility of select radionuclides. This report documents the results of a four cubic yard bulk fill scale up test on the grout formulation recommended for filling Tanks 18-F and 19-F. Details of the scale upmore » test are provided in a Test Plan. The work was authorized under a Technical Task Request (TTR), HLE-TTR-2011-008, and was performed according to Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2011-00587. The bulk fill scale up test described in this report was intended to demonstrate proportioning, mixing, and transportation, of material produced in a full scale ready mix concrete batch plant. In addition, the material produced for the scale up test was characterized with respect to fresh properties, thermal properties, and compressive strength as a function of curing time.« less

  15. 46 CFR 64.33 - Pipe connection.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) MARINE ENGINEERING MARINE PORTABLE TANKS AND CARGO HANDLING SYSTEMS Standards for an MPT § 64.33 Pipe connection. Each pipe connection that is not a pressure relief device must be fitted with a manually operated stop valve or closure located as close to the tank...

  16. 241-AW Tank Farm Construction Extent of Condition Review for Tank Integrity

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    2013-11-19

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

  17. 241-AY-101 Tank Construction Extent of Condition Review for Tank Integrity

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Barnes, Travis J.; Gunter, Jason R.

    2013-08-26

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

  18. Criteria: waste tank isolation and stabilization

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    1976-09-01

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

  19. Dangerous Waste Characteristics of Waste from Hanford Tank 241-S-109

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

    2004-11-05

    Existing analytical data from samples taken from Hanford Tank 241-S-109, along with process knowledge of the wastes transferred to this tank, are reviewed to determine whether dangerous waste characteristics currently assigned to all waste in Hanford underground storage tanks are applicable to this tank waste. Supplemental technologies are examined to accelerate the Hanford tank waste cleanup mission and to accomplish the waste treatment in a safer and more efficient manner. The goals of supplemental technologies are to reduce costs, conserve double-shell tank space, and meet the scheduled tank waste processing completion date of 2028.

  20. 75 FR 3902 - Notice of Public Hearings on the Draft Tank Closure and Waste Management Environmental Impact...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-25

    ... ending March 19, 2010. The State of Washington, Department of Ecology (Ecology) is a cooperating agency... and information about the Washington State Department of Ecology, contact: Annette Carlson, Nuclear... ultimate closure of Hanford. In support of Hanford's cleanup mission DOE, with Ecology as a cooperating...

  1. 49 CFR 178.337-6 - Closure for manhole.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... Specifications for Containers for Motor Vehicle Transportation § 178.337-6 Closure for manhole. (a) Each cargo... this subchapter), except that a cargo tank constructed of NQT steel having a capacity of 3,500 water gallons or less may be provided with an inspection opening conforming to paragraph UG-46 and other...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    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 presumedmore » 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.« less

  3. Technology development in support of the TWRS process flowsheet. Revision 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Washenfelder, D.J.

    1995-10-11

    The Tank Waste Remediation System is to treat and dispose of Hanford`s Single-Shell and Double-Shell Tank Waste. The TWRS Process Flowsheet, (WHC-SD-WM-TI-613 Rev. 1) described a flowsheet based on a large number of assumptions and engineering judgements that require verification or further definition through process and technology development activities. This document takes off from the TWRS Process Flowsheet to identify and prioritize tasks that should be completed to strengthen the technical foundation for the flowsheet.

  4. Evaluation of semi-empirical analyses for railroad tank car puncture velocity, part 1 : correlations with experimental data

    DOT National Transportation Integrated Search

    2001-11-01

    This report is the first in a two-part series that focuses on methodologies to determine the puncture velocity of tank car shells. In this context, puncture velocity refers to the impact velocity at which a coupler will puncture the tank. In this rep...

  5. Photogrammetry and Laser Imagery Tests for Tank Waste Volume Estimates: Summary Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Field, Jim G.

    2013-03-27

    Feasibility tests were conducted using photogrammetry and laser technologies to estimate the volume of waste in a tank. These technologies were compared with video Camera/CAD Modeling System (CCMS) estimates; the current method used for post-retrieval waste volume estimates. This report summarizes test results and presents recommendations for further development and deployment of technologies to provide more accurate and faster waste volume estimates in support of tank retrieval and closure.

  6. Evaluation of Aerodynamic Drag and Torque for External Tanks in Low Earth Orbit

    PubMed Central

    Stone, William C.; Witzgall, Christoph

    2006-01-01

    A numerical procedure is described in which the aerodynamic drag and torque in low Earth orbit are calculated for a prototype Space Shuttle external tank and its components, the “LO2” and “LH2” tanks, carrying liquid oxygen and hydrogen, respectively, for any given angle of attack. Calculations assume the hypersonic limit of free molecular flow theory. Each shell of revolution is assumed to be described by a series of parametric equations for their respective contours. It is discretized into circular cross sections perpendicular to the axis of revolution, which yield a series of ellipses when projected according to the given angle of attack. The drag profile, that is, the projection of the entire shell is approximated by the convex envelope of those ellipses. The area of the drag profile, that is, the drag area, and its center of area moment, that is, the drag center, are then calculated and permit determination of the drag vector and the eccentricity vector from the center of gravity of the shell to the drag center. The aerodynamic torque is obtained as the cross product of those vectors. The tanks are assumed to be either evacuated or pressurized with a uniform internal gas distribution: dynamic shifting of the tank center of mass due to residual propellant sloshing is not considered. PMID:27274926

  7. Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Groth, B.D.

    The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements.

  8. DOE Office of Scientific and Technical Information (OSTI.GOV)

    KIRKBRIDE, R.A.

    The Tank Waste Remediation System Operation and Utilization Plan updates the operating scenario and plans for the delivery of feed to BNFL Inc., retrieval of waste from single-shell tanks, and the overall process flowsheets for Phases I and II of the privatization of the Tank Waste Remediation System. The plans and flowsheets are updated with the most recent tank-by-tank inventory and sludge washing data. Sensitivity cases were run to evaluate the impact or benefits of proposed changes to the BNFL Inc. contract and to evaluate a risk-based SST retrieval strategy.

  9. 49 CFR 179.220-4 - Insulation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ...-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-4 Insulation. The annular space between the inner container and the outer shell must contain an approved insulation material. [Amdt. 179-9, 36 FR...

  10. 49 CFR 179.220-4 - Insulation.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ...-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-4 Insulation. The annular space between the inner container and the outer shell must contain an approved insulation material. [Amdt. 179-9, 36 FR...

  11. 49 CFR 179.220-4 - Insulation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ...-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-4 Insulation. The annular space between the inner container and the outer shell must contain an approved insulation material. [Amdt. 179-9, 36 FR...

  12. Sample Based Unit Liter Dose Estimates

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    JENSEN, L.

    The Tank Waste Characterization Program has taken many core samples, grab samples, and auger samples from the single-shell and double-shell tanks during the past 10 years. Consequently, the amount of sample data available has increased, both in terms of quantity of sample results and the number of tanks characterized. More and better data is available than when the current radiological and toxicological source terms used in the Basis for Interim Operation (BIO) (FDH 1999a) and the Final Safety Analysis Report (FSAR) (FDH 1999b) were developed. The Nuclear Safety and Licensing (NS and L) organization wants to use the new datamore » to upgrade the radiological and toxicological source terms used in the BIO and FSAR. The NS and L organization requested assistance in producing a statistically based process for developing the source terms. This report describes the statistical techniques used and the assumptions made to support the development of a new radiological source term for liquid and solid wastes stored in single-shell and double-shell tanks. The results given in this report are a revision to similar results given in an earlier version of the document (Jensen and Wilmarth 1999). The main difference between the results in this document and the earlier version is that the dose conversion factors (DCF) for converting {mu}Ci/g or {mu}Ci/L to Sv/L (sieverts per liter) have changed. There are now two DCFs, one based on ICRP-68 and one based on ICW-71 (Brevick 2000).« less

  13. 49 CFR 178.274 - Specifications for UN portable tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... and 178.277, as applicable. Design type means a portable tank or series of portable tanks made of... the top of the shell during the hydraulic pressure test equal to not less than 1.5 times the design... be designed and constructed to withstand a hydraulic test pressure of not less than 1.5 times the...

  14. 49 CFR 178.274 - Specifications for UN portable tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... and 178.277, as applicable. Design type means a portable tank or series of portable tanks made of... the top of the shell during the hydraulic pressure test equal to not less than 1.5 times the design... be designed and constructed to withstand a hydraulic test pressure of not less than 1.5 times the...

  15. Safety evaluation for packaging transportation of equipment for tank 241-C-106 waste sluicing system

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Calmus, D.B.

    1994-08-25

    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 transferredmore » 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.« less

  16. Shell effects in a multinucleon transfer process

    NASA Astrophysics Data System (ADS)

    Zhu, Long; Wen, Pei-Wei; Lin, Cheng-Jian; Bao, Xiao-Jun; Su, Jun; Li, Cheng; Guo, Chen-Chen

    2018-04-01

    The shell effects in multinucleon transfer process are investigated in the systems 136Xe + 198Pt and 136Xe + 208Pb within the dinuclear system (DNS) model. The temperature dependence of shell corrections on potential energy surface is taken into account in the DNS model and remarkable improvement for description of experimental data is noticed. The reactions 136Xe + 186W and 150Nd + 186W are also studied. It is found that due to shell effects the projectile 150Nd is more promising for producing transtarget nuclei rather than 136Xe with neutron shell closure.

  17. Development and Testing of a Mobile Platform for Tank Remediation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nance, T.A.

    2001-01-16

    The Department of Energy (DOE) is committed to removing millions of gallons of high level radioactive waste from waste storage tanks at the Savannah River Site (SRS). SRS was the first site in the DOE complex to have emptied and closed high level waste tanks. Tank closure at the Site is now progressing to tanks containing waste composed of liquid and large deposits of solids, including a tank that has a potential ''heel''. A heel is a hardened mass of solid waste material spread across the tank bottom. Tank closure requires breaking up this heel and moving the material tomore » the intake of a pumping system for transfer from the tank. In the past, overhead spray systems have been used with some success at moving waste. But the limited number of risers restricts the coverage area of the overhead spray system. Therefore, a floor- level spray system will be used to separate manageable size chunks of the material from the heel. The chunks will be guided into the pump's intake to be remove from the tank. The floor-level spray system movement will be accomplished by using a mobile platform, a crawler, which provides transport to nearly every point on the tank floor. Transport of the spray system will allow the system to ''corral'' the waste away from the tank walls and control the movement of the material across the tank floor. Because the available access riser is small, and a wide crawler platform is required to support the spray system, the crawler's frame must fold to enter the tank. After entry into the tank, the crawler unfolds on the tank floor using the crawler drive tracks to expand the frame and position the mobile platform under the entry riser. The spray system will then be lowered separately through the entry riser and mated onto the crawler on the tank floor. The crawler and spray system are tethered and controlled remotely by personnel at the control station. Motorized cable reels will also be remotely controlled to pay out, retrieve, and manage the tethers as the mobile platform moves the spray system across the tank floor. Both the crawler and spray systems are designed to be retrievable. Development of the tank cleaning system was evaluated using a performance test program. The tests evaluated the spray system dynamics, the crawler's fit through the riser, the crawler landing in mocked up tank with simulant, the crawler's traction, and the crawler and spray system mating. Initial testing verified the crawler platform was compatible with the dynamics produced by the spray system. The riser fit test confirmed that a dedicated riser is required for deployment of the crawler and the spray system. The crawler traction test defined the capabilities of the crawler at different levels of simulant. Deployment testing through a mockup riser verified the basic system processes. Finally, testing of the complete system in a full-scale mockup with sludge simulant was performed to evaluate the tank cleaning ability of the crawler. This paper describes th e tank conditions, the tank closure process, the development of the crawler and spray system, and the testing program and results used to evaluate the mobile platform and spray system.« less

  18. Analysis of seismic stability of large-sized tank VST-20000 with software package ANSYS

    NASA Astrophysics Data System (ADS)

    Tarasenko, A. A.; Chepur, P. V.; Gruchenkova, A. A.

    2018-05-01

    The work is devoted to the study of seismic stability of vertical steel tank VST-20000 with due consideration of the system response “foundation-tank-liquid”, conducted on the basis of the finite element method, modal analysis and linear spectral theory. The calculations are performed for the tank model with a high degree of detailing of metallic structures: shells, a fixed roof, a bottom, a reinforcing ring.

  19. Feasibility and Practical Limits for the Use of Lightweight Prestressed Concrete (LWPC) as a Shipbuilding Material.

    DTIC Science & Technology

    1982-10-01

    centerline by stanchions. A concrete beam is provided at the ship centerline to transfer unbalanced stanchion loads longitudinally along the shell . The 01...Place Cast-in-Place Concrete Connections -- Connections betw. an precast shell elements are made using cast-in-place concrete closure pours. See Figure...buckling using the column provi sions of the ACI code. For shells , the critical radius to thickness ratio is about 200 for cylindrical shells loaded in

  20. 78 FR 15358 - DOE's Preferred Alternative for Certain Tanks Evaluated in the Final Tank Closure and Waste...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-11

    ... SUPPLEMENTARY INFORMATION.) \\1\\ Transuranic (TRU) waste is waste that contains alpha particle-emitting... available on the DOE NEPA Web site at http://energy.gov/nepa . Additional information on the Final TC & WM... INFORMATION CONTACT: For further information on the Final TC & WM EIS, contact Ms. Burandt as listed in...

  1. 49 CFR 179.220-18 - Bottom outlets.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.220-18 Bottom outlets. (a) The... equivalent, except that bottom outlet closure plugs may be attached by 1/4-inch chain. When the bottom outlet... valve body may be steam jacketed, in which case the breakage groove or its equivalent must be below the...

  2. System for removing liquid waste from a tank

    DOEpatents

    Meneely, Timothy K.; Sherbine, Catherine A.

    1994-01-01

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

  3. System for removing liquid waste from a tank

    DOEpatents

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

    1994-04-26

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

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    2013-11-14

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

  5. Analysis and test results for a molten salt thermal energy storage system

    NASA Astrophysics Data System (ADS)

    Sterrett, R. H.; Scott, O. L.

    A system has been developed to provide low cost thermal energy storage using molten salt. It consists of a hot tank to store the 565 C (1050 F) salt and a cold tank to store the 289 C (550 F) salt. The hot tank uses internal insulation protected by a liner to enable the use of a carbon steel shell for structural support. Due to the lower salt temperature, the cold tank can be a carbon steel shell with external insulation. This paper describes an analytical method used to predict the thermal performance of such systems and presents experimental data from a Subsystem Research Experiment (SRE) conducted by Martin Marietta Aerospace, Solar Energy Systems under contract from Sandia National Laboratories, Livermore, CA. The results from three of the SRE test cases are compared with the STS model results. These are (1) steady state operation, (2) concurrent charging and discharging, and (3) transient cooldown. The temperature differences between the analytical and experimental results were less than 10%. The internally insulated hot tank performed well.

  6. Evaluation of 241-AZ tank farm supporting phase 1 privatization waste feed delivery

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    CARLSON, A.B.

    1998-11-19

    This evaluation is one in a series of evaluations determining the process needs and assessing the adequacy of existing and planned equipment in meeting those needs at various double-shell tank farms in support of Phase 1 privatization. A number of tank-to-tank transfers and waste preparation activities are needed to process and feed waste to the private contractor in support of Phase 1 privatization. The scope of this evaluation is limited to process needs associated with 241-AZ tank farm during the Phase 1 privatization.

  7. RCRA/UST, superfund, and EPCRA hotline training module. Introduction to: RCRA subtitle I. Underground storage tanks (40 cfr part 280). Updated as of July 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1996-07-01

    This module explains the Underground Storage Tank Regulatory Program established in 1988, that includes technical requirements to prevent, protect, and clean up releases from Underground Storage Tanks (USTs), as well as financial responsibility requirements to guarantee that UST owners and operators have enough money set aside to clean up releases and compensate third parties. Describes the Universe of USTs and the technical and financial requirements that apply to them. Defines underground storage tank and provides criteria for determining which USTs are subject to regulation. Discusses deadlines for upgrading tanks and the closure and corrective action requirements.

  8. Tanks 18 And 19-F Structural Flowable Grout Fill Material Evaluation And Recommendations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Langton, C. A.; Stefanko, D. B.

    2013-04-23

    Cementitious grout will be used to close Tanks 18-F and 19-F. The functions of the grout are to: 1) physically stabilize the final landfill by filling the empty volume in the tanks with a non-compressible material; 2) provide a barrier for inadvertent intrusion into the tank; 3) reduce contaminant mobility by a) limiting the hydraulic conductivity of the closed tank and b) reducing contact between the residual waste and infiltrating water; and 4) providing an alkaline, chemically reducing environment in the closed tank to control speciation and solubility of selected radionuclides. The objective of this work was to identify amore » single (all-in-one) grout to stabilize and isolate the residual radionuclides in the tank, provide structural stability of the closed tank and serve as an inadvertent intruder barrier. This work was requested by V. A. Chander, High Level Waste (HLW) Tank Engineering, in HLW-TTR-2011-008. The complete task scope is provided in the Task Technical and QA Plan, SRNL-RP-2011-00587 Revision 0. The specific objectives of this task were to: 1) Identify new admixtures and dosages for formulating a zero bleed flowable tank fill material selected by HLW Tank Closure Project personnel based on earlier tank fill studies performed in 2007. The chemical admixtures used for adjusting the flow properties needed to be updated because the original admixture products are no longer available. Also, the sources of cement and fly ash have changed, and Portland cements currently available contain up to 5 wt. % limestone (calcium carbonate). 2) Prepare and evaluate the placement, compressive strength, and thermal properties of the selected formulation with new admixture dosages. 3) Identify opportunities for improving the mix selected by HLW Closure Project personnel and prepare and evaluate two potentially improved zero bleed flowable fill design concepts; one based on the reactor fill grout and the other based on a shrinkage compensating flowable fill mix design. 4) Prepare samples for hydraulic property measurements for comparison to the values in the F and H- Tank Farm Performance Assessments (PAs). 5) Identify a grout mix for the Tanks 18-F and 19-F Grout Procurement Specification [Forty, 2011 a, b, c]. Results for two flowable zero bleed structural fill concepts containing 3/8 inch gravel (70070 Series and LP#8 Series) and a sand only mix (SO Series) are provided in this report. Tank Farm Engineering and SRNL Project Management selected the 70070 mix as the base case for inclusion in Revision 0 of the Tanks 18-F and 19-F grout procurement specification [Forty 2011 a] and requested admixture recommendations and property confirmation for this formulation [Forty, 2011 b]. Lower cementitious paste mixes were formulated because the 70070 mix is over designed with respect to strength and generates more heat from hydration reactions than is desirable for mass pour application. Work was also initiated on a modification of the recommended mix which included shrinkage compensation to mitigate fast pathways caused by shrinkage cracking and poor physical bonding to the tank and ancillary equipment. Testing of this option was postponed to FY12. Mix, LP#8-16 is recommended for inclusion in the specification for furnishing and delivering tank closure grout for Tanks 18-F and 19-F [Forty, 2011 c]. A shrinkage compensating variation of this mix, LP#16C, has not been fully developed and characterized at this time.« less

  9. Probing the N = 14 subshell closure: g factor of the 26Mg (21+) state

    NASA Astrophysics Data System (ADS)

    McCormick, B. P.; Stuchbery, A. E.; Kibédi, T.; Lane, G. J.; Reed, M. W.; Eriksen, T. K.; Hota, S. S.; Lee, B. Q.; Palalani, N.

    2018-04-01

    The first-excited state g factor of 26Mg has been measured relative to the g factor of the 24Mg (21+) state using the high-velocity transient-field technique, giving g = + 0.86 ± 0.10. This new measurement is in strong disagreement with the currently adopted value, but in agreement with the sd-shell model using the USDB interaction. The newly measured g factor, along with E (21+) and B (E 2) systematics, signal the closure of the νd5/2 subshell at N = 14. The possibility that precise g-factor measurements may indicate the onset of neutron pf admixtures in first-excited state even-even magnesium isotopes below 32Mg is discussed and the importance of precise excited-state g-factor measurements on sd shell nuclei with N ≠ Z to test shell-model wavefunctions is noted.

  10. First Direct Mass Measurements of Nuclides around Z =100 with a Multireflection Time-of-Flight Mass Spectrograph

    NASA Astrophysics Data System (ADS)

    Ito, Y.; Schury, P.; Wada, M.; Arai, F.; Haba, H.; Hirayama, Y.; Ishizawa, S.; Kaji, D.; Kimura, S.; Koura, H.; MacCormick, M.; Miyatake, H.; Moon, J. Y.; Morimoto, K.; Morita, K.; Mukai, M.; Murray, I.; Niwase, T.; Okada, K.; Ozawa, A.; Rosenbusch, M.; Takamine, A.; Tanaka, T.; Watanabe, Y. X.; Wollnik, H.; Yamaki, S.

    2018-04-01

    The masses of 246Es, 251Fm, and the transfermium nuclei Md-252249 and 254No, produced by hot- and cold-fusion reactions, in the vicinity of the deformed N =152 neutron shell closure, have been directly measured using a multireflection time-of-flight mass spectrograph. The masses of 246Es and 249,250,252Md were measured for the first time. Using the masses of Md,250249 as anchor points for α decay chains, the masses of heavier nuclei, up to 261Bh and 266Mt, were determined. These new masses were compared with theoretical global mass models and demonstrated to be in good agreement with macroscopic-microscopic models in this region. The empirical shell gap parameter δ2 n derived from three isotopic masses was updated with the new masses and corroborates the existence of the deformed N =152 neutron shell closure for Md and Lr.

  11. Multilayer Composite Pressure Vessels

    NASA Technical Reports Server (NTRS)

    DeLay, Tom

    2005-01-01

    A method has been devised to enable the fabrication of lightweight pressure vessels from multilayer composite materials. This method is related to, but not the same as, the method described in gMaking a Metal- Lined Composite-Overwrapped Pressure Vessel h (MFS-31814), NASA Tech Briefs, Vol. 29, No. 3 (March 2005), page 59. The method is flexible in that it poses no major impediment to changes in tank design and is applicable to a wide range of tank sizes. The figure depicts a finished tank fabricated by this method, showing layers added at various stages of the fabrication process. In the first step of the process, a mandrel that defines the size and shape of the interior of the tank is machined from a polyurethane foam or other suitable lightweight tooling material. The mandrel is outfitted with metallic end fittings on a shaft. Each end fitting includes an outer flange that has a small step to accommodate a thin layer of graphite/epoxy or other suitable composite material. The outer surface of the mandrel (but not the fittings) is covered with a suitable release material. The composite material is filament- wound so as to cover the entire surface of the mandrel from the step on one end fitting to the step on the other end fitting. The composite material is then cured in place. The entire workpiece is cut in half in a plane perpendicular to the axis of symmetry at its mid-length point, yielding two composite-material half shells, each containing half of the foam mandrel. The halves of the mandrel are removed from within the composite shells, then the shells are reassembled and bonded together with a belly band of cured composite material. The resulting composite shell becomes a mandrel for the subsequent steps of the fabrication process and remains inside the final tank. The outer surface of the composite shell is covered with a layer of material designed to be impermeable by the pressurized fluid to be contained in the tank. A second step on the outer flange of each end fitting accommodates this layer. Depending on the application, this layer could be, for example, a layer of rubber, a polymer film, or an electrodeposited layer of metal. If the fluid to be contained in the tank is a gas, then the best permeation barrier is electrodeposited metal (typically copper or nickel), which can be effective at a thickness of as little as 0.005 in (.0.13 mm). The electrodeposited metal becomes molecularly bonded to the second step on each metallic end fitting. The permeation-barrier layer is covered with many layers of filament-wound composite material, which could be the same as, or different from, the composite material of the inner shell. Finally, the filament-wound composite material is cured in an ov

  12. DOUBLE SHELL TANK (DST) INTEGRITY PROJECT HIGH LEVEL WASTE CHEMISTRY OPTIMIZATION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    WASHENFELDER DJ

    2008-01-22

    The U.S. Department of Energy's Office (DOE) of River Protection (ORP) has a continuing program for chemical optimization to better characterize corrosion behavior of High-Level Waste (HLW). The DOE controls the chemistry in its HLW to minimize the propensity of localized corrosion, such as pitting, and stress corrosion cracking (SCC) in nitrate-containing solutions. By improving the control of localized corrosion and SCC, the ORP can increase the life of the Double-Shell Tank (DST) carbon steel structural components and reduce overall mission costs. The carbon steel tanks at the Hanford Site are critical to the mission of safely managing stored HLWmore » until it can be treated for disposal. The DOE has historically used additions of sodium hydroxide to retard corrosion processes in HLW tanks. This also increases the amount of waste to be treated. The reactions with carbon dioxide from the air and solid chemical species in the tank continually deplete the hydroxide ion concentration, which then requires continued additions. The DOE can reduce overall costs for caustic addition and treatment of waste, and more effectively utilize waste storage capacity by minimizing these chemical additions. Hydroxide addition is a means to control localized and stress corrosion cracking in carbon steel by providing a passive environment. The exact mechanism that causes nitrate to drive the corrosion process is not yet clear. The SCC is less of a concern in the newer stress relieved double shell tanks due to reduced residual stress. The optimization of waste chemistry will further reduce the propensity for SCC. The corrosion testing performed to optimize waste chemistry included cyclic potentiodynamic volarization studies. slow strain rate tests. and stress intensity factor/crack growth rate determinations. Laboratory experimental evidence suggests that nitrite is a highly effective:inhibitor for pitting and SCC in alkaline nitrate environments. Revision of the corrosion control strategies to a nitrite-based control, where there is no constant depletion mechanism as with hydroxide, should greatly enhance tank lifetime, tank space availability, and reduce downstream reprocessing costs by reducing chemical addition to the tanks.« less

  13. Hanford Tanks 241-C-203 and 241 C 204: Residual Waste Contaminant Release Model and Supporting Data

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    This report was revised in May 2007 to correct 90Sr values in Chapter 3. The changes were made on page 3.9, paragraph two and Table 3.10; page 3.16, last paragraph on the page; and Tables 3.21 and 3.31. The rest of the text remains unchanged from the original report issued in October 2004. This report describes the development of release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks.more » Key results from this work are (1) future releases from the tanks of the primary contaminants of concern (99Tc and 238U) can be represented by relatively simple solubility relationships between infiltrating water and solid phases containing the contaminants; and (2) high percentages of technetium-99 in the sludges (20 wt% in C-203 and 75 wt% in C-204) are not readily water leachable, and, in fact, are very recalcitrant. This is similar to results found in related studies of sludges from Tank AY-102. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for the U.S. Department of Energy.« less

  14. TMA Chemical Release Payloads for Stratospheric Wind Measurements Auroral E Program and Related Programs

    DTIC Science & Technology

    1982-03-15

    this work was to provide a piston tank filled with trimethyl aluminum for release as a trail in the upper atmosphere. This payload was launched from the...trail payloads. II. PAYLOAD DESCRIPTION The payload consists of a programmer section with plumbing and a piston tank section. The outer shell of the...payload is the wall of the piston tank . The liquid side of the piston tank is filled with 20 pounds of tri- methyl- aluminum (TMA). After filling the

  15. Nuclear Structure of 186Re

    DTIC Science & Technology

    2016-12-24

    D population-depopulation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 AME Atomic Mass Evaluation...this mass region are important for validating models of nuclear structure and reactions. The ENSDF feeds a specific data library relevant to nuclear...spherically asymmetric. Spherical asymmetry is common for nuclei between shell closures, such as those in the mid-shell 150  A  190 mass range of interest

  16. Tank measurements of scattering from a resin-filled fiberglass spherical shell with internal flaws.

    PubMed

    Tesei, Alessandra; Guerrini, Piero; Zampolli, Mario

    2008-08-01

    This paper presents results of acoustic inversion and structural health monitoring achieved by means of low to midfrequency elastic scattering analysis of simple, curved objects, insonified in a water tank. Acoustic elastic scattering measurements were conducted between 15 and 100 kHz on a 60-mm-radius fiberglass spherical shell, filled with a low-shear-speed epoxy resin. Preliminary measurements were conducted also on the void shell before filling, and on a solid sphere of the same material as the filler. These data were used to estimate the constituent material parameters via acoustic inversion. The objects were measured in the backscatter direction, suspended at midwater, and insonified by a broadband directional transducer. From the inspection of the response of the solid-filled shell it was possible to detect and characterize significant inhomogeneities of the interior (air pockets), the presence of which were later confirmed by x-ray CT scan and ultrasound measurements. Elastic wave analysis and a model-data comparison study support the physical interpretation of the measurements.

  17. Solar hot water system installed at Days Inn Motel, Dallas, Texas (Forrest Lane)

    NASA Technical Reports Server (NTRS)

    1980-01-01

    The solar system was designed to provide 65 percent of the total Domestic Hot Water (DHW) demand. The liquid flat plate (water) collector (1,000 square feet) system automatically drains into the 1,000 gallon steel storage tank located in the mechanical room when the pump is not running. Heat is transferred from the storage tank to DHW tanks through a tube and shell heat exchanger. A circulating pump between the DHW tanks and the heat exchanger enables solar heated water to help make DHW tank standby losses. All pumps are controlled by differential temperature.

  18. Progress in Hanford's Double-Shell Tank Integrity Project

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bryson, D.C.; Washenfelder, D.J.; Boomer, K.D.

    2008-07-01

    The U.S. Department of Energy's Office of River Protection has an extensive integrity assessment program for the Hanford Site Double-Shell Tank System. The DOE Orders and environmental protection regulations provide the guidelines for the activities used to inspect and maintain 28 double-shell tanks (DSTs), the waste evaporator, and ancillary equipment that compose this system. This program has been reviewed by oversight and regulatory bodies and found to comply with the established guidelines. The basis for the DOE Order 435.1-1 for tank integrity comes from the Tank Structural Integrity Panel led by Brookhaven National Laboratory during the late 1990's. These guidelinesmore » established criteria for performing Non-Destructive Examination (NDE), for acceptance of the NDE results, for waste chemistry control, and for monitoring the tanks. The environmental regulations mirror these requirements and allow for the tank integrity program to provide compliant storage of the tanks. Both sets of requirements provide additional guidance for the protection of ancillary equipment. CH2M HILL uses two methods of NDE: visual inspection and Ultrasonic Testing (UT). The visual inspection program examines the primary tank and secondary liner of the DST. The primary tank is examined both on the interior surface above the waste in the tank and on the exterior surface facing the annulus of the DST. The interior surface of the tank liner is examined at the same time as the outer surface of the primary tank. The UT program examines representative areas of the primary tank and secondary liner by deploying equipment in the annulus of the tank. Both programs have led to the development of new equipment for remote inspection of the tanks. Compact camera and enhanced lighting systems have been designed and deployed through narrow access ports (called risers) into the tanks. The UT program has designed two generations of crawlers and equipment for deployment through risers into the thermally hot and radioactive environment. Also extensions were developed to allow inspection of the tank's curve upper (haunch) and lower (knuckle) surfaces. CH2M HILL primarily maintains chemistry control of the DST by ensuring that the concentrations of hydroxide and nitrite ions are favorable with respect to the nitrate ion concentration in the waste. This control program is supported by an extensive sampling program that obtains samples from the supernatant and solid layers in the tank to ensure compliance with the chemical specification. At DOE direction, CH2M HILL has embarked on a waste chemistry optimization program to enhance the protection of the tank surface and the understanding of the parameters that affect general and localized corrosion in the tanks. Over the past decade, DOE has deployed Electrochemical Noise corrosion probes in the DST to monitor localized corrosion. From the information gathered as part of the chemistry control, new information has been identified about the parameters requiring control to ensure tank integrity. CH2M HILL is deploying a series of corrosion probes to test and employ these parameters to provide real time corrosion monitoring of the DSTs. (authors)« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    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.

  20. FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    KRIPPS, L.J.

    2005-02-18

    This document describes the qualitative evaluation of frequency and consequences for double shell tank (DST) and single shell tank (SST) representative flammable gas accidents and associated hazardous conditions without controls. The evaluation indicated that safety-significant SSCs and/or TSRS were required to prevent or mitigate flammable gas accidents. Discussion on the resulting control decisions is included. This technical basis document was developed to support of the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process for the flammable gas representative accidents and associated represented hazardous conditions. The purpose of the risk binning process is to determine the needmore » for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous condition based on an evaluation of the event frequency and consequence.« less

  1. Tank waste remediation system nuclear criticality safety program management review

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BRADY RAAP, M.C.

    1999-06-24

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999.

  2. Final Report One-Twelfth-Scale Mixing Experiments to Characterize Double-Shell Tank Slurry Uniformity

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bamberger, Judith A.; Liljegren, Lucia M.; Enderlin, Carl W.

    The objectives of these 1/12-scale scoping experiments were to: Determine which of the dimensionless parameters discussed in Bamberger and Liljegren (1994) affect the maximum concentration that can be suspended during jet mixer pump operation in the full-scale double-shell tanks; Develop empirical correlations to predict the nozzle velocity required for jet mixer pumps to suspend the contents of full-scale double-shell tanks; Apply the models to predict the nozzle velocity required to suspend the contents of Tank 241 AZ-101; Obtain experimental concentration data to compare with the TEMPEST( )(Trent and Eyler 1989) computational modeling predictions to guide further code development; Analyze themore » effects of changing nozzle diameter on exit velocity (U0) and U0D0 (the product of the exit velocity and nozzle diameter) required to suspend the contents of a tank. The scoping study experimentally evaluated uniformity in a 1/12-scale experiment varying the Reynolds number, Froude number, and gravitational settling parameter space. The initial matrix specified only tests at 100% U0D0 and 25% U0D0. After initial tests were conducted with small diameter, low viscosity simulant this matrix was revised to allow evaluation of a broader range of U0D0s. The revised matrix included full factorial test between 100% and 50% U0D0 and two half-factorial tests at 75% and 25% U0D0. Adding points at 75% U0D0 and 50% U0D0 allowed evaluation curvature. Eliminating points at 25% U0D0 decreased the testing time by several weeks. Test conditions were achieved by varying the simulant viscosity, the mean particle size, and the jet nozzle exit velocity. Concentration measurements at sampling locations throughout the tank were used to assess the degree of uniformity achieved during each test. Concentration data was obtained using a real time ultrasonic attenuation probe and discrete batch samples. The undissolved solids concentration at these locations was analyzed to determine whether the tank contents were uniform (< ±10% variation about mean) or nonuniform (> ±10% variation about mean) in concentration. Concentration inhomogeneity was modeled as a function of dimensionless groups. The two parameters that best describe the maximum solids volume fraction that can be suspended in a double-shell tank were found to be 1) the Froude number (Fr) based on nozzle velocity (U0) and tank contents level (H) and 2) the dimensionless particle size (dp/D0). The dependence on the Reynolds number (Re) does not appear to be statistically significant.« less

  3. Solid Phase Characterization of Tank 241-C-105 Grab Samples

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ely, T. M.; LaMothe, M. E.; Lachut, J. S.

    The solid phase characterization (SPC) of three grab samples from single-shell Tank 241-C-105 (C-105) that were received at the laboratory the week of October 26, 2015, has been completed. The three samples were received and broken down in the 11A hot cells.

  4. Annular Air Leaks in a liquid hydrogen storage tank

    NASA Astrophysics Data System (ADS)

    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.

  5. Soil load above Hanford waste storage tanks (2 volumes)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pianka, E.W.

    1995-01-25

    This document is a compilation of work performed as part of the Dome Load Control Project in 1994. Section 2 contains the calculations of the weight of the soil over the tank dome for each of the 75-feet-diameter waste-storage tanks located at the Hanford Site. The chosen soil specific weight and soil depth measured at the apex of the dome crown are the same as those used in the primary analysis that qualified the design. Section 3 provides reference dimensions for each of the tank farm sites. The reference dimensions spatially orient the tanks and provide an outer diameter formore » each tank. Section 4 summarizes the available soil surface elevation data. It also provides examples of the calculations performed to establish the present soil elevation estimates. The survey data and other data sources from which the elevation data has been obtained are printed separately in Volume 2 of this Supporting Document. Section 5 contains tables that provide an overall summary of the present status of dome loads. Tables summarizing the load state corresponding to the soil depth and soil specific weight for the original qualification analysis, the gravity load requalification for soil depth and soil specific weight greater than the expected actual values, and a best estimate condition of soil depth and specific weight are presented for the Double-Shell Tanks. For the Single-Shell Tanks, only the original qualification analysis is available; thus, the tabulated results are for this case only. Section 6 provides a brief overview of past analysis and testing results that given an indication of the load capacity of the waste storage tanks that corresponds to a condition approaching ultimate failure of the tank. 31 refs.« less

  6. Hydroelastic vibration analysis of partially liquid-filled shells using a series representation of the liquid

    NASA Technical Reports Server (NTRS)

    Housner, J. M.; Herr, R. W.; Sewall, J. L.

    1980-01-01

    A series representation of the oscillatory behavior of incompressible nonviscous liquids contained in partially filled elastic tanks is presented. Each term is selected on the basis of hydroelastic vibrations in circular cylindrical tanks. Using a complementary energy principle, the superposition of terms is made to approximately satisfy the liquid-tank interface compatibility. This analysis is applied to the gravity sloshing and hydroelastic vibrations of liquids in hemispherical tanks and in a typical elastic aerospace propellant tank. With only a few series terms retained, the results correlate very well with existing analytical results, NASTRAN-generated analytical results, and experimental test results. Hence, although each term is based on a cylindrical tank geometry, the superposition can be successfully applied to noncylindrical tanks.

  7. Multiple lead seal assembly for a liquid-metal-cooled fast-breeder nuclear reactor

    DOEpatents

    Hutter, Ernest; Pardini, John A.

    1977-03-15

    A reusable multiple lead seal assembly provides leak-free passage of stainless-steel-clad instrument leads through the cover on the primary tank of a liquid-metal-cooled fast-breeder nuclear reactor. The seal isolates radioactive argon cover gas and sodium vapor within the primary tank from the exterior atmosphere and permits reuse of the assembly and the stainless-steel-clad instrument leads. Leads are placed in flutes in a seal body, and a seal shell is then placed around the seal body. Circumferential channels in the body and inner surface of the shell are contiguous and together form a conduit which intersects each of the flutes, placing them in communication with a port through the wall of the seal shell. Liquid silicone rubber sealant is injected into the flutes through the port and conduit; the sealant fills the space in the flutes not occupied by the leads themselves and dries to a rubbery hardness. A nut, threaded onto a portion of the seal body not covered by the seal shell, jacks the body out of the shell and shears the sealant without damage to the body, shell, or leads. The leads may then be removed from the body. The sheared sealant is cleaned from the body, leads, and shell and the assembly may then be reused with the same or different leads.

  8. Closure Report for Corrective Action Unit 516: Septic Systems and Discharge Points

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Restoration

    Corrective Action Unit (CAU) 516 is located in Areas 3, 6, and 22 of the Nevada Test Site. CAU 516 is listed in the Federal Facility Agreement and Consent Order of 1996 as Septic Systems and Discharge Points, and is comprised of six Corrective Action Sites (CASs): {sm_bullet} CAS 03-59-01, Bldg 3C-36 Septic System {sm_bullet} CAS 03-59-02, Bldg 3C-45 Septic System {sm_bullet} CAS 06-51-01, Sump and Piping {sm_bullet} CAS 06-51-02, Clay Pipe and Debris {sm_bullet} CAS 06-51-03, Clean Out Box and Piping {sm_bullet} CAS 22-19-04, Vehicle Decontamination Area The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASsmore » 06-51-02 and 22-19-04 is no further action. The NDEP-approved corrective action alternative for CASs 03-59-01, 03-59-02, 06-51-01, and 06-51-03 is clean closure. Closure activities included removing and disposing of total petroleum hydrocarbon (TPH)-impacted septic tank contents, septic tanks, distribution/clean out boxes, and piping. CAU 516 was closed in accordance with the NDEP-approved CAU 516 Corrective Action Plan (CAP). The closure activities specified in the CAP were based on the recommendations presented in the CAU 516 Corrective Action Decision Document (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2004). This Closure Report documents CAU 516 closure activities. During closure activities, approximately 186 tons of hydrocarbon waste in the form of TPH-impacted soil and debris, as well as 89 tons of construction debris, were generated and managed and disposed of appropriately. Waste minimization techniques, such as field screening of soil samples and the utilization of laboratory analysis to characterize and classify waste streams, were employed during the performance of closure work.« less

  9. HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SEISMIC ANALYSIS IN SUPPORT OF INCREASED LIQUID LEVEL IN 241-AP TANK FARMS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    TC MACKEY; FG ABATT; MW RINKER

    2009-01-14

    The essential difference between Revision 1 and the original issue of this report is in the spring constants used to model the anchor bolt response for the anchor bolts that tie the steel dome of the primary tank to the concrete tank dome. Consequently, focus was placed on the changes in the anchor bolt responses, and a full reevaluation of all tank components was judged to be unnecessary. To confirm this judgement, primary tank stresses from the revised analysis of the BES-BEC case are compared to the original analysis and it was verified that the changes are small, as expected.

  10. Alternatives generation and analysis for double-shell tank primary ventilation systems emissions control and monitoring

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    SEDERBURG, J.P.

    1999-09-30

    This AGA addresses the question: ''What equipment upgrades, operational changes, and/or other actions are required relative to the DST tanks farms' ventilation systems to support retrieval, staging (including feed sampling), and delivery of tank waste to the Phase I private contractor?'' Issues and options for the various components within the ventilation subsystem affect each other. Recommended design requirements are presented and the preferred alternatives are detailed.

  11. Effects of Initial Geometric Imperfections On the Non-Linear Response of the Space Shuttle Superlightweight Liquid-Oxygen Tank

    NASA Technical Reports Server (NTRS)

    Nemeth, Michael P.; Young, Richard D.; Collins, Timothy J.; Starnes, James H., Jr.

    2002-01-01

    The results of an analytical study of the elastic buckling and nonlinear behavior of the liquid-oxygen tank for the new Space Shuttle superlightweight external fuel tank are presented. Selected results that illustrate three distinctly different types of non-linear response phenomena for thin-walled shells which are subjected to combined mechanical and thermal loads are presented. These response phenomena consist of a bifurcation-type buckling response, a short-wavelength non-linear bending response and a non-linear collapse or "snap-through" response associated with a limit point. The effects of initial geometric imperfections on the response characteristics are emphasized. The results illustrate that the buckling and non-linear response of a geometrically imperfect shell structure subjected to complex loading conditions may not be adequately characterized by an elastic linear bifurcation buckling analysis, and that the traditional industry practice of applying a buckling-load knock-down factor can result in an ultraconservative design. Results are also presented that show that a fluid-filled shell can be highly sensitive to initial geometric imperfections, and that the use a buckling-load knock-down factor is needed for this case.

  12. Closure system

    DOEpatents

    Hertelendy, N.A.

    1987-04-22

    A pressure resistant seal for a metallic container is formed between a cylindrical portion having one end open and a cap which seals the open end of the shell. The cap is in the form of a frusto-conical flange which is inserted narrow end first into the open end of the shell and the container is sealed by means of a capping tool which pulls the flange against a die, deforming the flange and forcing the edge of the flange into the wall of the shell. 6 figs.

  13. Closure system

    DOEpatents

    Hertelendy, Nicholas A [Kennewick, WA

    1989-01-01

    A pressure resistant seal for a metallic container is formed between a cylindrical portion having one end open and a cap which seals the open end of the shell. The cap is in the form of a frusto-conical flange which is inserted narrow end first into the open end of the shell and the container is sealed by means of a capping tool which pulls the flange against a die, deforming the flange and forcing the edge of the flange into the wall of the shell.

  14. Closure system

    DOEpatents

    Hertelendy, Nicholas A.

    1989-04-04

    A pressure resistant seal for a metallic container is formed between a cylindrical portion having one end open and a cap which seals the open end of the shell. The cap is in the form of a frusto-conical flange which is inserted narrow end first into the open end of the shell and the container is sealed by means of a capping tool which pulls the flange against a die, deforming the flange and forcing the edge of the flange into the wall of the shell.

  15. Molten salt thermal energy storage subsystem for Solar Thermal Central Receiver plants

    NASA Astrophysics Data System (ADS)

    Wells, P. B.; Nassopoulos, G. P.

    The development of a low-cost thermal energy storage subsystem for large solar plants is analyzed. Molten nitrate salt is used as both the plant's working fluid and as the storage medium. The storage system comprises a specially designed hot tank to hold salt at a storage temperature of 839 K (1050 F) and a separate carbon steel cold tank to hold the salt after its thermal energy has been extracted to generate steam. The hot tank is lined with insulating firebrick to lower the shell temperature to 561 K (550 F) so that a low-cost carbon steel shell can be used. A preliminary design is described for a large commercial-size plant (1200 MWht). Also described are a laboratory test program for the critical components and the design, construction, and test of a small-scale research experiment at the Central Receiver Test Facility in Albuquerque, New Mexico.

  16. Hanford Double Shell Waste Tank Corrosion Studies - Final Report FY2015

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fuentes, R. E.; Wyrwas, R. B.

    2016-05-01

    During FY15, SRNL performed corrosion testing that supported Washington River Protection Solutions (WRPS) with their double shell tank (DST) integrity program. The testing investigated six concerns including, 1) the possibility of corrosion of the exterior of the secondary tank wall; 2) the effect of ammonia on vapor space corrosion (VSC) above waste simulants; 3) the determination of the minimum required nitrite and hydroxide concentrations that prevent pitting in concentrated nitrate solutions (i.e., waste buffering); 4) the susceptibility to liquid air interface (LAI) corrosion at proposed stress corrosion cracking (SCC) inhibitor concentrations; 5) the susceptibility of carbon steel to pitting inmore » dilute solutions that contain significant quantities of chloride and sulfate; and 6) the effect of different heats of A537 carbon steel on the corrosion response. For task 1, 2, and 4, the effect of heat treating and/ or welding of the materials was also investigated.« less

  17. First Images of R Aquarii and Its Asymmetric H2O Shell

    NASA Astrophysics Data System (ADS)

    Ragland, S.; Le Coroller, H.; Pluzhnik, E.; Cotton, W. D.; Danchi, W. C.; Monnier, J. D.; Traub, W. A.; Willson, L. A.; Berger, J.-P.; Lacasse, M. G.

    2008-05-01

    We report imaging observations of the symbiotic long-period Mira variable R Aquarii (R Aqr) at near-infrared and radio wavelengths. The near-infrared observations were made with the IOTA imaging interferometer in three narrowband filters centered at 1.51, 1.64, and 1.78 μm, which sample mainly water, continuum, and water features, respectively. Our near-infrared fringe visibility and closure phase data are analyzed using three models. (1) A uniform disk model with wavelength-dependent sizes fails to fit the visibility data, and is inconsistent with the closure phase data. (2) A three-component model, consisting of a Mira star, water shell, and an off-axis point source, provide a good fit to all data. (3) A model generated by a constrained image reconstruction analysis provides more insight, suggesting that the water shell is highly nonuniform, i.e., clumpy. The VLBA observations of SiO masers in the outer molecular envelope show evidence of turbulence, with jetlike features containing velocity gradients.

  18. 46 CFR 151.50-10 - Alkylene oxides.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... terminate in the liquid space and shall be attached to the shell by welding with the end of the fitting... BULK LIQUID HAZARDOUS MATERIAL CARGOES Special Requirements § 151.50-10 Alkylene oxides. (a) For the... alkylene oxide in either the liquid or vapor state is present in any cargo tank. Alkylene oxide tanks shall...

  19. 46 CFR 151.50-10 - Alkylene oxides.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... terminate in the liquid space and shall be attached to the shell by welding with the end of the fitting... BULK LIQUID HAZARDOUS MATERIAL CARGOES Special Requirements § 151.50-10 Alkylene oxides. (a) For the... alkylene oxide in either the liquid or vapor state is present in any cargo tank. Alkylene oxide tanks shall...

  20. 46 CFR 151.50-10 - Alkylene oxides.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... terminate in the liquid space and shall be attached to the shell by welding with the end of the fitting... BULK LIQUID HAZARDOUS MATERIAL CARGOES Special Requirements § 151.50-10 Alkylene oxides. (a) For the... alkylene oxide in either the liquid or vapor state is present in any cargo tank. Alkylene oxide tanks shall...

  1. 46 CFR 151.50-10 - Alkylene oxides.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... terminate in the liquid space and shall be attached to the shell by welding with the end of the fitting... BULK LIQUID HAZARDOUS MATERIAL CARGOES Special Requirements § 151.50-10 Alkylene oxides. (a) For the... alkylene oxide in either the liquid or vapor state is present in any cargo tank. Alkylene oxide tanks shall...

  2. 46 CFR 151.50-10 - Alkylene oxides.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... terminate in the liquid space and shall be attached to the shell by welding with the end of the fitting... BULK LIQUID HAZARDOUS MATERIAL CARGOES Special Requirements § 151.50-10 Alkylene oxides. (a) For the... alkylene oxide in either the liquid or vapor state is present in any cargo tank. Alkylene oxide tanks shall...

  3. 49 CFR 179.100-7 - Materials.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... welding and must comply with one of the following specifications (IBR, see § 171.7 of this subchapter... sensitizing treatment prior to testing. (d) All attachments welded to tank shell must be of approved material which is suitable for welding to the tank. [Amdt. 179-10, 36 FR 21344, Nov. 6, 1971, as amended by Amdt...

  4. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reidel, Stephen P.; Chamness, Mickie A.

    This data package discusses the geology of the single-shell tank (SST) farms and the geologic history of the area. The purpose 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.

  5. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reidel, Steve P.; Chamness, Mickie A.

    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.

  6. Thermodynamic model for uranium release from hanford site tank residual waste.

    PubMed

    Cantrell, Kirk J; Deutsch, William J; Lindberg, Mike J

    2011-02-15

    A thermodynamic model of U solid-phase solubility and paragenesis was developed for Hanford Site tank residual waste that will remain in place after tank closure. The model was developed using a combination of waste composition data, waste leach test data, and thermodynamic modeling of the leach test data. The testing and analyses were conducted using actual Hanford Site tank residual waste. Positive identification of U phases by X-ray diffraction was generally not possible either because solids in the waste were amorphous or their concentrations were not detectable by XRD for both as-received and leached residual waste. Three leachant solutions were used in the studies: deionized water, CaCO3 saturated solution, and Ca(OH)2 saturated solution. Analysis of calculated saturation indices indicate that NaUO2PO4·xH2O and Na2U2O7(am) are present in the residual wastes initially. Leaching of the residual wastes with deionized water or CaCO3 saturated solution results in preferential dissolution Na2U2O7(am) and formation of schoepite. Leaching of the residual wastes with Ca(OH)2 saturated solution appears to result in transformation of both NaUO2PO4·xH2O and Na2U2O7(am) to CaUO4. Upon the basis of these results, the paragenetic sequence of secondary phases expected to occur as leaching of residual waste progresses for two tank closure scenarios was identified.

  7. Laminated anisotropic reinforced plastic plates and shells

    NASA Technical Reports Server (NTRS)

    Korolev, V. I.

    1981-01-01

    Basic technical theories and engineering calculation equations for anisotropic plates and shells made of rigid reinforced plastics, mainly laminated fiberglass, are presented and discussed. Solutions are given for many problems of design of structural plates and shells, including curved sections and tanks, as well as two chapters on selection of the optimum materials, are given. Accounting for interlayer shearing and transverse separation, which are new engineering properties, are discussed. Application of the results obtained to thin three ply plates and shells wth a light elastic filler is presented and discussed.

  8. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 204: STORAGE BUNKERS, NEVADA TEST SITE, NEVADA

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    Corrective Action Unit (CAU) 330 consists of four Corrective Action Sites (CASs) located in Areas 6, 22, and 23 of the Nevada Test Site (NTS). The unit is listed in the Federal Facility Agreement and Consent Order (FFACO, 1996) as CAU 330: Areas 6, 22, and 23 Tanks and Spill Sites. CAU 330 consists of the following CASs: CAS 06-02-04, Underground Storage Tank (UST) and Piping CAS 22-99-06, Fuel Spill CAS 23-01-02, Large Aboveground Storage Tank (AST) Farm CAS 23-25-05, Asphalt Oil Spill/Tar Release

  9. NALE-IT

    EPA Pesticide Factsheets

    Technical product bulletin: this surface washing agent for oil spill cleanups is applied by pressure sprayer to pit closures, surface hydrocarbon spills, compressor stations, pipeline and flow line leaks, well head and tank farm leaks, and highway spills

  10. A Study of Multi-Λ Hypernuclei Within Spherical Relativistic Mean-Field Approach

    NASA Astrophysics Data System (ADS)

    Rather, Asloob A.; Ikram, M.; Usmani, A. A.; Kumar, B.; Patra, S. K.

    2017-12-01

    This research article is a follow up of an earlier work by M. Ikram et al., reported in Int. J. Mod. Phys. E 25, 1650103 (2016) where we searched for Λ magic numbers in experimentally confirmed doubly magic nucleonic cores in light to heavy mass region (i.e., 16 O-208 P b) by injecting Λ's into them. In the present manuscript, working within the state of the art relativistic mean field theory with the inclusion of Λ N and ΛΛ interaction in addition to nucleon-meson NL 3∗ effective force, we extend the search of lambda magic numbers in multi- Λ hypernuclei using the predicted doubly magic nucleonic cores 292120, 304120, 360132, 370132, 336138, 396138 of the elusive superheavy mass regime. In analogy to well established signatures of magicity in conventional nuclear theory, the prediction of hypernuclear magicities is made on the basis of one-, two- Λ separation energy ( S Λ, S 2Λ) and two lambda shell gaps ( δ 2Λ) in multi- Λ hypernuclei. The calculations suggest that the Λ numbers 92, 106, 126, 138, 184, 198, 240, and 258 might be the Λ shell closures after introducing the Λ's in the elusive superheavy nucleonic cores. The appearance of new lambda shell closures apart from the nucleonic ones predicted by various relativistic and non-relativistic theoretical investigations can be attributed to the relatively weak strength of the spin-orbit coupling in hypernuclei compared to normal nuclei. Further, the predictions made in multi- Λ hypernuclei under study resembles closely the magic numbers in conventional nuclear theory suggested by various relativistic and non-relativistic theoretical models. Moreover, in support of the Λ shell closure, the investigation of Λ pairing energy and effective Λ pairing gap has been made. We noticed a very close agreement of the predicted Λ shell closures with the survey made on the pretext of S Λ, S 2Λ, and δ 2Λ except for the appearance of magic numbers corresponding to Λ = 156 which manifest in Λ effective pairing gap and pairing energy. Also, the lambda single-particle spectrum is analyzed to mark the energy shell gap for further strengthening the predictions made on the basis of separation energies and shell gaps. Lambda and nucleon spin-orbit interactions are analyzed to confirm the reduction in magnitude of Λ spin-orbit interaction compared to the nucleonic case, however the interaction profile is similar in both the cases. Lambda and nucleon density distributions have been investigated to reveal the impurity effect of Λ hyperons which make the depression of central density of the core of superheavy doubly magic nuclei. Lambda skin structure is also seen.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Girardot, Crystal L.; Harlow, Donald G.

    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.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    RAST RS; RINKER MW; WASHENFELDER DJ

    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 Hanfordmore » 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 other surface conditions that may indicate signs of structural distress. The condition of the concrete and rebar of the Hanford SSTs is currently being tested and planned for additional activities in the near future. Concrete and rebar removed from the dome of a 65-year-old tank is being tested for mechanics properties and condition. Results indicated stronger than designed concrete with additional Petrographic examination and rebar testing ongoing. Material properties determined from previous efforts combined with current testing and construction document review will help to generate a database that will provide continuing indication of Hanford SST structural integrity.« less

  13. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reidel, Stephen P.

    This chapter summarizes the geology of the single-shell tank (SST) farms in the context of the region’s geologic history. This chapter is based on the information in the geology data package for the SST waste management areas and SST RFI Appendix E, which builds upon previous reports on the tank farm geology and Integrated Disposal Facility geology with information available after those reports were published.

  14. 49 CFR 179.300-8 - Tank heads.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ...-110A tanks shall have fusion-welded heads formed concave to pressure. Heads for fusion welding shall be... one heat so as to provide a straight flange at least 11/2 inches long. The thickness shall not be less... shell. They must be one piece, hot formed in one heat so as to provide a straight flange at least 4...

  15. 49 CFR 178.338-16 - Inspection and testing.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... all such residue and cleaning solution must be removed from the tank prior to final closure of the... heat-treated, if such heat treatment was previously performed, and the repaired areas must be retested...

  16. TANK SPACE ALTERNATIVES ANALYSIS REPORT

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    TURNER DA; KIRCH NW; WASHENFELDER DJ

    2010-04-27

    This report addresses the projected shortfall of double-shell tank (DST) space starting in 2018. Using a multi-variant methodology, a total of eight new-term options and 17 long-term options for recovering DST space were evaluated. These include 11 options that were previously evaluated in RPP-7702, Tank Space Options Report (Rev. 1). Based on the results of this evaluation, two near-term and three long-term options have been identified as being sufficient to overcome the shortfall of DST space projected to occur between 2018 and 2025.

  17. Tank Remote Repair System Conceptual Design

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kriikku, E.

    2002-12-06

    This document describes two conceptual designs for a Tank Remote Repair System to perform leak site repairs of double shell waste tank walls (Types I, II, III, and IIIA) from the annulus space. The first concept uses a magnetic wall crawler and an epoxy patch system and the second concept uses a magnetic wall crawler and a magnetic patch system. The recommended concept uses the magnetic patch system, since it is simpler to deliver, easier to apply, and has a higher probability of stopping an active leak.

  18. Space Shuttle external tank: Today - DDT & E: Tomorrow - Production

    NASA Technical Reports Server (NTRS)

    Norton, A. M.; Tanner, E. J.

    1979-01-01

    The External Tank (ET) is the structural backbone of the Space Shuttle. The ET is discussed relative to its role; its design as a highly efficient Shuttle element; the liquid oxygen tank - a thin shelled monocoque; the intertank - the forward structural connection; the liquid hydrogen tank structure - the connection with the Orbiter; the ET structural verification; the propulsion system - a variety of functions; the electrical subsystem; electrical subsystem qualification; the thermal protection system; and other related problems. To date the qualification programs have been extremely successful and are almost complete, and the first flight tank has been delivered. Tomorrow's objectives will concentrate on establishing the facilities, tools and processes to achieve a production rate of 24 ETs/year.

  19. High level waste tank closure project: ALARA applications at the Idaho National Engineering and Environmental Laboratory.

    PubMed

    Aitken, Steven B; Butler, Richard; Butterworth, Steven W; Quigley, Keith D

    2005-05-01

    Bechtel BWXT Idaho, Maintenance and Operating Contractor for the Department of Energy at the Idaho National Engineering and Environmental Laboratory, has emptied, cleaned, and sampled six of the eleven 1.135 x 10(6) L high level waste underground storage tanks at the Idaho Nuclear Technology and Engineering Center, well ahead of the State of Idaho Consent Order cleaning schedule. Cleaning of a seventh tank is expected to be complete by the end of calendar year 2004. The tanks, with associated vaults, valve boxes, and distribution systems, are being closed to meet Resource Conservation and Recovery Act regulations and Department of Energy orders. The use of remotely operated equipment placed in the tanks through existing tank riser access points, sampling methods and application of as-low-as-reasonably-achievable (ALARA) principles have proven effective in keeping personnel dose low during equipment removal, tank, vault, and valve box cleaning, and sampling activities, currently at 0.03 Sv.

  20. Wetter for fine dry powder

    DOEpatents

    Hall, James E.; Williams, Everett H.

    1977-01-01

    A system for wetting fine dry powders such as bentonite clay with water or other liquids is described. The system includes a wetting tank for receiving water and a continuous flow of fine powder feed. The wetting tank has a generally square horizontal cross section with a bottom end closure in the shape of an inverted pyramid. Positioned centrally within the wetting tank is a flow control cylinder which is supported from the walls of the wetting tank by means of radially extending inclined baffles. A variable speed motor drives a first larger propeller positioned immediately below the flow control cylinder in a direction which forces liquid filling the tank to flow downward through the flow control cylinder and a second smaller propeller positioned below the larger propeller having a reverse pitch to oppose the flow of liquid being driven downward by the larger propeller.

  1. Charge radii of neutron-deficient Ca isotopes

    NASA Astrophysics Data System (ADS)

    Miller, A. J.; Minamisono, K.; Klose, A.; Everett, N.; Kalman, C.; Powel, R. C.; Watkins, J.; Garand, D.; Sumithrarachchi, C.; Krämer, J.; Maa, B.; Nörtershäuser, W.; Rossi, D. M.; Kujawa, C.; Pineda, S.; Lantis, J.; Liu, Y.; Mantica, P. F.; Pearson, M. R.

    2017-09-01

    Nucleon shell closures are generally associated with a local minimum in mean-square charge radii, 〈r2 〉 , along an isotopic chain. The 〈r2 〉 of 18Ar and 19K isotopes, however, do not show this signature at the N = 20 neutron shell closure. To gain a microscopic understanding of this abnormal behavior, measurements of 〈r2 〉 of neutron-deficient Ca isotopes below N = 20 have been proposed at the BEam COoling and LAser spectroscopy (BECOLA) facility at NSCL/MSU. Preliminary results will be presented and the deduced charge radii will be compared to theoretical calculations and the trends in the nearby isotopic chains. Work supported in part by NSF Grant PHY-15-65546, U.S. DOE Grant DE-NA0002924 and by the Deutsche Forschungsgemeinschaft through Grant SFB 1245.

  2. Design and Development of Lightweight Composite Tanks for the Mars Ascent Propulsion Technology

    NASA Technical Reports Server (NTRS)

    Estrada, Hector

    1999-01-01

    The investigation presented here focuses on the design and development of lightweight composite tanks for the Mars ascent propulsion technology. The proposed tanks are fabricated using the filament winding technique. The tanks will be used in the experimental permeability characterization of composite pressure vessels pressurized using cryogenic and kerosene fluids. We considered the geometry and composite material tailorability in the preliminary design formulation to obtain an isotensoid tank. The design formulation is based on membrane shell analysis. The tanks also include circular openings at the apex of the end caps for the installation of polar bosses. The development of a polar boss system was also investigated, and led to an innovative polar boss system that applies a uniform pressure on the o-ring gaskets. The permeability of these tanks was also considered and recommendations for improvement are presented.

  3. Tank Waste Retrieval Lessons Learned at the Hanford Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dodd, R.A.

    One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the U. S. Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60 percent of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons ofmore » this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste to the surrounding soil. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring this waste to the DST system. Retrieval of SST salt-cake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. Regulatory requirements for SST waste retrieval and tank farm closure are established in the Hanford Federal Facility Agreement and Consent Order (HFFACO), better known as the Tri- Party Agreement, or TPA. The HFFACO was signed by the DOE, the State of Washington Department of Ecology (Ecology), and U.S. Environmental Protection Agency (EPA) and requires retrieval of as much waste as technically possible, with waste residues not to exceed 360 ft{sup 3} in 530,000 gallon or larger tanks; 30 ft{sup 3} in 55,000 gallon or smaller tanks; or the limit of waste retrieval technology, whichever is less. If residual waste volume requirements cannot be achieved, then HFFACO Appendix H provisions can be invoked to request Ecology and EPA approval of an exception to the waste retrieval criteria for a specific tank. Tank waste retrieval has been conducted at the Hanford Site over the last few decades using a method referred to as Past Practice Hydraulic Sluicing. Past Practice Hydraulic Sluicing employs large volumes of DST supernatant and water to dislodge, dissolve, mobilize, and retrieve tank waste. Concern over the leak integrity of SSTs resulted in the need for tank waste retrieval methods capable of using smaller volumes of liquid in a more controlled manner. Retrieval of SST waste in accordance with HFFACO requirements was initiated at the Hanford Site in April 2003. New and innovative tank waste retrieval methods that minimize and control the use of liquids are being implemented for the first time. These tank waste retrieval methods replace Past Practice Hydraulic Sluicing and employ modified sluicing, vacuum retrieval, and in-tank vehicle techniques. Waste retrieval has been completed in seven Hanford Site SSTs (C-106, C-103, C-201, C-202, C-203, C-204, and S-112) in accordance with HFFACO requirements. Three additional tanks are currently in the process of being retrieved (C-108, C-109 and S-102) Preparation for retrieval of two additional SSTs (C-104 and C-110) is ongoing with retrieval operations forecasted to start in calendar year 2008. Tank C-106 was retrieved to a residual waste volume of 470 ft{sup 3} using oxalic acid dissolution and modified sluicing. An Appendix H exception request for Tank C-106 is undergoing review. Tank C-103 was retrieved to a residual volume of 351 ft{sup 3} using a modified sluicing technology. This approach was successful at reaching the TPA limits for this tank of less than 360 ft{sup 3}and the limits of the technology. Tanks C-201, C-202, C-203, and C-204 are smaller (55,000 gallon) tanks and waste removal was completed in accordance with HFFACO requirements using a vacuum retrieval system. Residual waste volumes in each of these four tanks were less than 25 ft{sup 3}. Tank S-112 retrieval was completed February 28, 2007, meeting the TPA Limits of less than 360 cu ft using salt-cake dissolution, modified sluicing, in-tank vehicle with high pressure water spray and caustic dissolution. Tanks C-108 and C-109 have been retrieved to 90% and 85% respectively. Modified sluicing was no longer effective at retrieving the remaining 5,000 to 10,000 gallons of residual. A Mobile Retrieval Tool (FoldTrac) is scheduled for installation early in 2008 to assist in breaking up chunks of waste and mobilizing the waste for transfer. Lessons learned from application of new tank waste retrieval methods are being documented and incorporated into future retrieval operations. They address all phases of retrieval including process design, equipment procurement and installation, supporting documentation, and system operations. Information is obtained through interviews with retrieval project personnel, focused workshops, review of problem evaluation requests, and evaluation of retrieval performance data. This paper presents current retrieval successes and lessons learned from retrieval of tank waste at the Hanford Site and discusses how this information is used to optimize retrieval system efficiency, improve overall cost effectiveness of retrieval operations, and ensure that HFFACO requirements are met. (authors)« less

  4. DEVELOPMENT AND DEPLOYMENT OF THE MOBILE ARM RETRIEVAL SYSTEM (MARS) - 12187

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BURKE CA; LANDON MR; HANSON CE

    Washington River Protection Solutions (WRPS) is developing and deploying Mobile Arm Retrieval System (MARS) technologies solutions to support retrieval of radioactive and chemical waste from underground single shell storage tanks (SST) located at the Hanford Site, which is near Richland, Washington. WRPS has developed the MARS using a standardized platform that is capable of deploying multiple retrieval technologies. To date, WRPS, working with their mentor-protege company, Columbia Energy and Environmental Services (CEES), has developed two retrieval mechanisms, MARS-Sluicing (MARS-S) and MARS-Vacuum (MARS-V). MARS-S uses pressurized fluids routed through spray nozzles to mobilize waste materials to a centrally located slurry pumpmore » (deployed in 2011). MARS-V uses pressurized fluids routed through an eductor nozzle. The eductor nozzle allows a vacuum to be drawn on the waste materials. The vacuum allows the waste materials to be moved to an in-tank vessel, then extracted from the SST and subsequently pumped to newer and safer double shell tanks (DST) for storage until the waste is treated for disposal. The MARS-S system is targeted for sound SSTs (i.e., non leaking tanks). The MARS-V is targeted for assumed leaking tanks or those tanks that are of questionable integrity. Both versions of MARS are beinglhave been developed in compliance with WRPS's TFC-PLN-90, Technology Development Management Plan [1]. TFC-PLN-90 includes a phased approach to design, testing, and ultimate deployment of new technologies. The MARS-V is scheduled to be deployed in tank 241-C-105 in late 2012.« less

  5. Development and Deployment of the Mobile Arm Retrieval System (MARS) - 12187

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Burke, Christopher A.; Landon, Matthew R.; Hanson, Carl E.

    Washington River Protection Solutions (WRPS) is developing and deploying Mobile Arm Retrieval System (MARS) technologies solutions to support retrieval of radioactive and chemical waste from underground single shell storage tanks (SST) located at the Hanford Site, which is near Richland, Washington. WRPS has developed the MARS using a standardized platform that is capable of deploying multiple retrieval technologies. To date, WRPS, working with their mentor-protege company, Columbia Energy and Environmental Services (CEES), has developed two retrieval mechanisms, MARS-Sluicing (MARS-S) and MARS-Vacuum (MARS-V). MARS-S uses pressurized fluids routed through spray nozzles to mobilize waste materials to a centrally located slurry pumpmore » (deployed in 2011). MARS-V uses pressurized fluids routed through an eductor nozzle. The eductor nozzle allows a vacuum to be drawn on the waste materials. The vacuum allows the waste materials to be moved to an in-tank vessel, then extracted from the SST and subsequently pumped to newer and safer double shell tanks (DST) for storage until the waste is treated for disposal. The MARS-S system is targeted for sound SSTs (i.e., non leaking tanks). The MARS-V is targeted for assumed leaking tanks or those tanks that are of questionable integrity. Both versions of MARS are being/have been developed in compliance with WRPS's TFC-PLN-90, Technology Development Management Plan [1]. TFC-PLN-90 includes a phased approach to design, testing, and ultimate deployment of new technologies. The MARS-V is scheduled to be deployed in tank 241-C-105 in late 2012. (authors)« less

  6. DEVELOPMENT AND DEPLOYMENT OF THE MOBILE ARM RETRIEVAL SYSTEM (MARS) - 12187

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BURKE CA; LANDON MR; HANSON CE

    Washington River Protection Solutions (WRPS) is developing and deploying Mobile Arm Retrieval System (MARS) technologies solutions to support retrieval of radioactive and chemical waste from underground single shell storage tanks (SST) located at the Hanford Site, which is near Richland, Washington. WRPS has developed the MARS using a standardized platform that is capable of deploying multiple retrieval technologies. To date, WRPS, working with their mentor-protege company, Columbia Energy and Environmental Services (CEES), has developed two retrieval mechanisms, MARS-Sluicing (MARS-S) and MARS-Vacuum (MARS-V). MARS-S uses pressurized fluids routed through spray nozzles to mobilize waste materials to a centrally located slurry pumpmore » (deployed in 2011). MARS-V uses pressurized fluids routed through an eductor nozzle. The eductor nozzle allows a vacuum to be drawn on the waste materials. The vacuum allows the waste materials to be moved to an in-tank vessel, then extracted from the SST and subsequently pumped to newer and safer double shell tanks (DST) for storage until the waste is treated for disposal. The MARS-S system is targeted for sound SSTs (i.e., non leaking tanks). The MARS-V is targeted for assumed leaking tanks or those tanks that are of questionable integrity. Both versions of MARS are being/have been developed in compliance with WRPS's TFC-PLN-90, Technology Development Management Plan. TFC-PLN-90 includes a phased approach to design, testing, and ultimate deployment of new technologies. The MARS-V is scheduled to be deployed in tank 241-C-105 in late 2012.« less

  7. ANNULUS CLOSURE TECHNOLOGY DEVELOPMENT INSPECTION/SALT DEPOSIT CLEANING MAGNETIC WALL CRAWLER

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Minichan, R; Russell Eibling, R; James Elder, J

    2008-06-01

    The Liquid Waste Technology Development organization is investigating technologies to support closure of radioactive waste tanks at the Savannah River Site (SRS). Tank closure includes removal of the wastes that have propagated to the tank annulus. Although amounts and types of residual waste materials in the annuli of SRS tanks vary, simple salt deposits are predominant on tanks with known leak sites. This task focused on developing and demonstrating a technology to inspect and spot clean salt deposits from the outer primary tank wall located in the annulus of an SRS Type I tank. The Robotics, Remote and Specialty Equipmentmore » (RRSE) and Materials Science and Technology (MS&T) Sections of the Savannah River National Laboratory (SRNL) collaborated to modify and equip a Force Institute magnetic wall crawler with the tools necessary to demonstrate the inspection and spot cleaning in a mock-up of a Type I tank annulus. A remote control camera arm and cleaning head were developed, fabricated and mounted on the crawler. The crawler was then tested and demonstrated on a salt simulant also developed in this task. The demonstration showed that the camera is capable of being deployed in all specified locations and provided the views needed for the planned inspection. It also showed that the salt simulant readily dissolves with water. The crawler features two different techniques for delivering water to dissolve the salt deposits. Both water spay nozzles were able to dissolve the simulated salt, one is more controllable and the other delivers a larger water volume. The cleaning head also includes a rotary brush to mechanically remove the simulated salt nodules in the event insoluble material is encountered. The rotary brush proved to be effective in removing the salt nodules, although some fine tuning may be required to achieve the best results. This report describes the design process for developing technology to add features to a commercial wall crawler and the results of the demonstration testing performed on the integrated system. The crawler was modified to address the two primary objectives of the task (inspection and spot cleaning). SRNL recommends this technology as a viable option for annulus inspection and salt removal in tanks with minimal salt deposits (such as Tanks 5 and 6.) This report further recommends that the technology be prepared for field deployment by: (1) developing an improved mounting system for the magnetic idler wheel, (2) improving the robustness of the cleaning tool mounting, (3) resolving the nozzle selection valve connections, (4) determining alternatives for the brush and bristle assembly, and (5) adding a protective housing around the motors to shield them from water splash. In addition, SRNL suggests further technology development to address annulus cleaning issues that are apparent on other tanks that will also require salt removal in the future such as: (1) Developing a duct drilling device to facilitate dissolving salt inside ventilation ducts and draining the solution out the bottom of the ducts. (2) Investigating technologies to inspect inside the vertical annulus ventilation duct.« less

  8. Deflection Analysis of the Space Shuttle External Tank Door Drive Mechanism

    NASA Technical Reports Server (NTRS)

    Tosto, Michael A.; Trieu, Bo C.; Evernden, Brent A.; Hope, Drew J.; Wong, Kenneth A.; Lindberg, Robert E.

    2008-01-01

    Upon observing an abnormal closure of the Space Shuttle s External Tank Doors (ETD), a dynamic model was created in MSC/ADAMS to conduct deflection analyses for assessing whether the Door Drive Mechanism (DDM) was subjected to excessive additional stress, and more importantly, to evaluate the magnitude of the induced step or gap with respect to shuttle s body tiles. To model the flexibility of the DDM, a lumped parameter approximation was used to capture the compliance of individual parts within the drive linkage. These stiffness approximations were then validated using FEA and iteratively updated in the model to converge on the actual distributed parameter equivalent stiffnesses. The goal of the analyses is to determine the deflections in the mechanism and whether or not the deflections are in the region of elastic or plastic deformation. Plastic deformation may affect proper closure of the ETD and would impact aero-heating during re-entry.

  9. Interplay of spherical closed shells and N /Z asymmetry in quasifission dynamics

    NASA Astrophysics Data System (ADS)

    Mohanto, G.; Hinde, D. J.; Banerjee, K.; Dasgupta, M.; Jeung, D. Y.; Simenel, C.; Simpson, E. C.; Wakhle, A.; Williams, E.; Carter, I. P.; Cook, K. J.; Luong, D. H.; Palshetkar, C. S.; Rafferty, D. C.

    2018-05-01

    Background: Quasifission (QF) has gained tremendous importance in heavy-ion nuclear physics research because of its strong influence on superheavy-element synthesis. Collisions involving closed-shell nuclei in the entrance channel are found to affect the QF reaction mechanism. Hence, it is important to improve the understanding of their effect on QF. Apart from that, some recent studies show that the difference in N /Z of reaction partners influences the reaction dynamics. Since heavier doubly magic nuclei have different N /Z than lighter doubly magic nuclei, it is important to understand the effect of N /Z mismatch as well as the effect of shell closures. Purpose: To investigate the effect of entrance-channel shell closures and N /Z asymmetry on QF. The reactions were chosen to decouple these effects from the contributions of other entrance-channel parameters. Method: Fission fragment mass-angle distributions were measured using the CUBE fission spectrometer, consisting of two large area position-sensitive multi-wire proportional counters (MWPCs), for five reactions, namely, 50Cr+208Pb , 52Cr+Pb,208206 , 54Cr+Pb,208204 . Result: Two components were observed in the measured fragment mass angle distribution, a fast mass-asymmetric quasifission and a slow mass-symmetric component having a less significant mass-angle correlation. The ratio of these components was found to depend on spherical closed shells in the entrance channel nuclei and the magnitude of the N /Z mismatch between the two reaction partners, as well as the beam energy. Conclusions: Entrance-channel spherical closed shells can enhance compound nucleus formation provided the N /Z asymmetry is small. Increase in the N /Z asymmetry is expected to destroy the effect of entrance-channel spherical closed shells, through nucleon transfer reactions.

  10. Sampling and analyses plan for tank 103 at the 219-S waste handling facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    FOWLER, K.D.

    1999-06-23

    This document describes the sampling and analysis activities associated with taking a Resource Conservation and Recovery Act (RCRA) protocol sample of the waste from Tank 103 at the 21 9-S Waste Handling Facility treatment storage, andlor disposal (TSD) unit at the 2224 Laboratory complex. This sampling and analyses is required based on negotiations between the State of Washington Department of Ecology (Ecology) and the Department of Energy, Richland Operations, (RL) in letters concerning the TPA Change Form M-32-98-01. In a letter from George H. Sanders, RL to Moses N. Jaraysi, Ecology, dated January 28,1999, it was noted that ''Prior tomore » the Tank 103 waste inventory transfer, a RCRA protocol sample of the waste will be obtained and tested for the constituents contained on the Part A, Form 3 Permit Application for the 219-S Waste Handling Facility.'' In the April 2, 1999 letter, from Brenda L. Becher-Khaleel, Ecology to James, E. Rasmussen, RL, and William O. Adair, FDH, Ecology states that the purpose of these analyses is to provide information and justification for leaving Tank 103 in an isolated condition in the 2194 TSD unit until facility closure. The data may also be used at some future date in making decisions regarding closure methodology for Tank 103. Ecology also notes that As Low As Reasonably Achievable (ALARA) concerns may force deviations from some SW-846 protocol. Every effort will be made to accommodate requirements as specified. Deviations from SW-846 will be documented in accordance with HASQARD.« less

  11. Corrective Action Decision Document for Corrective Action Unit 428: Area 3 Septic Waste Systems 1 and 5, Tonopah Test Range, Nevada

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    U.S. Department of Energy, Nevada Operations Office

    2000-02-08

    This Corrective Action Decision Document identifies and rationalizes the US Department of Energy, Nevada Operations Office's selection of a recommended corrective action alternative (CAA) appropriate to facilitate the closure of Corrective Action Unit (CAU) 428, Septic Waste Systems 1 and 5, under the Federal Facility Agreement and Consent Order. Located in Area 3 at the Tonopah Test Range (TTR) in Nevada, CAU 428 is comprised of two Corrective Action Sites (CASs): (1) CAS 03-05-002-SW01, Septic Waste System 1 and (2) CAS 03-05-002- SW05, Septic Waste System 5. A corrective action investigation performed in 1999 detected analyte concentrations that exceeded preliminarymore » action levels; specifically, contaminants of concern (COCs) included benzo(a) pyrene in a septic tank integrity sample associated with Septic Tank 33-1A of Septic Waste System 1, and arsenic in a soil sample associated with Septic Waste System 5. During this investigation, three Corrective Action Objectives (CAOs) were identified to prevent or mitigate exposure to contents of the septic tanks and distribution box, to subsurface soil containing COCs, and the spread of COCs beyond the CAU. Based on these CAOs, a review of existing data, future use, and current operations in Area 3 of the TTR, three CAAs were developed for consideration: Alternative 1 - No Further Action; Alternative 2 - Closure in Place with Administrative Controls; and Alternative 3 - Clean Closure by Excavation and Disposal. These alternatives were evaluated based on four general corrective action standards and five remedy selection decision factors. Based on the results of the evaluation, the preferred CAA was Alternative 3. This alternative meets all applicable state and federal regulations for closure of the site and will eliminate potential future exposure pathways to the contaminated soils at the Area 3 Septic Waste Systems 1 and 5.« less

  12. Tank waste remediation system retrieval and disposal mission readiness-to-proceed responses to internal independent assessment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Schaus, P.S.

    1998-01-06

    The US Department of Energy (DOE) is planning to make critical decisions during fiscal year (FY) 1998 regarding privatization contracts for the treatment of Hanford tank waste. Specifically, DOE, Richland Operations Office (RL), will make decisions related to proceeding with Phase 1 Privatization. In support of these decisions, the management and integration (M+I) contractor must be able to meet the requirements to support the Phase 1 privatization contractors. As part of the assessment of the Tank Waste Retrieval (TWR) Readiness-To-Proceed (RTP), an independent review of their process and products was required by the RL letter of August 8, 1997. Themore » Independent Review Team reviewed the adequacy of the planning that has been done by the M+I contractor to validate that, if the plans are carried out, there is reasonable assurance of success. Overall, the RTP Independent Review Team concluded that, if the planning by the M+I contractor team is carried out with adequate funding, there is reasonable assurance that the M+I contractor will be able to deliver waste to the privatization contractor for the duration of Phase 1. This conclusion was based on addressing the recommendations contained in the Independent Review Team`s Final Report and in the individual Criteria and Review Approach (CRA) forms completed during the assessment. The purpose of this report is to formally document the independent assessment and the RTP team responses to the Independent Review Team recommendations. It also provides closure logics for selected recommendations from a Lockheed Martin Hanford Corporation (LMHC) internal assessment of the Technical Basis Review (TBR) packages. This report contains the RTP recommendation closure process (Section 2.0); the closure tables (Section 3.0) which provide traceability between each review team recommendation and its corresponding Project Hanford Management Contract closure logic; and two attachments that formally document the Independent Review Team Final Report and the Internal Assessment Final Report.« less

  13. DOUBLE SHELL TANK (DST) HYDROXIDE DEPLETION MODEL FOR CARBON DIOXIDE ABSORPTION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    OGDEN DM; KIRCH NW

    2007-10-31

    This document generates a supernatant hydroxide ion depletion model based on mechanistic principles. The carbon dioxide absorption mechanistic model is developed in this report. The report also benchmarks the model against historical tank supernatant hydroxide data and vapor space carbon dioxide data. A comparison of the newly generated mechanistic model with previously applied empirical hydroxide depletion equations is also performed.

  14. Recharge

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fayer, Michael J.

    2008-01-17

    This chapter describes briefly the nature and measurement of recharge in support of the CH2M HILL Tank Farm Vadose Zone Project. Appendix C (Recharge) and the Recharge Data Package (Fayer and Keller 2007) provide a more thorough and extensive review of the recharge process and the estimation of recharge rates for the forthcoming RCRA Facility Investigation report for Hanford single-shell tank (SST) Waste Management Areas (WMAs).

  15. DOE Office of Scientific and Technical Information (OSTI.GOV)

    CALLAWAY WS; HUBER HJ

    Based on an ENRAF waste surface measurement taken February 1, 2009, double-shell tank (DST) 241-AN-106 (AN-106) contained approximately 278.98 inches (793 kgal) of waste. A zip cord measurement from the tank on February 1, 2009, indicated a settled solids layer of 91.7 inches in height (280 kgal). The supernatant layer in February 2009, by difference, was approximately 187 inches deep (514 kgal). Laboratory results from AN-106 February 1, 2009 (see Table 2) grab samples indicated the supernatant was below the chemistry limit that applied at the time as identified in HNF-SD-WM-TSR-006, Tank Farms Technical Safety Requirements, Administrative Control (AC) 5.16,more » 'Corrosion Mitigation Controls.' (The limits have since been removed from the Technical Safety Requirements (TSR) and are captured in OSD-T-151-00007, Operating Specifications for the Double-Shell Storage Tanks.) Problem evaluation request WRPS-PER-2009-0218 was submitted February 9, 2009, to document the finding that the supernatant chemistry for grab samples taken from the middle and upper regions of the supernatant was noncompliant with the chemistry control limits. The lab results for the samples taken from the bottom region of the supernatant met AC 5.16 limits.« less

  16. Project W-211 Initial Tank Retrieval Systems (ITRS) Description of Operations for 241-AZ-102

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BRIGGS, S.R.

    2000-02-25

    The primary purpose of the Initial Tank Retrieval Systems (ITRS) is to provide systems for retrieval of radioactive wastes stored in underground double-shell tanks (DSTs) for transfer to alternate storage, evaporation, pretreatment or treatment, while concurrently reducing risks associated with safety watch list and other DSTs. This Description of Operation (DOO) defines the control philosophy for the waste retrieval system for Tank 241-AZ-102 (AZ-102). This DOO provides a basis for the detailed design of the Project W-211 Retrieval Control System (RCS) for AZ-102 and also establishes test criteria for the RCS.

  17. Structure of neutron-rich nuclei around the N = 50 shell-gap closure

    NASA Astrophysics Data System (ADS)

    Faul, T.; Duchêne, G.; Thomas, J.-C.; Nowacki, F.; Huyse, M.; Van Duppen, P.

    2010-04-01

    The structure of neutron-rich nuclei in the vicinity of 78Ni have been investigated via the β-decay of 71,73,75Cu isotopes (ISOLDE, CERN). Experimental results have been compared with shell-model calculations performed with the ANTOINE code using a large (2p3/21f5/22p1/21g9/2) valence space and a 56/28Ni28 core.

  18. National Aerospace Plane Integrated Fuselage/Cryotank Risk Reduction program

    NASA Astrophysics Data System (ADS)

    Dayton, K. E.

    1993-06-01

    The principal objectives and results of the National Aerospace Plane (NASP) Integrated Risk Reduction program are briefly reviewed. The program demonstrated the feasibility of manufacturing lightweight advanced composite materials for single-stage-to-orbit hypersonic flight vehicle applications. A series of combined load simulation tests (thermal, mechanical, and cryogenic) demonstrated proof of concept performance for an all unlined composite cryogenic fuel tank with flat end bulkheads and a high-temperature thin-shell advanced composite fuselage. Temperatures of the fuselage were as high as 1300 F, with 100 percent bending and shear loads applied to the tank while filled with 850 gallons of cryogenic fluid hydrogen (-425 F). Leak rates measured on and around the cryotank shell and bulkheads were well below acceptable levels.

  19. B(E2)↑ Measurements for Radioactive Neutron-Rich Ge Isotopes: Reaching the N=50 Closed Shell

    NASA Astrophysics Data System (ADS)

    Padilla-Rodal, E.; Galindo-Uribarri, A.; Baktash, C.; Batchelder, J. C.; Beene, J. R.; Bijker, R.; Brown, B. A.; Castaños, O.; Fuentes, B.; del Campo, J. Gomez; Hausladen, P. A.; Larochelle, Y.; Lisetskiy, A. F.; Mueller, P. E.; Radford, D. C.; Stracener, D. W.; Urrego, J. P.; Varner, R. L.; Yu, C.-H.

    2005-03-01

    The B(E2;0+1→2+1) values for the radioactive neutron-rich germanium isotopes 78,80Ge and the closed neutron shell nucleus 82Ge were measured at the HRIBF using Coulomb excitation in inverse kinematics. These data allow a study of the systematic trend between the subshell closures at N=40 and 50. The B(E2) behavior approaching N=50 is similar to the trend observed for heavier isotopic chains. A comparison of the experimental results with a shell model calculation demonstrates persistence of the N=50 shell gap and a strong sensitivity of the B(E2) values to the effective interaction.

  20. Nonlinear Analysis of the Space Shuttle Superlightweight LO2 Tank. Part 2; Behavior Under 3g End-of-Flight Loads

    NASA Technical Reports Server (NTRS)

    Nemeth, Michael P.; Young, Richard D.; Collins, Timothy J.; Starnes, James H.,Jr.

    1998-01-01

    Results of linear bifurcation and nonlinear analyses of the Space Shuttle super lightweight (SLWT) external liquid-oxygen (LO2) tank are presented for an important end-of-flight loading condition. These results illustrate an important type of response mode for thin-walled shells, that are subjected to combined mechanical and thermal loads, that may be encountered in the design of other liquid-fuel launch vehicles. Linear bifurcation analyses are presented that predict several nearly equal eigenvalues that correspond to local buckling modes in the aft dome of the LO2 tank. In contrast, the nonlinear response phenomenon is shown to consist of a short-wavelength bending deformation in the aft elliptical dome of the LO2 tank that grows in amplitude in a stable manner with increasing load. Imperfection sensitivity analyses are presented that show that the presence of several nearly equal eigenvalues does not lead to a premature general instability mode for the aft dome. For the linear bifurcation and nonlinear analyses, the results show that accurate predictions of the response of the shell generally require a large-scale, high fidelity finite-element model. Results are also presented that show that the SLWT LO2 tank can support loads in excess of approximately 1.9 times the values of the operational loads considered.

  1. Solar hot water system installed at Day's Inn Motel, Dallas, Texas (Valley View)

    NASA Technical Reports Server (NTRS)

    1980-01-01

    The solar system was designed to provide 65 percent of the total domestic hot water (DHW) demand. A liquid (water) flat plate collector (1,000 square feet) system automatically drains into the 1,000 gallon steel storage tank when the solar pump is not running. Heat is transferred from the DHW tanks through a shell and tube heat exchanger. A circulating pump between the DHW tanks and heat exchanger enables solar heated water to help make up standby losses. All pumps are controlled by differential temperature controllers.

  2. Analytical test results for archived core composite samples from tanks 241-TY-101 and 241-TY-103

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Beck, M.A.

    1993-07-16

    This report describes the analytical tests performed on archived core composite samples form a 1.085 sampling of the 241-TY-101 (101-TY) and 241-TY-103 (103-TY) single shell waste tanks. Both tanks are suspected of containing quantities of ferrocyanide compounds, as a result of process activities in the late 1950`s. Although limited quantities of the composite samples remained, attempts were made to obtain as much analytical information as possible, especially regarding the chemical and thermal properties of the material.

  3. Solar hot water system installed at Days Inn Motel, Jacksonville, Florida

    NASA Technical Reports Server (NTRS)

    1980-01-01

    The solar system was designed to provide 65 percent of the hot water demand. Water in the liquid flat plate collector (900 square feet) system automatically drains into the 1000 gallon lined and vented steel storage tank when the pump is not running. Heat is transferred from storage to Domestic Hot Water (DHW) tanks through a tube and shell heat exchanger. A circulating pump between the DHW tanks and heat exchanger enables solar heated water to help make up DHW standby losses. All pumps are controlled by differential temperature.

  4. Glass shell manufacturing in space

    NASA Technical Reports Server (NTRS)

    Downs, R. L.; Ebner, M. A.; Nolen, R. L., Jr.

    1981-01-01

    Highly-uniform, hollow glass spheres (shells), which are used for inertial confinement fusion targets, were formed from metal-organic gel powder feedstock in a vertical furnace. As a result of the rapid pyrolysis caused by the furnace, the gel is transformed to a shell in five distinct stages: (a) surface closure of the porous gel; (b) generation of a closed-cell foam structure in the gel; (c) spheridization of the gel and further expansion of the foam; (d) coalescence of the closed-cell foam to a single-void shell; and (e) fining of the glass shell. The heat transfer from the furnace to the falling gel particle was modeled to determine the effective heating rate of the gel. The model predicts the temperature history for a particle as a function of mass, dimensions, specific heat, and absorptance as well as furnace temperature profile and thermal conductivity of the furnace gas. A model was developed that predicts the gravity-induced degradation of shell concentricity in falling molten shells as a function of shell characteristics and time.

  5. Repository of not readily available documents for project W-320

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Conner, J.C.

    1997-04-18

    The purpose of this document is to provide a readily available source of the technical reports needed for the development of the safety documentation provided for the waste retrieval sluicing system (WRSS), designed to remove the radioactive and chemical sludge from tank 241-C-106, and transport that material to double-shell tank 241-AY-102 via a new, temporary, shielded, encased transfer line.

  6. 40 CFR 271.12 - Requirements for hazardous waste management facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... and 266. These standards shall include: (a) Technical standards for tanks, containers, waste piles...-closure monitoring and maintenance; (e) Groundwater monitoring; (f) Security to prevent unauthorized access to the facility; (g) Facility personnel training; (h) Inspections, monitoring, recordkeeping, and...

  7. 40 CFR 271.12 - Requirements for hazardous waste management facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... and 266. These standards shall include: (a) Technical standards for tanks, containers, waste piles...-closure monitoring and maintenance; (e) Groundwater monitoring; (f) Security to prevent unauthorized access to the facility; (g) Facility personnel training; (h) Inspections, monitoring, recordkeeping, and...

  8. 40 CFR 271.12 - Requirements for hazardous waste management facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... and 266. These standards shall include: (a) Technical standards for tanks, containers, waste piles...-closure monitoring and maintenance; (e) Groundwater monitoring; (f) Security to prevent unauthorized access to the facility; (g) Facility personnel training; (h) Inspections, monitoring, recordkeeping, and...

  9. 40 CFR 271.12 - Requirements for hazardous waste management facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... and 266. These standards shall include: (a) Technical standards for tanks, containers, waste piles...-closure monitoring and maintenance; (e) Groundwater monitoring; (f) Security to prevent unauthorized access to the facility; (g) Facility personnel training; (h) Inspections, monitoring, recordkeeping, and...

  10. 40 CFR 271.12 - Requirements for hazardous waste management facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... and 266. These standards shall include: (a) Technical standards for tanks, containers, waste piles...-closure monitoring and maintenance; (e) Groundwater monitoring; (f) Security to prevent unauthorized access to the facility; (g) Facility personnel training; (h) Inspections, monitoring, recordkeeping, and...

  11. AN EVALUATION OF HANFORD SITE TANK FARM SUBSURFACE CONTAMINATION FY2007

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    MANN, F.M.

    2007-07-10

    The Tank Farm Vadose Zone (TFVZ) Project conducts activities to characterize and analyze the long-term environmental and human health impacts from tank waste releases to the vadose zone. The project also implements interim measures to mitigate impacts, and plans the remediation of waste releases from tank farms and associated facilities. The scope of this document is to report data needs that are important to estimating long-term human health and environmental risks. The scope does not include technologies needed to remediate contaminated soils and facilities, technologies needed to close tank farms, or management and regulatory decisions that will impact remediation andmore » closure. This document is an update of ''A Summary and Evaluation of Hanford Site Tank Farm Subsurface Contamination''. That 1998 document summarized knowledge of subsurface contamination beneath the tank farms at the time. It included a preliminary conceptual model for migration of tank wastes through the vadose zone and an assessment of data and analysis gaps needed to update the conceptual model. This document provides a status of the data and analysis gaps previously defined and discussion of the gaps and needs that currently exist to support the stated mission of the TFVZ Project. The first data-gaps document provided the basis for TFVZ Project activities over the previous eight years. Fourteen of the nineteen knowledge gaps identified in the previous document have been investigated to the point that the project defines the current status as acceptable. In the process of filling these gaps, significant accomplishments were made in field work and characterization, laboratory investigations, modeling, and implementation of interim measures. The current data gaps are organized in groups that reflect Components of the tank farm vadose zone conceptual model: inventory, release, recharge, geohydrology, geochemistry, and modeling. The inventory and release components address residual wastes that will remain in the tanks and tank-farm infrastructure after closure and potential losses from leaks during waste retrieval. Recharge addresses the impacts of current conditions in the tank farms (i.e. gravel covers that affect infiltration and recharge) as well as the impacts of surface barriers. The geohydrology and geochemistry components address the extent of the existing subsurface contaminant inventory and drivers and pathways for contaminants to be transported through the vadose zone and groundwater. Geochemistry addresses the mobility of key reactive contaminants such as uranium. Modeling addresses conceptual models and how they are simulated in computers. The data gaps will be used to provide input to planning (including the upcoming C Farm Data Quality Objective meetings scheduled this year).« less

  12. Installation restoration program. Closure assessment report for UST removals at sites 4 and 5 - petroleum, oils, and lubricants facility. Virginia Air National Guard, 192nd Fighter Group, Richmond International Airport, Sandston, Virginia. Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    The objectives of the closure assessment were to determine the extent of contaminated soil adjacent to the USTs requiring excavation, to provide documentation of soil and groundwater conditions following excavation, and to document closure activities in accordance with applicable VADEQ regulations. During closure activities, ASI provided technical support to the Base to ensure that the UST removal contractor (E K, Inc.) hereinafter referred to as the Contractor was in compliance with the technical requirements (as specified in the Plans and Specifications for Removal of Abandoned Underground Storage Tanks, Virginia Air National Guard, Richmond International Airport, Sandston, VA., dated July 1991more » and revised April 1992, and Addendum Numbers 1 through 7) of the contract. ASI was also responsible for collecting soil and/or groundwater closure samples from the excavations, and providing off-site fixed based laboratory analysis to verify clean conditions within the excavations.« less

  13. Riser Difference Uncertainty Methodology Based on Tank AY-101 Wall Thickness Measurements with Application to Tank AN-107

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Weier, Dennis R.; Anderson, Kevin K.; Berman, Herbert S.

    2005-03-10

    The DST Integrity Plan (RPP-7574, 2003, Double-Shell Tank Integrity Program Plan, Rev. 1A, CH2M HILL Hanford Group, Inc., Richland, Washington.) requires the ultrasonic wall thickness measurement of two vertical scans of the tank primary wall while using a single riser location. The resulting measurements are then used in extreme value methodology to predict the minimum wall thickness expected for the entire tank. The representativeness of using a single riser in this manner to draw conclusions about the entire circumference of a tank has been questioned. The only data available with which to address the representativeness question comes from Tank AY-101more » since only for that tank have multiple risers been used for such inspection. The purpose of this report is to (1) further characterize AY-101 riser differences (relative to prior work); (2) propose a methodology for incorporating a ''riser difference'' uncertainty for subsequent tanks for which only a single riser is used, and (3) specifically apply the methodology to measurements made from a single riser in Tank AN-107.« less

  14. Effects of Shell-Buckling Knockdown Factors in Large Cylindrical Shells

    NASA Technical Reports Server (NTRS)

    Hrinda, Glenn A.

    2012-01-01

    Shell-buckling knockdown factors (SBKF) have been used in large cylindrical shell structures to account for uncertainty in buckling loads. As the diameter of the cylinder increases, achieving the manufacturing tolerances becomes increasingly more difficult. Knockdown factors account for manufacturing imperfections in the shell geometry by decreasing the allowable buckling load of the cylinder. In this paper, large-diameter (33 ft) cylinders are investigated by using various SBKF's. An investigation that is based on finite-element analysis (FEA) is used to develop design sensitivity relationships. Different manufacturing imperfections are modeled into a perfect cylinder to investigate the effects of these imperfections on buckling. The analysis results may be applicable to large- diameter rockets, cylindrical tower structures, bulk storage tanks, and silos.

  15. Large-Scale Liquid Hydrogen Tank Rapid Chill and Fill Testing for the Advanced Shuttle Upper Stage Concept

    NASA Technical Reports Server (NTRS)

    Flachbart, R. H.; Hedayat, A.; Holt, K. A.; Sims, J.; Johnson, E. F.; Hastings, L. J.; Lak, T.

    2013-01-01

    Cryogenic upper stages in the Space Shuttle program were prohibited primarily due to a safety risk of a 'return to launch site' abort. An upper stage concept addressed this concern by proposing that the stage be launched empty and filled using shuttle external tank residuals after the atmospheric pressure could no longer sustain an explosion. However, only about 5 minutes was allowed for tank fill. Liquid hydrogen testing was conducted within a near-ambient environment using the multipurpose hydrogen test bed 638.5 ft3 (18m3) cylindrical tank with a spray bar mounted longitudinally inside. Although the tank was filled within 5 minutes, chilldown of the tank structure was incomplete, and excessive tank pressures occurred upon vent valve closure. Elevated tank wall temperatures below the liquid level were clearly characteristic of film boiling. The test results have substantial implications for on-orbit cryogen transfer since the formation of a vapor film would be much less inhibited due to the reduced gravity. However, the heavy tank walls could become an asset in normal gravity testing for on-orbit transfer, i.e., if film boiling in a nonflight weight tank can be inhibited in normal gravity, then analytical modeling anchored with the data could be applied to reduced gravity environments with increased confidence.

  16. Corrosion Management of the Hanford High-Level Nuclear Waste Tanks

    NASA Astrophysics Data System (ADS)

    Beavers, John A.; Sridhar, Narasi; Boomer, Kayle D.

    2014-03-01

    The Hanford site is located in southeastern Washington State and stores more than 200,000 m3 (55 million gallons) of high-level radioactive waste resulting from the production and processing of plutonium. The waste is stored in large carbon steel tanks that were constructed between 1943 and 1986. The leak and structurally integrity of the more recently constructed double-shell tanks must be maintained until the waste can be removed from the tanks and encapsulated in glass logs for final disposal in a repository. There are a number of corrosion-related threats to the waste tanks, including stress-corrosion cracking, pitting corrosion, and corrosion at the liquid-air interface and in the vapor space. This article summarizes the corrosion management program at Hanford to mitigate these threats.

  17. Behavioral Response of Hermit Crabs (Clibanarius digueti) to Dissolved Carbon Dioxide

    NASA Astrophysics Data System (ADS)

    Maier, H. J.

    2016-02-01

    CO2 induced ocean acidification is currently changing the population dynamics of marine organisms. This can involve increased stress in populations, and alteration in individual physiology, which can eventually be expressed through an organism's behavior. If sustained, CO2 induced ocean acidification has the potential to cause major impacts on marine food chains, including on services they provide. The purpose of this study was to understand whether and how ocean acidification affects the behavior of hermit crab Clibanarius digueti, a crustacean inhabiting the littoral zone. We hypothesized that an increase in dissolved carbonic acid would modify grazing and individual movement, because an increase in acidification alters the normal chemical composition of the water and potentially the physiology of C. digueti. A model tidal pool experiment consisting of two tanks (control and treatment) inhabited with seven living C. digueti was set up in the Ocean Biome of Biosphere-2. Each tank was also provided with uninhabited shells: two Turbo fluctuosa and four Cerithium sp. Gaseous CO2 was dissolved into the treatment tank and measured as dissolved CO2 by using a NaOH titration method. Additionally, water conditions were characterized for light and temperature. Two trials were run in this experiment with tanks and treatments interchanged in each trial. We found a marked treatment effect on C. digueti behavior. The population experiencing increased CO2 performed daily shell changes after first day of exposure for each of the 4-day trials, as compared to individuals unexposed to dissolved CO2, that experienced no shell changes. From this study we conclude that the behavior of C. Digueti can be a good indicator of changes in dissolved CO2. This would allow us to better interpret patterns in marine animal behavior in response to climate change.

  18. Behavioral Response of Hermit Crabs (Clibanarius digueti) to Dissolved Carbon Dioxide

    NASA Astrophysics Data System (ADS)

    Maier, H. J.

    2015-12-01

    CO2 induced ocean acidification is currently changing the population dynamics of marine organisms. As a result of ocean acidification, marine organisms expend extra energy on modifying behaviors. The current rate of ocean acidification will deplete the marine food chain that much of the world relies on as their major food supply. The purpose of this study was to understand whether and how ocean acidification affects the behavior of hermit crabs Clibanarius digueti. We hypothesized that an increase in carbonic acid would modify grazing and individual movement, because an increase in acidification alters the normal chemical composition of the water and potentially the niche occupancy of C. digueti. A model tidal pool experiment consisting of two tanks (control and treatment) inhabited with seven living C. digueti was set up in the Ocean Biome of Biosphere-2. Each tank was also provided with uninhabited shells: two Turbo fluctuosa and four Cerithium sp. Gaseous CO2 was dissolved into a treatment tank and measured as dissolved CO2 by using a sodium hydroxide titration method. Additionally, water conditions were characterized for UV- light and temperature. Two trials were run in this experiment with tanks and treatments interchanged in each trial. We assessed whether increased CO2 affected hermit crab shell change rate. We found that shell changes only happened among C. digueti placed under increased CO2. The information from this analysis will allow us to assess whether ocean acidification affects basic behavior in hermit crabs, which could later affect population dynamics. Bringing together all of this information will allow us to measure the effects of climate change on the behavior of C.Digueti.

  19. Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rosenberger, Kent H.

    2013-07-01

    The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of Southmore » Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling input parameters associated with the modeled features, both initial values (at the time of facility closure) and degradation rates/values. During the development of the PA, evaluations are conducted to reflect not only the results associated with the best available information at the time but also to evaluate potential uncertainties and sensitivities associated with the modeled system. While the PA will reflect the modeled system results from the best available information, it will also identify areas for future work to reduce overall PA uncertainties moving forward. DOE requires a PA Maintenance Program such that work continues to reduce model uncertainties, thus bolstering confidence in PA results that support regulatory decisions. This maintenance work may include new Research and Development activities or modeling as informed by previous PA results and other new information that becomes available. As new information becomes available, it is evaluated against previous PAs and appropriate actions are taken to ensure continued confidence in the regulatory decisions. Therefore, the PA program is a continual process that is not just the development of a PA but seeks to incorporate new information to reduce overall model uncertainty and provide continuing confidence in regulatory decisions. (author)« less

  20. Characterization of the March 2017 tank 10 surface sample (combination of HTF-10-17-30 AND HTF-10-17-31) and variable depth sample (combination of HTF-10-17-32 and HTF-10-17-33)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reboul, S. H.

    Two surface samples (HTF-10-17-30 and HTF-10-17-31) and two variable depth samples (HTF-10-17-32 and HTF-10-17-33) were collected from SRS Tank 10 during March 2017 and submitted to SRNL for characterization. At SRNL, the two surface samples were combined in one container, the two variable depth samples (VDSs) were combined in another container, and then the two composite samples were each characterized by a series of physical, ionic, radiological, and elemental analysis methods. The surface sample composite was characterized primarily for Tank Farm corrosion control purposes, while the VDS composite was characterized primarily for Tank Closure Cesium Removal (TCCR) purposes.

  1. Annual Report, Fall 2016: Alternative Chemical Cleaning of Radioactive High Level Waste Tanks - Corrosion Test Results

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wyrwas, R. B.

    The testing presented in this report is in support of the investigation of the Alternative Chemical Cleaning program to aid in developing strategies and technologies to chemically clean radioactive High Level Waste tanks prior to tank closure. The data and conclusions presented here were the examination of the corrosion rates of A285 carbon steel and 304L stainless steel exposed to two proposed chemical cleaning solutions: acidic permanganate (0.18 M nitric acid and 0.05M sodium permanganate) and caustic permanganate. (10 M sodium hydroxide and 0.05M sodium permanganate). These solutions have been proposed as a chemical cleaning solution for the retrieval ofmore » actinides in the sludge in the waste tanks, and were tested with both HM and PUREX sludge simulants at a 20:1 ratio.« less

  2. Effects of full-stream carbon filtration on the development of head and lateral line erosion syndrome (HLLES) in ocean surgeon.

    PubMed

    Stamper, M Andrew; Kittell, Michele M; Patel, Erin E; Corwin, Allison L

    2011-09-01

    Head and lateral line erosion syndrome (HLLES) is a common but very poorly understood disease of marine aquarium fish. One suspected etiology is the use of granulated activated carbon (GAC) to filter the water. Seventy-two ocean surgeons Acanthurus bahianus were distributed among three carbon-negative control systems and three GAC-treated systems such that each tank contained approximately the same total body mass. Each replicate system was made up of two 250-L circular tanks with a common filtration system (6 fish per tank, 12 fish per replicate system). The GAC-treated tanks were exposed to full-stream, extruded coconut shell activated carbon, which produced a mean total organic carbon content of 0.4 mg/L. The results of this study indicate that extruded coconut shell activated carbon filtering at full-stream rates can cause HLLES-type lesions in ocean surgeons. The HLLES developed exponentially over 15 d, beginning in the chin region. This was followed by pitting in the cheek region, which expanded until erosions coalesced. Once the carbon was discontinued, the processes reversed in a mean time of 49 d. As the lesions healed, they reverted from the coalesced to the pitted stage and then darkened before returning to normal.

  3. Ground-state properties of neutron magic nuclei

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Saxena, G., E-mail: gauravphy@gmail.com; Kaushik, M.

    2017-03-15

    A systematic study of the ground-state properties of the entire chains of even–even neutron magic nuclei represented by isotones of traditional neutron magic numbers N = 8, 20, 40, 50, 82, and 126 has been carried out using relativistic mean-field plus Bardeen–Cooper–Schrieffer approach. Our present investigation includes deformation, binding energy, two-proton separation energy, single-particle energy, rms radii along with proton and neutron density profiles, etc. Several of these results are compared with the results calculated using nonrelativistic approach (Skyrme–Hartree–Fock method) along with available experimental data and indeed they are found with excellent agreement. In addition, the possible locations of themore » proton and neutron drip-lines, the (Z, N) values for the new shell closures, disappearance of traditional shell closures as suggested by the detailed analyzes of results are also discussed in detail.« less

  4. Evidence for the Role of Proton Shell Closure in Quasifission Reactions from X-Ray Fluorescence of Mass-Identified Fragments

    NASA Astrophysics Data System (ADS)

    Morjean, M.; Hinde, D. J.; Simenel, C.; Jeung, D. Y.; Airiau, M.; Cook, K. J.; Dasgupta, M.; Drouart, A.; Jacquet, D.; Kalkal, S.; Palshetkar, C. S.; Prasad, E.; Rafferty, D.; Simpson, E. C.; Tassan-Got, L.; Vo-Phuoc, K.; Williams, E.

    2017-12-01

    The atomic numbers and the masses of fragments formed in quasifission reactions are simultaneously measured at scission in 48Ti + 238U reactions at a laboratory energy of 286 MeV. The atomic numbers are determined from measured characteristic fluorescence x rays, whereas the masses are obtained from the emission angles and times of flight of the two emerging fragments. For the first time, thanks to this full identification of the quasifission fragments on a broad angular range, the important role of the proton shell closure at Z =82 is evidenced by the associated maximum production yield, a maximum predicted by time-dependent Hartree-Fock calculations. This new experimental approach gives now access to precise studies of the time dependence of the N /Z (neutron over proton ratios of the fragments) evolution in quasifission reactions.

  5. Inadvertent Intruder Calculatios for F Tank Farm

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Koffman, L

    2005-09-12

    Savannah River National Laboratory (SRNL) has been providing radiological performance assessment analysis for Savannah River Site (SRS) solid waste disposal facilities (McDowell-Boyer 2000). The performance assessment considers numerous potential exposure pathways that could occur in the future. One set of exposure scenarios, known as inadvertent intruder analysis, considers the impact on hypothetical individuals who are assumed to inadvertently intrude onto the waste disposal site. An Automated Intruder Analysis application was developed by SRNL (Koffman 2004) that simplifies the inadvertent intruder analysis into a routine, automated calculation. Based on SRNL's experience, personnel from Planning Integration & Technology of Closure Business Unitmore » asked SRNL to assist with inadvertent intruder calculations for F Tank Farm to support the development of the Tank Closure Waste Determination Document. Meetings were held to discuss the scenarios to be calculated and the assumptions to be used in the calculations. As a result of the meetings, SRNL was asked to perform four scenario calculations. Two of the scenarios are the same as those calculated by the Automated Intruder Analysis application and these can be calculated directly by providing appropriate inputs. The other two scenarios involve use of groundwater by the intruder and the Automated Intruder Analysis application was adapted to perform these calculations. The four calculations to be performed are: (1) A post-drilling scenario in which the drilling penetrates a transfer line. (2) A calculation of internal exposure due to drinking water from a well located near a waste tank. (3) A post-drilling calculation in which waste is introduced by irrigation of the garden with water from a well located near a waste tank. (4) A resident scenario where a house is built above transfer lines. Note that calculations 1 and 4 use sources from the waste inventory in the transfer line (given in Table 1) whereas calculations 2 and 3 use sources from groundwater beneath the waste tank (given in Appendix B). It is important to recognize that there are two different sources in the calculations. In these calculations, assumptions are made for parameter values. Three key parameters are the size of the garden, the amount of vegetables eaten, and the distance of the well from the waste tank. For these three parameters, different values are considered in the calculations to determine the impact of the change in these parameters. Another key parameter is the length of time of institutional control, which determines when an inadvertent intruder could first be exposed. The standard length of time for institutional control is 100 years from the time of closure. In this analysis, waste inventory values are used from year 2005 but tanks will not be closed until year 2020. Thus, the effective length of time of institutional control used in the calculations is 115 years from year 2005, which is taken to be time zero for radiological decay calculations. All calculations are carried out for a period of 10,000 years.« less

  6. A systematic study of superheavy nuclei for Z = 114 and beyond using the relativistic mean field approach

    NASA Astrophysics Data System (ADS)

    Patra, S. K.; Wu, Cheng-Li; Praharaj, C. R.; Gupta, Raj K.

    1999-05-01

    We have studied the structural properties of even-even, neutron deficient, Z = 114-126, superheavy nuclei in the mass region A ˜ 270-320, using an axially deformed relativistic mean field model. The calculations are performed with three parameter sets (NL1, TM1 and NL-SH), in order to see the dependence of the structural properties on the force used. The calculated ground state shapes are found to be parameter dependent. For some parameter sets, many of the nuclei are degenerate in their ground state configuration. Special attention is given to the investigation of the magic structures (spherical shell closures) in the superheavy region. We find that some known magic numbers are absent and new closed shells are predicted. Large shell gaps appear at Z = 80, 92, (114), 120 and 138, N = 138, (164), (172), 184, (198), (228) and 258, irrespective of the parameter sets used. The numbers in parenthesis are those which correspond to relatively smaller gaps. The existence of new magic numbers in the valley of superheavy elements is discussed. It is suggested that nuclei around Z = 114 and N = 164 ˜ 172 could be considered as candidates for the next search of superheavy nuclei. The existence of superheavy islands around Z = 120 and N = 172 or N = 184 double shell closure is also discussed.

  7. Simulation of Hanford Tank 241-C-106 Waste Release into Tank 241-Y-102

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    KP Recknagle; Y Onishi

    Waste stored in Hdord single-shell Tank 241-C-106 will be sluiced with a supernatant liquid from doubIe-shell Tank 241 -AY- 102 (AY-1 02) at the U.S. Department of Energy's Har@ord Site in Eastern Washington. The resulting slurry, containing up to 30 wtYo solids, will then be transferred to Tank AY-102. During the sluicing process, it is important to know the mass of the solids being transferred into AY- 102. One of the primary instruments used to measure solids transfer is an E+ densitometer located near the periphery of the tank at riser 15S. This study was undert.dcen to assess how wellmore » a densitometer measurement could represent the total mass of soiids transferred if a uniform lateral distribution was assumed. The study evaluated the C-1 06 slurry mixing and accumulation in Tank AY- 102 for the following five cases: Case 1: 3 wt'%0 slurry in 6.4-m AY-102 waste Case 2: 3 w-t% slurry in 4.3-m AY-102 waste Case 3: 30 wtYo slurry in 6.4-m AY-102 waste Case 4: 30 wt% slurry in 4.3-m AY-102 waste Case 5: 30 wt% slurry in 5. O-m AY-102 waste. The tirne-dependent, three-dimensional, TEMPEST computer code was used to simulate solid deposition and accumulation during the injection of the C-106 slurry into AY-102 through four injection nozzles. The TEMPEST computer code was applied previously to other Hanford tanks, AP-102, SY-102, AZ-101, SY-101, AY-102, and C-106, to model tank waste mixing with rotating pump jets, gas rollover events, waste transfer from one tank to another, and pump-out retrieval of the sluiced waste. The model results indicate that the solid depth accumulated at the densitometer is within 5% of the average depth accumulation. Thus the reading of the densitometer is expected to represent the total mass of the transferred solids reasonably well.« less

  8. Numerical analysis of the cylindrical rigidity of the vertical steel tank shell

    NASA Astrophysics Data System (ADS)

    Chirkov, Sergey; Tarasenko, Alexander; Chepur, Petr

    2017-10-01

    The paper deals with the study of rigidity of a vertical steel cylindrical tank and its structural elements with the development of inhomogeneous subsidence in ANSYS software complex. The limiting case is considered in this paper: a complete absence of a base sector that varies along an arc of a circle. The subsidence zone is modeled by the parameter n. A finite-element model of vertical 20000 m3 steel tank has been created, taking into account all structural elements of tank metal structures, including the support ring, beam frame and roof sheets. Various combinations of vertical steel tank loading are analyzed. For operational loads, the most unfavorable combination is considered. Calculations were performed for the filled and emptied tank. Values of the maximum possible deformations of the outer contour of the bottom are obtained with the development of inhomogeneous base subsidence for the given tank size. The obtained parameters of intrinsic rigidity (deformability) of vertical steel tank can be used in the development of new regulatory and technical documentation for tanks.

  9. Long-Term High-Level Defense-Waste technology

    NASA Astrophysics Data System (ADS)

    1982-07-01

    In the residual liquid solidification effort, the primary alternative studied is the wiped film evaporator approach to solidifying salt well pumped liquids and returning the molten material to single shell tanks for microwave final stabilization to a hard dry product. Both systems analysis and experimental work are proceeding to evaluate this approach. The primary alternative for in situ stabilization of in-tank wastes is microwave drying of wet salt cake and unpumped sludges. Experimental work was successfully conducted on a 1/12 scale tank containing wet synthetic salt cake. Related systems analysis of a full scale system was initiated.

  10. Development of deep drawn aluminum piston tanks

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Whitehead, J.C.; Bronder, R.L.; Kilgard, L.W.

    1990-06-08

    An aluminum piston tank has been developed for applications requiring lightweight, low cost, low pressure, positive-expulsion liquid storage. The 3 liter (183 in{sup 3}) vessel is made primarily from aluminum sheet, using production forming and joining operations. The development process relied mainly on pressurizing prototype parts and assemblies to failure, as the primary source of decision making information for driving the tank design toward its optimum minimum-mass configuration. Critical issues addressed by development testing included piston operation, strength of thin-walled formed shells, alloy choice, and joining the end cap to the seamless deep drawn can. 9 refs., 8 figs.

  11. Molten salt thermal energy storage subsystem for solar thermal central receiver plants

    NASA Astrophysics Data System (ADS)

    Wells, P. B.; Nassopoulos, G. P.

    1982-02-01

    The development of a low cost thermal energy storage subsystem for large solar plants is described. Molten nitrate salt is used as both the solar plant working fluid and the storage medium. The storage system consists of a specially designed hot tank to hold salt at a storage temperature of 839K (1050 deg F) and a separate carbon steel cold tank to hold the salt after its thermal energy has been extracted to generate steam. The hot tank is lined with insulating firebrick to reduce the shell temperature to 561K (550 deg F) so that a low cost carbon steel shell is used. The internal insulation is protected from the hot salt by a unique metal liner with orthogonal corrugations to allow for numerous cycles of thermal expansion and contraction. A preliminary design for a large commercial size plant (1200 MWh sub +), a laboratory test program for the critical components, and the design, construction, and test of a small scale (7 MWH sub t) research experiment at the Central Receiver Test Facility in Albuquerque, New Mexico is described.

  12. Modeling and Test Data Analysis of a Tank Rapid Chill and Fill System for the Advanced Shuttle Upper Stage (ASUS) Concept

    NASA Technical Reports Server (NTRS)

    Flachbart, Robin; Hedayat, Ali; Holt, Kimberly A.; Cruit, Wendy (Technical Monitor)

    2001-01-01

    The Advanced Shuttle Upper Stage (ASUS) concept addresses safety concerns associated .with cryogenic stages by launching empty, and filling on ascent. The ASUS employs a rapid chill and fill concept. A spray bar is used to completely chill the tank before fill, allowing the vent valve to be closed during the fill process. The first tests of this concept, using a flight size (not flight weight) tank. were conducted at Marshall Space Flight Center (MSFC) during the summer of 2000. The objectives of the testing were to: 1) demonstrate that a flight size tank could be filled in roughly 5 minutes to accommodate the shuttle ascent window, and 2) demonstrate a no-vent fill of the tank. A total of 12 tests were conducted. Models of the test facility fill and vent systems, as well as the tank, were constructed. The objective of achieving tank fill in 5 minutes was met during the test series. However, liquid began to accumulate in the tank before it was chilled. Since the tank was not chilled until the end of each test, vent valve closure during fill was not possible. Even though the chill and fill process did not occur as expected, reasonable model correlation with the test data was achieved.

  13. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nag, Somnath; Singh, A. K.; Hagemann, G. B.

    In this paper, high-spin states in 124Xe have been populated using the 80Se( 48Ca, 4n) reaction at a beam energy of 207 MeV and high-multiplicity, γ-ray coincidence events were measured using the Gammasphere spectrometer. Six high-spin rotational bands with moments of inertia similar to those observed in neighboring nuclei have been observed. The experimental results are compared with calculations within the framework of the Cranked Nilsson-Strutinsky model. Finally, it is suggested that the configurations of the bands involve excitations of protons across the Z = 50 shell gap coupled to neutrons within the N = 50 - 82 shell ormore » excited across the N = 82 shell closure.« less

  14. Alternative Chemical Cleaning Methods for High Level Waste Tanks: Simulant Studies

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rudisill, T.; King, W.; Hay, M.

    Solubility testing with simulated High Level Waste tank heel solids has been conducted in order to evaluate two alternative chemical cleaning technologies for the dissolution of sludge residuals remaining in the tanks after the exhaustion of mechanical cleaning and sludge washing efforts. Tests were conducted with non-radioactive pure phase metal reagents, binary mixtures of reagents, and a Savannah River Site PUREX heel simulant to determine the effectiveness of an optimized, dilute oxalic/nitric acid cleaning reagent and pure, dilute nitric acid toward dissolving the bulk non-radioactive waste components. A focus of this testing was on minimization of oxalic acid additions duringmore » tank cleaning. For comparison purposes, separate samples were also contacted with pure, concentrated oxalic acid which is the current baseline chemical cleaning reagent. In a separate study, solubility tests were conducted with radioactive tank heel simulants using acidic and caustic permanganate-based methods focused on the “targeted” dissolution of actinide species known to be drivers for Savannah River Site tank closure Performance Assessments. Permanganate-based cleaning methods were evaluated prior to and after oxalic acid contact.« less

  15. 49 CFR 178.275 - Specification for UN Portable Tanks intended for the transportation of liquid and solid hazardous...

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... external heat. Fusible elements must not be utilized on portable tanks with a test pressure which exceeds 2... conductance of the insulation, in kW m −2 K −1, at 38 °C (100 °F); and t = actual temperature of the hazardous... given in this paragraph (i)(2)(i)(A) for insulated shells may only be used if the insulation is in...

  16. 49 CFR 178.275 - Specification for UN Portable Tanks intended for the transportation of liquid and solid hazardous...

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... external heat. Fusible elements must not be utilized on portable tanks with a test pressure which exceeds 2... conductance of the insulation, in kW m −2 K −1, at 38 °C (100 °F); and t = actual temperature of the hazardous... given in this paragraph (i)(2)(i)(A) for insulated shells may only be used if the insulation is in...

  17. 49 CFR 178.275 - Specification for UN Portable Tanks intended for the transportation of liquid and solid hazardous...

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... external heat. Fusible elements must not be utilized on portable tanks with a test pressure which exceeds 2... conductance of the insulation, in kW m −2 K −1, at 38 °C (100 °F); and t = actual temperature of the hazardous... given in this paragraph (i)(2)(i)(A) for insulated shells may only be used if the insulation is in...

  18. 49 CFR 178.275 - Specification for UN Portable Tanks intended for the transportation of liquid and solid hazardous...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... external heat. Fusible elements must not be utilized on portable tanks with a test pressure which exceeds 2... conductance of the insulation, in kW m −2 K −1, at 38 °C (100 °F); and t = actual temperature of the hazardous... given in this paragraph (i)(2)(i)(A) for insulated shells may only be used if the insulation is in...

  19. 49 CFR 178.275 - Specification for UN Portable Tanks intended for the transportation of liquid and solid hazardous...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... external heat. Fusible elements must not be utilized on portable tanks with a test pressure which exceeds 2... conductance of the insulation, in kW m −2 K −1, at 38 °C (100 °F); and t = actual temperature of the hazardous... given in this paragraph (i)(2)(i)(A) for insulated shells may only be used if the insulation is in...

  20. Neutrinoless double-β decay of Se82 in the shell model: Beyond the closure approximation

    NASA Astrophysics Data System (ADS)

    Sen'kov, R. A.; Horoi, M.; Brown, B. A.

    2014-05-01

    We recently proposed a method [R. A. Senkov and M. Horoi, Phys. Rev. C 88, 064312 (2013), 10.1103/PhysRevC.88.064312] to calculate the standard nuclear matrix elements for neutrinoless double-β decay (0νββ) of Ca48 going beyond the closure approximation. Here we extend this analysis to the important case of Se82, which was chosen as the base isotope for the upcoming SuperNEMO experiment. We demonstrate that by using a mixed method that considers information from closure and nonclosure approaches, one can get excellent convergence properties for the nuclear matrix elements, which allows one to avoid unmanageable computational costs. We show that in contrast with the closure approximation the mixed approach has a very weak dependence on the average closure energy. The matrix elements for the heavy neutrino-exchange mechanism that could contribute to the 0νββ decay of Se82 are also presented.

  1. HANFORD DST THERMAL & SEISMIC PROJECT ANSYS BENCHMARK ANALYSIS OF SEISMIC INDUCED FLUID STRUCTURE INTERACTION IN A HANFORD DOUBLE SHELL PRIMARY TANK

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    MACKEY, T.C.

    M&D Professional Services, Inc. (M&D) is under subcontract to Pacific Northwest National Laboratories (PNNL) to perform seismic analysis of the Hanford Site Double-Shell Tanks (DSTs) in support of a project entitled ''Double-Shell Tank (DSV Integrity Project-DST Thermal and Seismic Analyses)''. The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST System at Hanford in support of Tri-Party Agreement Milestone M-48-14. The work described herein was performed in support of the seismic analysis of the DSTs. The thermal and operating loads analysis of the DSTs is documented in Rinker et al. (2004). Themore » overall seismic analysis of the DSTs is being performed with the general-purpose finite element code ANSYS. The overall model used for the seismic analysis of the DSTs includes the DST structure, the contained waste, and the surrounding soil. The seismic analysis of the DSTs must address the fluid-structure interaction behavior and sloshing response of the primary tank and contained liquid. ANSYS has demonstrated capabilities for structural analysis, but the capabilities and limitations of ANSYS to perform fluid-structure interaction are less well understood. The purpose of this study is to demonstrate the capabilities and investigate the limitations of ANSYS for performing a fluid-structure interaction analysis of the primary tank and contained waste. To this end, the ANSYS solutions are benchmarked against theoretical solutions appearing in BNL 1995, when such theoretical solutions exist. When theoretical solutions were not available, comparisons were made to theoretical solutions of similar problems and to the results from Dytran simulations. The capabilities and limitations of the finite element code Dytran for performing a fluid-structure interaction analysis of the primary tank and contained waste were explored in a parallel investigation (Abatt 2006). In conjunction with the results of the global ANSYS analysis reported in Carpenter et al. (2006), the results of the two investigations will be compared to help determine if a more refined sub-model of the primary tank is necessary to capture the important fluid-structure interaction effects in the tank and if so, how to best utilize a refined sub-model of the primary tank. Both rigid tank and flexible tank configurations were analyzed with ANSYS. The response parameters of interest are total hydrodynamic reaction forces, impulsive and convective mode frequencies, waste pressures, and slosh heights. To a limited extent: tank stresses are also reported. The results of this study demonstrate that the ANSYS model has the capability to adequately predict global responses such as frequencies and overall reaction forces. Thus, the model is suitable for predicting the global response of the tank and contained waste. On the other hand, while the ANSYS model is capable of adequately predicting waste pressures and primary tank stresses in a large portion of the waste tank, the model does not accurately capture the convective behavior of the waste near the free surface, nor did the model give accurate predictions of slosh heights. Based on the ability of the ANSYS benchmark model to accurately predict frequencies and global reaction forces and on the results presented in Abatt, et al. (2006), the global ANSYS model described in Carpenter et al. (2006) is sufficient for the seismic evaluation of all tank components except for local areas of the primary tank. Due to the limitations of the ANSYS model in predicting the convective response of the waste, the evaluation of primary tank stresses near the waste free surface should be supplemented by results from an ANSYS sub-model of the primary tank that incorporates pressures from theoretical solutions or from Dytran solutions. However, the primary tank is expected to have low demand to capacity ratios in the upper wall. Moreover, due to the less than desired mesh resolution in the primary tank knuckle of the global ANSYS model, the evaluation of the primary tank stresses in the lower knuckle should be supplemented by results from a more refined ANSYS sub-model of the primary tank that incorporates pressures from theoretical solutions or from Dytran solutions.« less

  2. Tank characterization report for double-shell tank 241-AW-105

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sasaki, L.M.

    1997-06-05

    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 double-shell tank 241-AW-105. The objectives of this report are to use characterization data in response to technical issues associated with tank 241-AW-105 waste; and to provide a standard characterization of this waste in terms of a best-basis inventorymore » 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 milestone Characterization. information presented in this report originated from sample analyses and known historical sources. While only the results of a recent sampling event 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-AW-105 is provided in Appendix A, including surveillance information, records pertaining to waste transfers and tank operations, and expected tank contents derived from a process knowledge model. The recent sampling event listed, as well as pertinent sample data obtained before 1996, are summarized in Appendix B along with the sampling results. The results of the 1996 grab sampling event satisfied the data requirements specified in the sampling and analysis plan (SAP) for this tank. In addition, the tank headspace flammability was measured, which addresses one of the requirements specified in the safety screening DQO. 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-AW-105 and its respective waste types is contained in Appendix E. A majority of the documents listed in Appendix E may be found in the Tank Characterization and Safety Resource Center.« less

  3. Analysis on influence of guide vanes closure laws of pump-turbine on load rejection transient process

    NASA Astrophysics Data System (ADS)

    Yao, Z.; Bi, H. L.; Huang, Q. S.; Li, Z. J.; Wang, Z. W.

    2013-12-01

    In load rejection transient process, the sudden shut down of guide vanes may cause units speed rise and a sharp increase in water hammer pressure of diversion system, which endangers the safety operation of the power plant. Adopting reasonable guide vane closure law is a kind of economic and effective measurement to reduce the water hammer pressure and limit rotational speed increases. In this paper, combined with Guangzhou Pumped Storage Power Station plant A, the load rejection condition under different guide vanes closure laws is calculated and the key factor of guide vanes closure laws on the impact of the load rejection transition process is analyzed. The different inflection points, which are the closure modes, on the impact of unit speed change, water level fluctuation of surge tank, and the pressure fluctuation of volute inlet and draft tube inlet are further discussed. By compared with the calculation results, a reasonable guide vanes inflection point position can be determined according to security requirements and a reasonable guide vanes closure law can be attained to effectively coordinate the unit speed rise and the rapid pressure change in the load rejection transient process.

  4. TANKS 18 AND 19-F STRUCTURAL FLOWABLE GROUT FILL MATERIAL EVALUATION AND RECOMMENDATIONS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stefanko, D.; Langton, C.

    2011-11-01

    Cementitious grout will be used to close Tanks 18-F and 19-F. The functions of the grout are to: (1) physically stabilize the final landfill by filling the empty volume in the tanks with a non compressible material; (2) provide a barrier for inadvertent intrusion into the tank; (3) reduce contaminant mobility by (a) limiting the hydraulic conductivity of the closed tank and (b) reducing contact between the residual waste and infiltrating water; and (4) providing an alkaline, chemically reducing environment in the closed tank to control speciation and solubility of selected radionuclides. The objective of this work was to identifymore » a single (all-in-one) grout to stabilize and isolate the residual radionuclides in the tank, provide structural stability of the closed tank and serve as an inadvertent intruder barrier. This work was requested by V. A. Chander, High Level Waste (HLW) Tank Engineering, in HLW-TTR-2011-008. The complete task scope is provided in the Task Technical and QA Plan, SRNL-RP-2011-00587 Revision 0. The specific objectives of this task were to: (1) Identify new admixtures and dosages for formulating a zero bleed flowable tank fill material selected by HLW Tank Closure Project personnel based on earlier tank fill studies performed in 2007. The chemical admixtures used for adjusting the flow properties needed to be updated because the original admixture products are no longer available. Also, the sources of cement and fly ash have changed, and Portland cements currently available contain up to 5 wt. % limestone (calcium carbonate). (2) Prepare and evaluate the placement, compressive strength, and thermal properties of the selected formulation with new admixture dosages. (3) Identify opportunities for improving the mix selected by HLW Closure Project personnel and prepare and evaluate two potentially improved zero bleed flowable fill design concepts; one based on the reactor fill grout and the other based on a shrinkage compensating flowable fill mix design. (4) Prepare samples for hydraulic property measurements for comparison to the values in the F and H- Tank Farm Performance Assessments (PAs). (5) Identify a grout mix for the Tanks 18-F and 19-F Grout Procurement Specification [Forty, 2011 a, b, c]. Results for two flowable zero bleed structural fill concepts containing 3/8 inch gravel (70070 Series and LP-8 Series) and a sand only mix (SO Series) are provided in this report. Tank Farm Engineering and SRNL Project Management selected the 70070 mix as the base case for inclusion in Revision 0 of the Tanks 18-F and 19-F grout procurement specification [Forty 2011 a] and requested admixture recommendations and property confirmation for this formulation [Forty, 2011 b]. Lower cementitious paste mixes were formulated because the 70070 mix is over designed with respect to strength and generates more heat from hydration reactions than is desirable for mass pour application. Work was also initiated on a modification of the recommended mix which included shrinkage compensation to mitigate fast pathways caused by shrinkage cracking and poor physical bonding to the tank and ancillary equipment. Testing of this option was postponed to FY12.« less

  5. Shell Model Far From Stability: Island of Inversion Mergers

    NASA Astrophysics Data System (ADS)

    Nowacki, F.; Poves, A.

    2018-02-01

    In this study we propose a common mechanism for the disappearance of shell closures far from stabilty. With the use of Large Scale Shell Model calculations (SM-CI), we predict that the region of deformation which comprises the heaviest Chromium and Iron isotopes at and beyond N=40 will merge with a new one at N=50 in an astonishing parallel to the N=20 and N=28 case in the Neon and Magnesium isotopes. We propose a valence space including the full pf-shell for the protons and the full sdg shell for the neutrons, which represents a come-back of the the harmonic oscillator shells in the very neutron rich regime. Our calculations preserve the doubly magic nature of the ground state of 78Ni, which, however, exhibits a well deformed prolate band at low excitation energy, providing a striking example of shape coexistence far from stability. This new Island of Inversion (IoI) adds to the four well documented ones at N=8, 20, 28 and 40.

  6. 40 CFR 280.73 - Applicability to previously closed UST systems.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.73 Applicability to previously closed UST systems. When directed by the implementing agency, the owner and operator of an UST system... systems. 280.73 Section 280.73 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...

  7. 40 CFR 280.73 - Applicability to previously closed UST systems.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.73 Applicability to previously closed UST systems. When directed by the implementing agency, the owner and operator of an UST system... systems. 280.73 Section 280.73 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...

  8. 40 CFR 280.73 - Applicability to previously closed UST systems.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.73 Applicability to previously closed UST systems. When directed by the implementing agency, the owner and operator of an UST system... systems. 280.73 Section 280.73 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...

  9. 40 CFR 280.73 - Applicability to previously closed UST systems.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.73 Applicability to previously closed UST systems. When directed by the implementing agency, the owner and operator of an UST system... systems. 280.73 Section 280.73 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...

  10. 40 CFR 280.73 - Applicability to previously closed UST systems.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... UNDERGROUND STORAGE TANKS (UST) Out-of-Service UST Systems and Closure § 280.73 Applicability to previously closed UST systems. When directed by the implementing agency, the owner and operator of an UST system... systems. 280.73 Section 280.73 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...

  11. 77 FR 74472 - Notice of Availability of the Final Tank Closure and Waste Management Environmental Impact...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-14

    ... Rooms Gonzaga University, Foley Center Library, 101-L East 502 Boone, Spokane, Washington 99258, (509) 313-5931. Portland State University, Government Information, Branford Price Millar Library, 1875 SW Park Avenue, Portland, Oregon 97201, (503) 725- 5874. University of Washington, Suzzallo-Allen Library...

  12. 75 FR 6018 - Environmental Management Site-Specific Advisory Board, Hanford

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-05

    ... in the Draft Tank Closure (TC) and Waste Management (WM) Environmental Impact Statement (EIS) Overview of the Draft TC and WM EIS findings by other stakeholder groups Discussion of HAB member comments on the TC and WM EIS Development of HAB advice principles Adjourn Public Participation: The meeting...

  13. 46 CFR 32.50-15 - Cargo piping on tank vessels constructed on or after July 1, 1951-TB/ALL.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ...) Except for the carriage of animal fats and vegetable oils, the system has a closure which forms a vapor... vegetable oils, the system has a metallic drop line which complies with 46 CFR 153.282. (3) Cargo piping...

  14. 46 CFR 32.50-15 - Cargo piping on tank vessels constructed on or after July 1, 1951-TB/ALL.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ...) Except for the carriage of animal fats and vegetable oils, the system has a closure which forms a vapor... vegetable oils, the system has a metallic drop line which complies with 46 CFR 153.282. (3) Cargo piping...

  15. The effect of enhanced carbon dioxide on the sinking and swimming of the shelled pteropod Limacina retroversa

    NASA Astrophysics Data System (ADS)

    Bergan, A. J.; Maas, A.; Lawson, G. L.

    2016-02-01

    Shelled pteropods (thecosomes) are planktonic mollusks that are expected to be negatively impacted by ocean acidification. The shells of live pteropods exposed to enhanced CO2 are known to exhibit degradation in condition, but the impacts on the fitness of the animals are unclear. Limacina retroversa from the Gulf of Maine were used to investigate the impact of enhanced CO2 on shell condition as well as swimming and sinking behaviors. L. retroversa were caught in the summer, fall, and spring and maintained in seawater at either ambient or two levels of enhanced CO2, and then filmed in a mirrored tank to measure the 3D velocities and other characteristics of the animals' movements while sinking or swimming. Shell condition was also examined by a suite of imaging techniques including light microscopy, SEM, and micro-computed tomography. After exposures to enhanced CO2 of as little as 3 days the pteropod shells became darker and more opaque. The pteropds had slower sinking velocities when kept under medium and high CO2 (800 and 1200 ppm) in comparison to the ambient ( 400 ppm) control group for exposure periods between one and four weeks. The swimming velocities of animals ascending in the tank were similarly decreased for animals maintained under the enhanced CO2 conditions for one to three weeks. The wing beat frequency and the path of motion were analyzed to further characterize swimming ability. Pteropods use both sinking and swimming as anti-predation techniques and hence the observed decrease in sinking and swimming speeds observed for animals exposed to increased CO2 could have a direct impact on their fitness by increasing their mortality risk to predators.

  16. 49 CFR 179.220-23 - Test of tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... must not be in place when the test is made. (b) The inner container must be pressure tested before... container after its installation within outer shell must have their attachment welds thoroughly inspected by...

  17. 49 CFR 178.274 - Specifications for UN portable tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... welding of pressure vessels. When the manufacturing process or the materials make it necessary, the shells... strength of the tubing, such as may happen when cutting threads. Brazed joints are not authorized for...

  18. 49 CFR 178.274 - Specifications for UN portable tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... welding of pressure vessels. When the manufacturing process or the materials make it necessary, the shells... strength of the tubing, such as may happen when cutting threads. Brazed joints are not authorized for...

  19. 1200008

    NASA Image and Video Library

    2012-01-18

    EXTERNAL TANK TEST ARTICLE (ETTA2) IS IN TRANSIT TO BE ROTATED 180° FOR INTERFACE RING INSTALLATION FOR SBKF (SHELL BUCKLING KNOCKDOWN FACTOR) CRITICAL FEEDBACK, UNDERSTANDING AND IDEAS THAT WILL ENABLE THE DEVELOPMENT AND IMPLEMENTATION OF NEW DESIGN APPROACHES AND TECHNOLOGY .

  20. River Protection Project (RPP) Dangerous Waste Training Plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    POHTO, R.E.

    2000-03-09

    This supporting document contains the training plan for dangerous waste management at River Protection Project TSD Units. This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by River Protection Project (RPP) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units managed by RPP are: the Double-Shell Tank (DST) System, 204-AR Waste Unloading Facility, Grout, and the Single-Shell Tank (SST) System. The program is designed in compliance with the requirements of Washington Administrative Code (WAC) 173-303-330 and Titlemore » 40 Code of Federal Regulations (CFR) 265.16 for the development of a written dangerous waste training program and the Hanford Facility Permit. Training requirements were determined by an assessment of employee duties and responsibilities. The RPP training program is designed to prepare employees to operate and maintain the Tank Farms in a safe, effective, efficient, and environmentally sound manner. In addition to preparing employees to operate and maintain the Tank Farms under normal conditions, the training program ensures that employees are prepared to respond in a prompt and effective manner should abnormal or emergency conditions occur. Emergency response training is consistent with emergency responses outlined in the following Building Emergency Plans: HNF-IP-0263-TF and HNF-=IP-0263-209E.« less

  1. Data Quality Objectives for Tank Farms Waste Compatibility Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BANNING, D.L.

    1999-07-02

    There are 177 waste storage tanks containing over 210,000 m{sup 3} (55 million gal) of mixed waste at the Hanford Site. The River Protection Project (RPP) has adopted the data quality objective (DQO) process used by the U.S. Environmental Protection Agency (EPA) (EPA 1994a) and implemented by RPP internal procedure (Banning 1999a) to identify the information and data needed to address safety issues. This DQO document is based on several documents that provide the technical basis for inputs and decision/action levels used to develop the decision rules that evaluate the transfer of wastes. A number of these documents are presentlymore » in the process of being revised. This document will need to be revised if there are changes to the technical criteria in these supporting documents. This DQO process supports various documents, such as sampling and analysis plans and double-shell tank (DST) waste analysis plans. This document identifies the type, quality, and quantity of data needed to determine whether transfer of supernatant can be performed safely. The requirements in this document are designed to prevent the mixing of incompatible waste as defined in Washington Administrative Code (WAC) 173-303-040. Waste transfers which meet the requirements contained in this document and the Double-Shell Tank Waste Analysis Plan (Mulkey 1998) are considered to be compatible, and prevent the mixing of incompatible waste.« less

  2. A 400,000 lb crude oil storage tank was moved on an 11 in. air blanket

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1979-03-01

    The British patented-system used to move the 55,000 bbl tank at the Cushing, Okla., tank farm of Getty Oil Co. uses the same airlift principle employed by various hovercraft. Representatives from 20 pipeline and oil companies watched the move, which placed the tank 22 ft higher and 600 ft away from its former location, to improve its gravity flow rate, an improvement spurred by greater crude demands placed on Cushing Terminal. Two 425 hp air compressors were attached to the tank's shell and produced 130,000 cu ft/min of air. The airflow was directed beneath the tank through a segmented skirtmore » fixed to the circumference of the tank's base. Less than 0.5 psi air pressure across the tank floor was needed to lift the tank. Four large D-7 tractors pulled and guided the tank up the incline onto its new pad, where the vessel was rotated into alignment for piping connections. Preliminary rig-up, grading, and pad preparation took six days, but actual tank relocation required only two hours. Getty's Cushing terminal feeds to the 20 in. dia Osage pipeline that serves Getty's El Dorado, Kans., refinery as well as other carriers.« less

  3. Assessment of Tank 241-S-112 Liquid Waste Mixing in Tank 241-SY-101

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Onishi, Yasuo; Trent, Donald S.; Wells, Beric E.

    The objectives of this study were to evaluate mixing of liquid waste from Tank 241-S-112 with waste in Tank 241-SY-101 and to determine the properties of the resulting waste for the cross-site transfer to avoid potential double-shell tank corrosion and pipeline plugging. We applied the time-varying, three-dimensional computer code TEMPEST to Tank SY-101 as it received the S-112 liquid waste. The model predicts that temperature variations in Tank SY-101 generate a natural convection flow that is very slow, varying from about 7 x 10{sup -5} to 1 x 10{sup -3} ft/sec (0.3 to about 4 ft/hr) in most areas. Thus,more » natural convection would eventually mix the liquid waste in SY-101 but would be very slow to achieve nearly complete mixing. These simulations indicate that the mixing of S-112 and SY-101 wastes in Tank SY-101 is a very slow process, and the density difference between the two wastes would further limit mixing. It is expected to take days or weeks to achieve relatively complete mixing in Tank SY-101.« less

  4. An Enriched Shell Element for Delamination Simulation in Composite Laminates

    NASA Technical Reports Server (NTRS)

    McElroy, Mark

    2015-01-01

    A formulation is presented for an enriched shell finite element capable of delamination simulation in composite laminates. The element uses an adaptive splitting approach for damage characterization that allows for straightforward low-fidelity model creation and a numerically efficient solution. The Floating Node Method is used in conjunction with the Virtual Crack Closure Technique to predict delamination growth and represent it discretely at an arbitrary ply interface. The enriched element is verified for Mode I delamination simulation using numerical benchmark data. After determining important mesh configuration guidelines for the vicinity of the delamination front in the model, a good correlation was found between the enriched shell element model results and the benchmark data set.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Girardot, Crystal; Harlow, Don; Venetz, Theodore

    2012-07-01

    Washington River Protection Solutions, LLC (WRPS) developed an enhanced single-shell tank (SST) integrity project in 2009. An expert panel on SST integrity was created to provide recommendations supporting the development of the project. One primary recommendation was to expand the leak assessment reports (substitute report or LD-1) to include leak causes and locations. The recommendation has been included in the M-045-91F Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) as one of four targets relating to SST leak integrity. The 241-SX Farm (SX Farm) tanks with leak losses were addressed on an individual tank basis as part of LD-1.more » Currently, 8 out of 23 SSTs that have been reported to having a liner leak are located in SX Farm. This percentage was the highest compared to other tank farms which is why SX Farm was analyzed first. The SX Farm is comprised of fifteen SSTs built 1953-1954. The tanks are arranged in rows of three tanks each, forming a cascade. Each of the SX Farm tanks has a nominal 1-million-gal storage capacity. Of the fifteen tanks in SX Farm, an assessment reported leak losses for the following tanks: 241-SX-107, 241-SX-108, 241-SX-109, 241-SX- 111, 241-SX-112, 241-SX-113, 241-SX-114 and 241-SX-115. The method used to identify leak location consisted of reviewing in-tank and ex-tank leak detection information. This provided the basic data identifying where and when the first leaks were detected. In-tank leak detection consisted of liquid level measurement that can be augmented with photographs which can provide an indication of the vertical leak location on the sidewall. Ex-tank leak detection for the leaking tanks consisted of soil radiation data from laterals and dry-wells near the tank. The in-tank and ex-tank leak detection can provide an indication of the possible leak location radially around and under the tank. Potential leak causes were determined using in-tank and ex-tank information that is not directly related to leak detection. In-tank parameters can include temperature of the supernatant and sludge, types of waste, and chemical determination by either transfer or sample analysis. Ex-tank information can be assembled from many sources including design media, construction conditions, technical specifications, and other sources. Five conditions may have contributed to SX Farm tank liner failure including: tank design, thermal shock, chemistry-corrosion, liner behavior (bulging), and construction temperature. Tank design did not apparently change from tank to tank for the SX Farm tanks; however, there could be many unknown variables present in the quality of materials and quality of construction. Several significant SX Farm tank design changes occurred from previous successful tank farm designs. Tank construction occurred in winter under cold conditions which could have affected the ductile to brittle transition temperature of the tanks. The SX Farm tanks received high temperature boiling waste from REDOX which challenged the tank design with rapid heat up and high temperatures. All eight of the leaking SX Farm tanks had relatively high rate of temperature rise. Supernatant removal with subsequent nitrate leaching was conducted in all but three of the eight leaking tanks prior to leaks being detected. It is possible that no one characteristic of the SX Farm tanks could in isolation from the others have resulted in failure. However, the application of so many stressors - heat up rate, high temperature, loss of corrosion protection, and tank design working jointly or serially resulted in their failure. Thermal shock coupled with the tank design, construction conditions, and nitrate leaching seem to be the overriding factors that can lead to tank liner failure. The distinction between leaking and sound SX Farm tanks seems to center on the waste types, thermal conditions, and nitrate leaching. (authors)« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    VENETZ TJ; WASHENFELDER D; JOHNSON J

    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.more » 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 leak detection. In-tank parameters can include temperature of the supernatant and sludge, types of waste, and chemical determination by either transfer or sample analysis. Ex-tank information can be assembled from many sources including design media, construction conditions, technical specifications, and other sources. Five conditions may have contributed to SX Farm tank liner failure including: tank design, thermal shock, chemistry-corrosion, liner behavior (bulging), and construction temperature. Tank design did not apparently change from tank to tank for the SX Farm tanks; however, there could be many unknown variables present in the quality of materials and quality of construction. Several significant SX Farm tank design changes occurred from previous successful tank farm designs. Tank construction occurred in winter under cold conditions which could have affected the ductile to brittle transition temperature of the tanks. The SX Farm tanks received high temperature boiling waste from REDOX which challenged the tank design with rapid heat up and high temperatures. All eight of the leaking SX Farm tanks had relatively high rate of temperature rise. Supernatant removal with subsequent nitrate leaching was conducted in all but three of the eight leaking tanks prior to leaks being detected. It is possible that no one characteristic of the SX Farm tanks could in isolation from the others have resulted in failure. However, the application of so many stressors - heat up rate, high temperature, loss of corrosion protection, and tank design - working jointly or serially resulted in their failure. Thermal shock coupled with the tank design, construction conditions, and nitrate leaching seem to be the overriding factors that can lead to tank liner failure. The distinction between leaking and sound SX Farm tanks seems to center on the waste types, thermal conditions, and nitrate leaching.« less

  7. THE INTEGRATION OF A PROPOSED ZONE CLOSURE APPROACH FOR THE PLUTONIUM FINISHING PLANT (PFP) DECOMMISSIONING & THE PFP ZONE HANFORD SITE WASHINGTON

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    HOPKINS, A.M.

    2005-02-23

    The Plutonium Finishing Plant (PFP) and associated processing facilities are located in the 200 area of the Hanford Site in Eastern Washington. This area is part of what is now called the Central Plateau. In order to achieve closure of the contaminated facilities and waste sites at Hanford on the Central Plateau (CP), a geographic re-districting of the area into zones has been proposed in the recently published Plan for Central Plateau Closure. One of the 22 zones proposed in the Central Plateau encompasses the PFP and ancillary facilities. Approximately eighty six buildings are included in the PFP Zone. Thismore » paper addresses the approach for the closure of the PFP Zone within the Central Plateau. The PFP complex of buildings forms the bulk of the structures in the PFP Zone. For closure of the above-grade portion of structures within the PFP complex, the approach is to remove them to a state called ''slab-on-grade'' per the criteria contained in PFP End Point Criteria document and as documented in action memoranda. For below-grade portions of the structures (such as below-grade rooms, pipe trenches and underground ducts), the approach is to remove as much residual contamination as practicable and to fill the void spaces with clean fill material such as sand, grout, or controlled density fill. This approach will be modified as planning for the waste sites progresses to ensure that the actions of the PFP decommissioning projects do not negatively impact future planned actions under the CERCLA. Cribs, settling tanks, septic tanks and other miscellaneous below-grade void spaces will either be cleaned to the extent practicable and filled or will be covered with an environmental barrier as determined by further studies and CERCLA decision documents. Currently, between two and five environmental barriers are proposed to be placed over waste sites and remaining building slabs in the PFP Zone.« less

  8. Corrective Action Decision Document/Closure Report for Corrective Action 405: Area 3 Septic Systems, Tonopah Test Range, Nevada Rev. No.: 0, April 2002

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    IT Coroporation, Las Vegas, NV

    2002-04-17

    This Corrective Action Decision Document/Closure Report (CADD/CR) has been prepared for Corrective Action Unit (CAU) 405, Area 3 Septic Systems, in accordance with the Federal Facility Agreement and Consent Order. Located on the Tonopah Test Range (TTR) approximately 235 miles north of Las Vegas, Nevada, CAU 405 consists of three Corrective Action Sites (CASs): 03-05-002-SW03, Septic Waste System (aka: Septic Waste System [SWS] 3); 03-05-002-SW04, Septic Waste System (aka: SWS 4); 03-05-002-SW07, Septic Waste System (aka: SWS 7). The CADD and CR have been combined into one report because no further action is recommended for this CAU, and this reportmore » provides specific information necessary to support this recommendation. The CAU consists of three leachfields and associated collection systems that were installed in or near Area 3 for wastewater disposal. These systems were used until a consolidated sewer system was installed in 1990. Historically, operations within various buildin gs in and near Area 3 of the TTR generated sanitary and industrial wastewaters. There is a potential that contaminants of concern (COCs) were present in the wastewaters and were disposed of in septic tanks and leachfields. The justification for closure of this CAU without further action is based on process knowledge and the results of the investigative activities. Closure activities were performed at these CASs between January 14 and February 2, 2002, and included the removal and proper disposal of media containing regulated constituents and proper closure of septic tanks. No further action is appropriate because all necessary activities have been completed. No use restrictions are required to be imposed for these sites since the investigation showed no evidence of COCs identified in the soil for CAU 405.« less

  9. Project W-211, initial tank retrieval systems, description of operations for 241-AP-102 and 241-AP-104

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    RIECK, C.A.

    1999-02-25

    The primary purpose of the Initial Tank Retrieval Systems (ITRS) is to provide systems for retrieval of radioactive wastes stored in underground double-shell tanks (DSTS) for transfer to alternate storage, evaporation, pretreatment or treatment, while concurrently reducing risks associated with safety watch list and other DSTs. This Description of Operations (DOO) defines the control philosophy for the waste retrieval system for tanks 241-AP-102 (AP-102) and 241-AP-104 (AP-104). This DOO will provide a basis for the detailed design of the Retrieval Control System (RCS) for AP-102 and AP-104 and establishes test criteria for the RCS. The test criteria will be usedmore » during qualification testing and acceptance testing to verify operability.« less

  10. CALUTRON ASSEMBLING AND DISASSEMBLING APPARATUS

    DOEpatents

    Andrews, R.E.

    1959-01-27

    A closure plate assembly is presented for a calutron tank. Due to the size and weight of the calutron tank a special face plate, hinges and latch construction are required. The salient feature of the invention is the provision of a face plate carrying the ion separating niechanism and adapted to close an open side of a calutron tank. A spring-type hinge secured to the face plate at one end prevents injury to the sealing gasket as the face plate is inserted and withdrawn. In additions a hinged support for the face plate comprises readily separable hinge elements, so that the face plate may first be swung outwardly from its operative position far enough to clear the ion separating meehanism carried thereby, and may thereafter be elevated and transported by a convcntional overhead crane.

  11. Production of n-rich Nuclei along the Closed Shell N=126 in the collision 136Xe + 208Pb @E lab =870 MeV

    NASA Astrophysics Data System (ADS)

    Quero, D.; Vardaci, E.; Kozulin, E. M.; Zagrebaev, V. A.; Corradi, L.; Pulcini, A.; La Rana, G.; Itkis, I. M.; Knyazheva, G. N.; Novikov, K.; Harca, I.; Fioretto, E.; Stefanini, A. M.; Montanari, D.; Montagnoli, G.; Scarlassara, F.; Szilner, S.; Mijatović, T.; Trzaska, W. H.

    2018-05-01

    Multi-nucleon transfer reactions are nowadays the only known mean to produce neutron-rich nuclei in the Terra Incognita. The closed-shell region N=126 is crucial for both studying shell-quenching in exotic nuclei and the r-process, being its last “waiting-point”. The choice of suitable reactions is challenging and a favorable case is 136Xe+208Pb, near the Coulomb barrier, because their neutron shell-closures play a stabilizing role, favoring the proton-transfer from lead to xenon. TOF-TOF data were analyzed to reconstruct the mass-energy distribution of the primary fragments. Preliminary results of an experiment held at Laboratori Nazionali di Legnaro with PRISMA, aimed at A and Z identification of the products, will be shown.

  12. 49 CFR 179.200-4 - Insulation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ..., the tank shell and expansion dome when used must be insulated with an approved material. The entire... thermal conductance at 60 °F is not more than 0.225 Btu per hour, per square foot, per degree F...

  13. 49 CFR 178.345-4 - Joints.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Containers for Motor Vehicle Transportation § 178.345-4 Joints. (a) All joints between the cargo tank shell... accessible for inspection. [Amdt. 178-89, 54 FR 25022, June 12, 1989, as amended by Amdt. 178-118, 61 FR...

  14. 49 CFR 178.345-4 - Joints.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Containers for Motor Vehicle Transportation § 178.345-4 Joints. (a) All joints between the cargo tank shell... accessible for inspection. [Amdt. 178-89, 54 FR 25022, June 12, 1989, as amended by Amdt. 178-118, 61 FR...

  15. 49 CFR 178.345-4 - Joints.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... Containers for Motor Vehicle Transportation § 178.345-4 Joints. (a) All joints between the cargo tank shell... accessible for inspection. [Amdt. 178-89, 54 FR 25022, June 12, 1989, as amended by Amdt. 178-118, 61 FR...

  16. 49 CFR 178.345-4 - Joints.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Containers for Motor Vehicle Transportation § 178.345-4 Joints. (a) All joints between the cargo tank shell... accessible for inspection. [Amdt. 178-89, 54 FR 25022, June 12, 1989, as amended by Amdt. 178-118, 61 FR...

  17. 49 CFR 178.345-4 - Joints.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Containers for Motor Vehicle Transportation § 178.345-4 Joints. (a) All joints between the cargo tank shell... accessible for inspection. [Amdt. 178-89, 54 FR 25022, June 12, 1989, as amended by Amdt. 178-118, 61 FR...

  18. Design Issues Affecting Pipings Associated with a New Moisture Separator Reheater

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hyung-Keun, Kim; Jae-Kyoung, Cho

    2006-07-01

    This paper summarizes the piping design effects on a New Moisture Separator Reheater (MSR) in Shin-Kori Nuclear Power Plant Units 1 and 2 (SKN 1 and 2) being under the construction in Korea. This SKN 1 and 2 has the same arrangement of a Turbine-Generator set as one of Korea Standard Nuclear Plant Units ( OPR 1000 ) in commercial operation. The Turbine-Generator Supplier has developed a new Moisture Separator Reheater which has first and second stage heating steam supply connections respectively, at both ends of the shell side of the vessel in comparison to MSR of OPR 1000 whichmore » has first and second stage heating steam supply connections at only one end. The different locations of reheaters in MSR cause changes in the associated pipings such as 2. stage reheater heating steam, 2. stage reheater drain, shell drain, drain tank location and tank condensate drainage pipings. (authors)« less

  19. Structural analyses for the modification and verification of the Viking aeroshell

    NASA Technical Reports Server (NTRS)

    Stephens, W. B.; Anderson, M. S.

    1976-01-01

    The Viking aeroshell is an extremely lightweight flexible shell structure that has undergone thorough buckling analyses in the course of its development. The analytical tools and modeling technique required to reveal the structural behavior are presented. Significant results are given which illustrate the complex failure modes not usually observed in simple models and analyses. Both shell-of-revolution analysis for the pressure loads and thermal loads during entry and a general shell analysis for concentrated tank loads during launch were used. In many cases fixes or alterations to the structure were required, and the role of the analytical results in determining these modifications is indicated.

  20. Alpha decay properties of the semi-magic nucleus 219Np

    NASA Astrophysics Data System (ADS)

    Yang, H. B.; Ma, L.; Zhang, Z. Y.; Yang, C. L.; Gan, Z. G.; Zhang, M. M.; Huang, M. H.; Yu, L.; Jiang, J.; Tian, Y. L.; Wang, Y. S.; Wang, J. G.; Liu, Z.; Liu, M. L.; Duan, L. M.; Zhou, S. G.; Ren, Z. Z.; Zhou, X. H.; Xu, H. S.; Xiao, G. Q.

    2018-02-01

    The semi-magic nucleus 219Np was produced in the fusion reaction 187Re(36Ar, 4n)219Np at the gas-filled recoil separator SHANS (Spectrometer for Heavy Atoms and Nuclear Structure). A fast electronics system based on waveform digitizers was used in the data acquisition and the sampled pulses were processed by digital algorithms. The reaction products were identified using spatial and time correlations between the implants and subsequent α decays. According to the observed α-decay chain, an energy of Eα = 9039 (40) keV and a half-life of T1/2 =0.15-0.07 + 0.72 ms were determined for 219Np. The deduced proton binding energy of 219Np fits well into the systematics, which gives another evidence of that there is no sub-shell closure at Z = 92. The influence of the N = 126 shell closure on the stability of Np isotopes is discussed within the framework of α-decay reduced widths.

  1. Systematic study of α decay of nuclei around the Z =82 , N =126 shell closures within the cluster-formation model and proximity potential 1977 formalism

    NASA Astrophysics Data System (ADS)

    Deng, Jun-Gang; Zhao, Jie-Cheng; Chu, Peng-Cheng; Li, Xiao-Hua

    2018-04-01

    In the present work, we systematically study the α decay preformation factors Pα within the cluster-formation model and α decay half-lives by the proximity potential 1977 formalism for nuclei around Z =82 ,N =126 closed shells. The calculations show that the realistic Pα is linearly dependent on the product of valance protons (holes) and valance neutrons (holes) NpNn . It is consistent with our previous works [Sun et al., Phys. Rev. C 94, 024338 (2016), 10.1103/PhysRevC.94.024338; Deng et al., Phys. Rev. C 96, 024318 (2017), 10.1103/PhysRevC.96.024318], in which Pα are model dependent and extracted from the ratios of calculated α half-lives to experimental data. Combining with our previous works, we confirm that the valance proton-neutron interaction plays a key role in the α preformation for nuclei around Z =82 ,N =126 shell closures whether the Pα is model dependent or microcosmic. In addition, our calculated α decay half-lives by using the proximity potential 1977 formalism taking Pα evaluated by the cluster-formation model can well reproduce the experimental data and significantly reduce the errors.

  2. Estimating Residual Solids Volume In Underground Storage Tanks

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Clark, Jason L.; Worthy, S. Jason; Martin, Bruce A.

    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 andmore » 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 accurately determine a volume is a function of the quantity and quality of the waste tank images. Currently, mapping is performed remotely with closed circuit video cameras and still photograph cameras due to the hazardous environment. There are two methods that can be used to create a solids volume map. These methods are: liquid transfer mapping / post transfer mapping and final residual solids mapping. The task is performed during a transfer because the liquid level (which is a known value determined by a level measurement device) is used as a landmark to indicate solids accumulation heights. The post transfer method is primarily utilized after the majority of waste has been removed. This method relies on video and still digital images of the waste tank after the liquid transfer is complete to obtain the relative height of solids across a waste tank in relation to known and usable landmarks within the waste tank (cooling coils, column base plates, etc.). In order to accurately monitor solids over time across various cleaning campaigns, and provide a technical basis to support final waste tank closure, a consistent methodology for volume determination has been developed and implemented at SRS.« less

  3. Pressurization System Modeling for a Generic Bimese Two- Stage-to-Orbit Reusable Launch Vehicle

    NASA Technical Reports Server (NTRS)

    Mazurkivich, Pete; Chandler, Frank; Nguyen, Han

    2005-01-01

    A pressurization system model was developed for a generic bimese Two-Stage-to-orbit Reusable Launch Vehicle using a cross-feed system and operating with densified propellants. The model was based on the pressurization system model for a crossfeed subscale water test article and was validated with test data obtained from the test article. The model consists of the liquid oxygen and liquid hydrogen pressurization models, each made up of two submodels, Booster and Orbiter tank pressurization models. The tanks are controlled within a 0.2-psi band and pressurized on the ground with ambient helium and autogenously in flight with gaseous oxygen and gaseous hydrogen. A 15-psi pressure difference is maintained between the Booster and Orbiter tanks to ensure crossfeed check valve closure before Booster separation. The analysis uses an ascent trajectory generated for a generic bimese vehicle and a tank configuration based on the Space Shuttle External Tank. It determines the flow rates required to pressurize the tanks on the ground and in flight, and demonstrates the model's capability to analyze the pressurization system performance of a full-scale bimese vehicle with densified propellants.

  4. Engineering report for simulated riser installation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Brevick, C.H., Westinghouse Hanford

    1996-05-09

    The simulated riser installation field tests demonstrated that new access ports (risers) can be installed safely, quickly, and economically in the concrete domes of existing underground single- shell waste storage tanks by utilizing proven rotary drilling equipment and vacuum excavation techniques. The new riser installation will seal against water intrusion, provide as table riser anchored to the tank dome, and be installed in accordance with ALARA principles. The information contained in the report will apply to actual riser installation activity in the future.

  5. Structural Configuration Analysis of Crew Exploration Vehicle Concepts

    NASA Technical Reports Server (NTRS)

    Mukhopadhyay, V.

    2006-01-01

    Structural configuration modeling and finite element analysis of crew exploration vehicle (CEV) concepts are presented. In the structural configuration design approach, parametric solid models of the pressurized shell and tanks are developed. The CEV internal cabin pressure is same as in the International Space Station (ISS) to enable docking with the ISS without an intermediate airlock. Effects of this internal pressure load on the stress distribution, factor of safety, mass and deflections are investigated. Uniform 7 mm thick skin shell, 5 mm thick shell with ribs and frames, and isogrid skin construction options are investigated. From this limited study, the isogrid construction appears to provide most strength/mass ratio. Initial finite element analysis results on the service module tanks are also presented. These rapid finite element analyses, stress and factor of safety distribution results are presented as a part of lessons learned and to build up a structural mass estimation and sizing database for future technology support. This rapid structural analysis process may also facilitate better definition of the vehicles and components for rapid prototyping. However, these structural analysis results are highly conceptual and exploratory in nature and do not reflect current configuration designs being conducted at the program level by NASA and industry.

  6. Buckling Design Studies of Inverted, Oblate Bulkheads for a Propellant Tank

    NASA Technical Reports Server (NTRS)

    Smeltzer, Stanley S., III; Bowman, Lynn M.

    2002-01-01

    An investigation of the deformation and buckling characteristics of a composite, oblate bulkhead that has an inverted geometry and is subjected to pressure-only loading is presented for three bulkhead geometries and thicknesses. The effects of a stiffening support ring at the bulkhead to cylinder interface are also evaluated. Buckling analyses conducted using the axisymmetric shell code BOSOR4 are discussed for several bulkhead configurations. These results are analytically verified using results from the Structural Analysis of General Shells (STAGS) code for a selected bulkhead configuration. The buckling characterization of an inverted, oblate bulkhead requires careful attention as small changes in bulkhead parameters can have a significant effect on the critical buckling load. Comparison of BOSOR4 and STAGS results provided a very good correlation between the two analysis methods. In addition, the analysis code BOSOR4 was found to be an efficient sizing tool that is useful during the preliminary design stage of a practical shell structure. Together, these two aspects should give the design engineer confidence in sizing these stability critical structures. Additional characterization is warranted, especially for a composite tank structure, since only one bulkhead configuration was examined closely.

  7. 75 FR 1048 - Notice of Public Hearings on the Draft Tank Closure and Waste Management Environmental Impact...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-08

    ... ending March 19, 2010. The State of Washington, Department of Ecology (Ecology) is a cooperating agency.... For general questions and information about the Washington State Department of Ecology, contact... Ecology as a cooperating agency, prepared the Draft TC & WM EIS in accordance with the Council on...

  8. 43 CFR 3809.420 - What performance standards apply to my notice or plan of operations?

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... or facility maintenance after project closure. Long-term, or post-mining, effluent capture and... the Resource Conservation and Recovery Act (42 U.S.C. 6901 et seq.). All garbage, refuse or waste... design. (iv) You must construct a secondary containment system around vats, tanks, or recovery circuits...

  9. 43 CFR 3809.420 - What performance standards apply to my notice or plan of operations?

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... or facility maintenance after project closure. Long-term, or post-mining, effluent capture and... the Resource Conservation and Recovery Act (42 U.S.C. 6901 et seq.). All garbage, refuse or waste... design. (iv) You must construct a secondary containment system around vats, tanks, or recovery circuits...

  10. 9 CFR 354.244 - Temperatures and cooling and freezing procedures.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... wrapped or packaged in water-vapor resistant cartons or the containers should be lined with heavy water... carcasses and to permit unsealed closure or sealing in such a manner that water-vapor loss from the product... cooling tank containing running cold tap water to remove the animal heat from the carcass. Carcasses shall...

  11. 9 CFR 354.244 - Temperatures and cooling and freezing procedures.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... wrapped or packaged in water-vapor resistant cartons or the containers should be lined with heavy water... carcasses and to permit unsealed closure or sealing in such a manner that water-vapor loss from the product... cooling tank containing running cold tap water to remove the animal heat from the carcass. Carcasses shall...

  12. 9 CFR 354.244 - Temperatures and cooling and freezing procedures.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... wrapped or packaged in water-vapor resistant cartons or the containers should be lined with heavy water... carcasses and to permit unsealed closure or sealing in such a manner that water-vapor loss from the product... cooling tank containing running cold tap water to remove the animal heat from the carcass. Carcasses shall...

  13. 9 CFR 354.244 - Temperatures and cooling and freezing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... wrapped or packaged in water-vapor resistant cartons or the containers should be lined with heavy water... carcasses and to permit unsealed closure or sealing in such a manner that water-vapor loss from the product... cooling tank containing running cold tap water to remove the animal heat from the carcass. Carcasses shall...

  14. UNDERGROUND STORAGE TANK SITE CLOSURE USING ACTIVE INTERVENTION FOR SITE CLEANUP

    EPA Science Inventory

    The Clean Air Act Amendments of 1990 mandate seasonal or year-round use of oxygenated compounds in gasoline in certain areas of the country. Methyl t-butyl ether (MtBE) has been the most commonly used oxygenate. However, the use of MtBE has created a significant risk to groundwat...

  15. Alternative Chemical Cleaning Methods for High Level Waste Tanks: Actual Waste Testing with SRS Tank 5F Sludge

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    King, William D.; Hay, Michael S.

    Solubility testing with actual High Level Waste tank sludge has been conducted in order to evaluate several alternative chemical cleaning technologies for the dissolution of sludge residuals remaining in the tanks after the exhaustion of mechanical cleaning and sludge sluicing efforts. Tests were conducted with archived Savannah River Site (SRS) radioactive sludge solids that had been retrieved from Tank 5F in order to determine the effectiveness of an optimized, dilute oxalic/nitric acid cleaning reagent toward dissolving the bulk non-radioactive waste components. Solubility tests were performed by direct sludge contact with the oxalic/nitric acid reagent and with sludge that had beenmore » pretreated and acidified with dilute nitric acid. For comparison purposes, separate samples were also contacted with pure, concentrated oxalic acid following current baseline tank chemical cleaning methods. One goal of testing with the optimized reagent was to compare the total amounts of oxalic acid and water required for sludge dissolution using the baseline and optimized cleaning methods. A second objective was to compare the two methods with regard to the dissolution of actinide species known to be drivers for SRS tank closure Performance Assessments (PA). Additionally, solubility tests were conducted with Tank 5 sludge using acidic and caustic permanganate-based methods focused on the “targeted” dissolution of actinide species.« less

  16. Characterization of Al 2219 material for the application of the spin-forming-process

    NASA Astrophysics Data System (ADS)

    Mueller-Wiesner, D.; Sieger, E.; Ernsberger, K.

    1991-10-01

    The shells of the propellant tanks of the Ariane 5 EPS stage are to be manufactured by the spin forming process. The material for the shells (hemispheres) is the aluminum alloy 2219. By a material characterization program optimized parameters for the application of the forming process starting from different material conditions (T31 temper and '0' condition) are determined. Based on the results of this program it was decided to start spin forming in the '0' condition for flight hardware.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Quigley, K.D.; Butterworth, St.W.; Lockie, K.A.

    2008-07-01

    Significant progress has been made at the U.S. Department of Energy (DOE) Idaho National Laboratory (INL) to empty, clean and close radioactive liquid waste storage tanks at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF). The TFF includes eleven 1,135.6-kL (300,000-gal) underground stainless steel storage tanks and four smaller, 113.5-kL (30,000-gal) stainless steel tanks, along with tank vaults, interconnecting piping, and ancillary equipment. The TFF tanks have historically been used to store a variety of radioactive liquid waste, including wastes associated with past spent nuclear fuel reprocessing. Although four of the large storage tanks remain inmore » use for waste storage, the other seven 1,135.6-kL (300,000-gal) tanks and the four 113.5-kL (30,000-gal) tanks have been emptied of waste, cleaned and filled with grout. A water spray cleaning system was developed and deployed to clean internal tank surfaces and remove remaining tank wastes. The cleaning system was effective in removing all but a very small volume of solid residual waste particles. Recent issuance of an Amended Record of Decision (ROD) in accordance with the National Environmental Policy Act, and a Waste Determination complying with Section 3116 of the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, has allowed commencement of grouting activities on the cleaned tanks. The first three 113.5-kL (30,000-gal) tanks were grouted in the Fall of 2006 and the fourth tank and the seven 1,135.6-kL (300,000-gal) tanks were filled with grout in 2007 to provide long-term stability. It is currently planned that associated tank valve boxes and interconnecting piping, will be stabilized with grout as early as 2008. (authors)« less

  18. Constrained Hartree-Fock Theory and Study of Deformed Structures of Closed Shell Nuclei

    NASA Astrophysics Data System (ADS)

    Praharaj, Choudhury

    2016-03-01

    We have studied some N or Z = 50 nuclei in a microscopic model with effective interaction in a reasonably large shell model space. Excitation of particles across 50 shell closure leads to well-deformed excited prolate configurations. The potential energy surfaces of nuclei are studied using Hartree-Fock theory with quadrupole constraint to explore the various deformed configurations of N = 50 nuclei 82Ge , 84Se and 86Kr . Energy spectra are calculated from various intrinsic states using Peierls-Yoccoz angular momentum projection technique. Results of spectra and electromagnetic moments and transitions will be presented for N = 50 nuclei and for Z = 50 114Sn nucleus. Supported by Grant No SB/S2/HEP-06/2013 of DST.

  19. Observation of high-spin bands with large moments of inertia in Xe 124

    DOE PAGES

    Nag, Somnath; Singh, A. K.; Hagemann, G. B.; ...

    2016-09-07

    In this paper, high-spin states in 124Xe have been populated using the 80Se( 48Ca, 4n) reaction at a beam energy of 207 MeV and high-multiplicity, γ-ray coincidence events were measured using the Gammasphere spectrometer. Six high-spin rotational bands with moments of inertia similar to those observed in neighboring nuclei have been observed. The experimental results are compared with calculations within the framework of the Cranked Nilsson-Strutinsky model. Finally, it is suggested that the configurations of the bands involve excitations of protons across the Z = 50 shell gap coupled to neutrons within the N = 50 - 82 shell ormore » excited across the N = 82 shell closure.« less

  20. ANALYSIS OF SAMPLES FROM TANK 5F CHEMICAL CLEANING

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Poirier, M.; Fink, S.

    2011-03-07

    The Savannah River Site (SRS) is preparing Tank 5F for closure. The first step in preparing the tank for closure is mechanical sludge removal. Following mechanical sludge removal, SRS performed chemical cleaning with oxalic acid to remove the sludge heel. Personnel are currently assessing the effectiveness of the chemical cleaning. SRS personnel collected liquid samples during chemical cleaning and submitted them to Savannah River National Laboratory (SRNL) for analysis. Following chemical cleaning, they collected a solid sample (also known as 'process sample') and submitted it to SRNL for analysis. The authors analyzed these samples to assess the effectiveness of themore » chemical cleaning process. The conclusions from this work are: (1) With the exception of iron, the dissolution of sludge components from Tank 5F agreed with results from the actual waste demonstration performed in 2007. The fraction of iron removed from Tank 5F by chemical cleaning was significantly less than the fraction removed in the SRNL demonstrations. The likely cause of this difference is the high pH following the first oxalic acid strike. (2) Most of the sludge mass remaining in the tank is iron and nickel. (3) The remaining sludge contains approximately 26 kg of barium, 37 kg of chromium, and 37 kg of mercury. (4) Most of the radioactivity remaining in the residual material is beta emitters and {sup 90}Sr. (5) The chemical cleaning removed more than {approx} 90% of the uranium isotopes and {sup 137}Cs. (6) The chemical cleaning removed {approx} 70% of the neptunium, {approx} 83% of the {sup 90}Sr, and {approx} 21% of the {sup 60}Co. (7) The chemical cleaning removed less than 10% of the plutonium, americium, and curium isotopes. (8) The chemical cleaning removed more than 90% of the aluminium, calcium, and sodium from the tank. (9) The cleaning operations removed 61% of lithium, 88% of non-radioactive strontium, and 65% of zirconium. The {sup 90}Sr and non-radioactive strontium were measured by different methods, and the differences in the fraction removed are not statistically significant. (10) Chemical cleaning removed 10-50% of the barium, chromium, iron, magnesium, manganese, and silicon. (11) Chemical cleaning removed only {approx}1% of the nickel.« less

  1. 1301259

    NASA Image and Video Library

    2013-12-10

    MARK HILBURGER, PROJECT ENGINEER FROM LANGLEY RESEARCH CENTER (LARC) WITH THE ALUMINUM-LITHIUM CYLINDER USED IN THE SHELL BUCKLE KNOCKDOWN FACTOR TESTING. DURING THE TESTING FORCE AND PRESSURE WERE INCREASINGLY APPLIED TO THE TOP OF AN EMPTY BUT PRESSURIZED ROCKET FUEL TANK TO EVALUATE ITS STRUCTURAL INTEGRITY.

  2. Deciphering the Origin of Plume-Textured Geodes.

    ERIC Educational Resources Information Center

    Garlick, George Donald; Jones, Francis Tucker

    1990-01-01

    Presented is an interpretation of the inward and outward growth and formation of plume textured geodes available from southern Brazil. Field occurrence, morphology of vesicles, growth history, closure of the agate shell, microscopic features, coherent reflection of light from convoluted surfaces, and accessory minerals of the inner cavity are…

  3. The bioeconomic impact of different management regulations on the Chesapeake Bay blue crab fishery

    USGS Publications Warehouse

    Bunnell, David B.; Lipton, Douglas W.; Miller, Thomas J.

    2010-01-01

    The harvest of blue crabs Callinectes sapidus in Chesapeake Bay declined 46% between 1993 and 2001 and remained low through 2008. Because the total market value of this fishery has declined by an average of US $ 3.3 million per year since 1993, the commercial fishery has been challenged to maintain profitability. We developed a bioeconomic simulation model of the Chesapeake Bay blue crab fishery to aid managers in determining which regulations will maximize revenues while ensuring a sustainable harvest. We compared 15 different management scenarios, including those implemented by Maryland and Virginia between 2007 and 2009, that sought to reduce female crab harvest and nine others that used seasonal closures, different size regulations, or the elimination of fishing for specific market categories. Six scenarios produced the highest revenues: the 2008 and 2009 Maryland regulations, spring and fall closures for female blue crabs, and 152- and 165-mm maximum size limits for females. Our most important finding was that for each state the 2008 and 2009 scenarios that implemented early closures of the female crab fishery produced higher revenues than the 2007 scenario, in which no early female closures were implemented. We conclude that the use of maximum size limits for female crabs would not be feasible despite their potentially high revenue, given the likelihood that the soft-shell and peeler fisheries cannot be expanded beyond their current capacity and the potentially high mortality rate for culled individuals that are the incorrect size. Our model results support the current use of seasonal closures for females, which permit relatively high exploitation of males and soft-shell and peeler blue crabs (which have high prices) while keeping the female crab harvest sustainable. Further, our bioeconomic model allows for the inclusion of an economic viewpoint along with biological data when target reference points are set by managers.

  4. Chemical Species in the Vapor Phase of Hanford Double-Shell Tanks: Potential Impacts on Waste Tank Corrosion Processes

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Felmy, Andrew R.; Qafoku, Odeta; Arey, Bruce W.

    2010-09-22

    The presence of corrosive and inhibiting chemicals on the tank walls in the vapor space, arising from the waste supernatant, dictate the type and degree of corrosion that occurs there. An understanding of how waste chemicals are transported to the walls and the affect on vapor species from changing supernatant chemistry (e.g., pH, etc.), are basic to the evaluation of risks and impacts of waste changes on vapor space corrosion (VSC). In order to address these issues the expert panel workshop on double-shell tank (DST) vapor space corrosion testing (RPP-RPT-31129) participants made several recommendations on the future data and modelingmore » needs in the area of DST corrosion. In particular, the drying of vapor phase condensates or supernatants can form salt or other deposits at the carbon steel interface resulting in a chemical composition at the near surface substantially different from that observed directly in the condensates or the supernatants. As a result, over the past three years chemical modeling and experimental studies have been performed on DST supernatants and condensates to predict the changes in chemical composition that might occur as condensates or supernatants equilibrate with the vapor space species and dry at the carbon steel surface. The experimental studies included research on both the chemical changes that occurred as the supernatants dried as well as research on how these chemical changes impact the corrosion of tank steels. The chemical modeling and associated experimental studies were performed at the Pacific Northwest National Laboratory (PNNL) and the research on tank steel corrosion at the Savannah River National Laboratory (SRNL). This report presents a summary of the research conducted at PNNL with special emphasis on the most recent studies conducted in FY10. An overall summary of the project results as well as their broader implications for vapor space corrosion of the DST’s is given at the end of this report.« less

  5. Performance evaluation of rotating pump jet mixing of radioactive wastes in Hanford Tanks 241-AP-102 and -104

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Onishi, Y.; Recknagle, K.P.

    The purpose of this study was to confirm the adequacy of a single mixer pump to fully mix the wastes that will be stored in Tanks 241-AP-102 and -104. These Hanford double-shell tanks (DSTs) will be used as staging tanks to receive low-activity wastes from other Hanford storage tanks and, in turn, will supply the wastes to private waste vitrification facilities for eventual solidification. The TEMPEST computer code was applied to Tanks AP-102 and -104 to simulate waste mixing generated by the 60-ft/s rotating jets and to determine the effectiveness of the single rotating pump to mix the waste. TEMPESTmore » simulates flow and mass/heat transport and chemical reactions (equilibrium and kinetic reactions) coupled together. Section 2 describes the pump jet mixing conditions the authors evaluated, the modeling cases, and their parameters. Section 3 reports model applications and assessment results. The summary and conclusions are presented in Section 4, and cited references are listed in Section 5.« less

  6. 75 FR 13268 - Extension of the Public Comment Period for the Draft Tank Closure and Waste Management...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-19

    ... Management Environmental Impact Statement for the Hanford Site, Richland, WA AGENCY: Department of Energy... Statement for the Hanford Site, Richland, Washington (Draft EIS, DOE/EIS-00391), made available for public... Draft EIS is also available through the Hanford Web site at: http://www.hanford.gov/orp . Issued in...

  7. Fort Holabird Defense Investigative Service (DIS), Base Realignment and Closure (BRAC) Cleanup Plan (BCP), Version II

    DTIC Science & Technology

    1998-12-01

    3-16 3.4.7 Category 7: Areas Not Evaluated or Require Additional Evaluation .................... 3-16...Alternatives Evaluation Process for DIS Disposal and Reuse, Fort Holabird, Maryland ........ 2-6 Figure 3-1. Environmental Restoration Early Action...Requirement AREE ............... Area Requiring Environmental Evaluation AST .................. Above-ground Storage Tank BCP .................. BRAC

  8. Investigation of Noise in Solids at Low Temperatures.

    DTIC Science & Technology

    1980-08-01

    surroundinz liquid helium dewar. The procedure used has been to liquefy helium gas and fill the liquid helium dewar. The liquefier operation is then...cryostat is at room temperature and is 25’ diameter X 72" long. Inside this is the liquid nitrogen shield which is a shell formed by two co-axial...cylinders of 22" and 19" diameters X 68’ long. This liquid nitrogen tank has a volume of 108 k. Across the bottom of this tank is a 1/16" thick copper

  9. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This volume contains the interim change notice for sample preparation methods. Covered are: acid digestion for metals analysis, fusion of Hanford tank waste solids, water leach of sludges/soils/other solids, extraction procedure toxicity (simulate leach in landfill), sample preparation for gamma spectroscopy, acid digestion for radiochemical analysis, leach preparation of solids for free cyanide analysis, aqueous leach of solids for anion analysis, microwave digestion of glasses and slurries for ICP/MS, toxicity characteristic leaching extraction for inorganics, leach/dissolution of activated metal for radiochemical analysis, extraction of single-shell tank (SST) samples for semi-VOC analysis, preparation and cleanup of hydrocarbon- containing samples for VOCmore » and semi-VOC analysis, receiving of waste tank samples in onsite transfer cask, receipt and inspection of SST samples, receipt and extrusion of core samples at 325A shielded facility, cleaning and shipping of waste tank samplers, homogenization of solutions/slurries/sludges, and test sample preparation for bioassay quality control program.« less

  10. Removal of 137-Cs from Dissolved Hanford Tank Saltcake by Treatment with IE-911

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rapko, Brian M.; Sinkov, Sergei I.; Levitskaia, Tatiana G.

    2003-12-09

    The U.S. Department of Energy’s Richland Operations Office plans to accelerate the cleanup of the Hanford Site. Testing new technology for the accelerated cleanup will require dissolved saltcake from single-shell tanks. However, the 137Cs will need to be removed from the saltcake to alleviate radiation hazards. A saltcake composite constructed from archived samples from Hanford Site single-shell tanks 241-S-101, 241-S-109, 241-S-110, 241-S-111, 241-U-106, and 241-U-109 was dissolved in water, adjusted to 5 M Na, and transferred from the 222-S Laboratory to the Radiochemical Processing Laboratory (RPL). At the RPL, the approximately 5.5 liters of solution was passed through a 0.2-micronmore » polyethersulfone filter, collected, and homogenized. The filtered solution then was passed through an ion exchange column containing approximately 150 mL IONSIV® IE-911, an engineered form of crystalline silicotitanate available from UOP, at approximately 200 mL/hour in a continuous operation until all of the feed solution had been run through the column. An analysis of the 137Cs concentrations in the initial feed solution and combined column effluent indicates that > 99.999 percent of the Cs in the feed solution was removed by this operation. PNNR« less

  11. COMPUTATIONAL FLUID DYNAMICS MODELING OF SCALED HANFORD DOUBLE SHELL TANK MIXING - CFD MODELING SENSITIVITY STUDY RESULTS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    JACKSON VL

    2011-08-31

    The primary purpose of the tank mixing and sampling demonstration program is to mitigate the technical risks associated with the ability of the Hanford tank farm delivery and celtification systems to measure and deliver a uniformly mixed high-level waste (HLW) feed to the Waste Treatment and Immobilization Plant (WTP) Uniform feed to the WTP is a requirement of 24590-WTP-ICD-MG-01-019, ICD-19 - Interface Control Document for Waste Feed, although the exact definition of uniform is evolving in this context. Computational Fluid Dynamics (CFD) modeling has been used to assist in evaluating scaleup issues, study operational parameters, and predict mixing performance atmore » full-scale.« less

  12. In-beam γ -ray spectroscopy of the neutron-rich platinum isotope 200Pt toward the N =126 shell gap

    NASA Astrophysics Data System (ADS)

    John, P. R.; Valiente-Dobón, J. J.; Mengoni, D.; Modamio, V.; Lunardi, S.; Bazzacco, D.; Gadea, A.; Wheldon, C.; Rodríguez, T. R.; Alexander, T.; de Angelis, G.; Ashwood, N.; Barr, M.; Benzoni, G.; Birkenbach, B.; Bizzeti, P. G.; Bizzeti-Sona, A. M.; Bottoni, S.; Bowry, M.; Bracco, A.; Browne, F.; Bunce, M.; Camera, F.; Corradi, L.; Crespi, F. C. L.; Melon, B.; Farnea, E.; Fioretto, E.; Gottardo, A.; Grente, L.; Hess, H.; Kokalova, Tz.; Korten, W.; Kuşoǧlu, A.; Lenzi, S.; Leoni, S.; Ljungvall, J.; Menegazzo, R.; Michelagnoli, C.; Mijatović, T.; Montagnoli, G.; Montanari, D.; Napoli, D. R.; Podolyák, Zs.; Pollarolo, G.; Recchia, F.; Reiter, P.; Roberts, O. J.; Şahin, E.; Salsac, M.-D.; Scarlassara, F.; Sferrazza, M.; Söderström, P.-A.; Stefanini, A. M.; Szilner, S.; Ur, C. A.; Vogt, A.; Walshe, J.

    2017-06-01

    The neutron-rich nucleus 200Pt is investigated via in-beam γ -ray spectroscopy to study the shape evolution in the neutron-rich platinum isotopes towards the N =126 shell closure. The two-neutron transfer reaction 198Pt(82Se, 80Se)200Pt is used to populate excited states of 200Pt. The Advanced Gamma Ray Tracking Array (AGATA) demonstrator coupled with the PRISMA spectrometer detects γ rays coincident with the 80Se recoils, the binary partner of 200Pt. The binary partner method is applied to extract the γ -ray transitions and build the level scheme of 200Pt. The level at 1884 keV reported by Yates et al. [S. W. Yates, E. M. Baum, E. A. Henry, L. G. Mann, N. Roy, A. Aprahamian, R. A. Meyer, and R. Estep, Phys. Rev. C 37, 1889 (1988)] was confirmed to be at 1882.1 keV and assigned as the (61+) state. An additional γ ray was found and it presumably deexcites the (81+) state. The results are compared with state-of-the-art beyond mean-field calculations, performed for the even-even 190 -204Pt isotopes, revealing that 200Pt marks the transition from the γ -unstable behavior of lighter Pt nuclei towards a more spherical one when approaching the N =126 shell closure.

  13. Mg and 18O Variations in the Shell of the Chilean Gastropod Concholepas concholepas Reflect SST and Growth Rate variations

    NASA Astrophysics Data System (ADS)

    Guzman, N.; Lazareth, C. E.; Poitrasson, F.; Cuif, J.; Ortlieb, L.

    2004-12-01

    To validate the use of fossil mollusc shells as recorders of environmental conditions, a primary calibration study was carried out on modern shells of the Chilean gastropod Concholepas concholepas, the so-called southern hemisphere abalone which is particularly abundant in Holocene archaeological sites. Organisms were maintained in culture tanks and feed with live mytilids. The sea water temperature in the tank was recorded every half-an-hour by an automatic device. The experiment lasted several months. Periodical marking with calcein provided a precise chronological control of the shell growth. Thus, well-dated high resolution chemical profiles could be directly compared with temperatures during shell formation. Geochemical analyses of the calcite layers include Mg, Sr and 16O/18O composition. Trace elements were analysed using Laser Ablation ICP-MS and Electron Microprobe while stable isotopes were measured on a Secondary Ion Mass spectrometry (SIMS). The shell growth rate during two months of formation varied between 30 and 140 µm/day which allows us to reach a temporal resolution for chemical profiles between a few hours and three days. The growth rate variations do not seem to be related to temperature fluctuations. Only Mg content was analytically reproducible and showed significant variations across the shells. The Mg high-resolution profiles display a grossly sinusoidal shape. Shells from different sites along the coasts of Chile showed mean Mg contents of 300 ppm and 500 ppm for mean temperatures of 17 and 20° C, respectively. This suggests a gross correlation between Mg and temperature. However, high resolution Mg results do not show an exact fitting neither with temperature nor with growth rates. Other parameters, like shell ageing as suggested by an amplitude increase observed near the edge of one of the shells, or other complex biological factors, may influence Mg incorporation into the shell. \\delta 18O values of the calcite vary between -1,5 and 2,0 \\permil for a temperature range between 17 and 22° C. Growth rate variations seem to be an important factor affecting the oxygen isotopic ratio within shells. When growth rate variations are limited, \\delta 18O and temperature are well correlated. The study confirms that, like for all biogenic carbonates, elemental and isotopic composition of the calcite layer of this gastropod, should not be used in paleoenvironmental reconstructions without detailed calibration experiments, and must systematically include precise growth rate analyses. The growth rhythms, which vary under the double influence of environmental and biological factors, are of paramount importance in the relationship between environmental parameters and geochemical composition of the growth layers of the shells. Work supported by "CONCHAS" Project (PNEDC).

  14. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Petersen, C.A., Westinghouse Hanford

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  15. One-Piece Battery Incorporating A Circulating Fluid Type Heat Exchanger

    DOEpatents

    Verhoog, Roelof

    2001-10-02

    A one-piece battery comprises a tank divided into cells each receiving an electrode assembly, closure means for the tank and a circulating fluid type heat exchanger facing the relatively larger faces of the electrode assembly. The fluid flows in a compartment defined by two flanges which incorporate a fluid inlet orifice communicating with a common inlet manifold and a fluid outlet orifice communicating with a common outlet manifold. The tank comprises at least two units and each unit comprises at least one cell delimited by walls. The wall facing a relatively larger face of the electrode assembly constitutes one of the flanges. Each unit further incorporates a portion of an inlet and outlet manifold. The units are fastened together so that the flanges when placed face-to-face form a sealed circulation compartment and the portions of the same manifold are aligned with each other.

  16. Proton configurations and pairing correlations at the N=80 superdeformed shell closure: Study of 145Tb

    NASA Astrophysics Data System (ADS)

    Mullins, S. M.; Schmeing, N. C.; Flibotte, S.; Hackman, G.; Rodriguez, J. L.; Waddington, J. C.; Yao, L.; Andrews, H. R.; Galindo-Uribarri, A.; Janzen, V. P.; Radford, D. C.; Ward, D.; Degraaf, J.; Drake, T. E.; Pilotte, S.; Paul, E. S.

    1994-11-01

    A superdeformed band has been observed in the N=80 nucleus 145Tb which was produced with the reactions 112Sn(37Cl,2p2n) and 118Sn(31P,4n) at bombarding energies of 187 and 160 MeV, respectively. Since superdeformed bands also exist in the three lighter N=80 isotones 142Sm, 143Eu, and 144Gd, it is now possible to understand the valence-proton configurations of these bands in a systematic way. The T(2) dynamic moment of inertia in 145Tb shows no evidence for the N = 6 quasiproton crossing that is observed in 144Gd. Comparison with cranked Woods-Saxon and total Routhian surface calculations suggests that the proton configuration in 145Tb is 61⊗[404]29/2+ in which the quasiproton crossing is blocked. Furthermore, like 143Eu and 142Sm, there is no evidence in the T (2) for the N=6 quasineutron crossing predicted by the calculations. This may indicate that static neutron pairing correlations are quenched at the N=80 superdeformed shell closure.

  17. Case Study in Corporate Memory Recovery: Hanford Tank Farms Miscellaneous Underground Waste Storage Tanks - 15344

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Washenfelder, D. J.; Johnson, J. M.; Turknett, J. C.

    In addition to managing the 177 underground waste storage tanks containing 212,000 m3 (56 million gal) of radioactive waste at the U. S. Department of Energy’s Hanford Site 200 Area Tank Farms, Washington River Protection Solutions LLC is responsible for managing numerous small catch tanks and special surveillance facilities. These are collectively known as “MUSTs” - Miscellaneous Underground Storage Tanks. The MUSTs typically collected drainage and flushes during waste transfer system piping changes; special surveillance facilities supported Tank Farm processes including post-World War II uranium recovery and later fission product recovery from tank wastes. Most were removed from service followingmore » deactivation of the single-shell tank system in 1980 and stabilized by pumping the remaining liquids from them. The MUSTs were isolated by blanking connecting transfer lines and adding weatherproofing to prevent rainwater entry. Over the next 30 years MUST operating records were dispersed into large electronic databases or transferred to the National Archives Regional Center in Seattle, Washington. During 2014 an effort to reacquire the historical bases for the MUSTs’ published waste volumes was undertaken. Corporate Memory Recovery from a variety of record sources allowed waste volumes to be initially determined for 21 MUSTs, and waste volumes to be adjusted for 37 others. Precursors and symptoms of Corporate Memory Loss were identified in the context of MUST records recovery.« less

  18. NRC Consultation and Monitoring at the Savannah River Site: Focusing Reviews of Two Different Disposal Actions - 12181

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ridge, A. Christianne; Barr, Cynthia S.; Pinkston, Karen E.

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2011, the NRC staff reviewed DOE performance assessments for tank closure at the F-Tank Farm (FTF) Facility and salt waste disposal at the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) as part of consultation and monitoring, respectively. Differences in inventories, waste forms,more » and key barriers led to different areas of focus in the NRC reviews of these two activities at the SRS. Because of the key role of chemically reducing grouts in both applications, the evaluation of chemical barriers was significant to both reviews. However, radionuclide solubility in precipitated metal oxides is expected to play a significant role in FTF performance whereas release of several key radionuclides from the SDF is controlled by sorption or precipitation within the cementitious wasteform itself. Similarly, both reviews included an evaluation of physical barriers to flow, but differences in the physical configurations of the waste led to differences in the reviews. For example, NRC's review of the FTF focused on the modeled degradation of carbon steel tank liners while the staff's review of the SDF performance included a detailed evaluation of the physical degradation of the saltstone wasteform and infiltration-limiting closure cap. Because of the long time periods considered (i.e., tens of thousands of years), the NRC reviews of both facilities included detailed evaluation of the engineered chemical and physical barriers. The NRC staff reviews of residual waste disposal in the FTF and salt waste disposal in the SDF focused on physical barriers to flow and chemical barriers to radionuclide release from the waste. Because the waste inventory and concentration at both sites is sufficient to generate unacceptable doses to an off-site member of the public or inadvertent intruder in the absence of engineered barriers, the NRC staff review focused on the engineering features DOE plans to put in place to limit radionuclide release. At the FTF, DOE expects that peak doses are delayed beyond a 10,000 year performance period by a combination of (1) the flow-limiting effect of the steel tank liner and (2) chemical conditions created by the stabilizing grout overlying the waste that limit the solubility of key radionuclides for tens of thousands of years. At the SDF, DOE expects that flow will be significantly limited by water shedding along the closure cap lower drainage layer and that radionuclide release will be further limited by radionuclide precipitation or sorption within the high pH, chemically reducing conditions created within the saltstone waste form. Because the performance of both facilities depends on the performance of engineered barriers for thousands of years, the reviews included a detailed evaluation of the expected long-term behavior of these barriers. As previously discussed, NRC staff reviews of DOE waste determinations during consultation are designed to evaluate the three NDAA criteria, whereas the review of an updated PA during monitoring only addresses whether the NRC staff has reasonable assurance that the planned disposal action will meet the performance objectives of 10 CFR Part 61. The NRC staff review of the Waste Determination for the FTF did not include conclusions about whether the planned disposal of residual waste at the FTF would meet the NDAA criteria because of the substantial uncertainties in the degree of waste removal DOE would achieve and other technical uncertainties. The main product of the NRC staff review of the planned FTF disposal action is the recommendation that DOE should conduct waste release experiments to increase support for key modeling assumptions related to: (1) the evolution of pH and Eh in the grouted tank system over time; (2) identification of HRR association with solid phases comprising the residual wastes; and (3) expected solubility of HRRs under a range of environmental or service conditions that the residual wastes in the contaminated zone are expected to be exposed to over time. Implementation of this recommendation is deemed crucial for NRC staff to have reasonable assurance that the performance objectives in 10 CFR Part 61, Subpart C can be met. Given the risk-significance of Tank 18 to the overall PA and the short timeline for closure of this tank, the NRC staff recommended that DOE should initiate discussions with NRC staff regarding implementation of this recommendation for Tank 18 as soon as practical. The NRC staff also recommended that experiments to address this recommendation should be conducted prior to final closure of Tank 18. Results of the Tank 18 residual waste experiments, if conducted, will be evaluated by NRC staff to determine the need for additional data collection, experiments, and modeling for Tank 18, as well as other FTF tanks. Additional information regarding the NRC staff's recommendations in this area, including details on the suggested implementation of other recommendations will be provided in the NRC staff's plan for monitoring the FTF later in FY 2012, after DOE makes a final decision on the waste determination. The NRC staff's review of waste disposal at the SDF is ongoing. When complete, the SDF TER will indicate whether the NRC staff continues to have reasonable assurance that waste disposal at the SDF will meet the performance objectives of 10 CFR Part 61 (NDAA Criterion 3). The TER also will include risk insights that will form the basis of the NRC staff's revised monitoring plan for the SDF. The NRC staff will publish an updated monitoring plan for the SDF later in FY 2012. (authors)« less

  19. Bubblers Speed Nuclear Waste Processing at SRS

    ScienceCinema

    None

    2018-05-23

    At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

  20. Microscopic description of quadrupole collectivity in neutron-rich nuclei across the N = 126 shell closure

    NASA Astrophysics Data System (ADS)

    Rodríguez-Guzmán, R.; Robledo, L. M.; Sharma, M. M.

    2015-06-01

    The quadrupole collectivity in Nd, Sm, Gd, Dy, Er, Yb, Hf and W nuclei with neutron numbers 122 ≤ N ≤ 156 is studied, both at the mean field level and beyond, using the Gogny energy density functional. Besides the robustness of the N = 126 neutron shell closure, it is shown that the onset of static deformations in those isotopic chains with increasing neutron number leads to an enhanced stability and further extends the corresponding two-neutron drip lines far beyond what could be expected from spherical calculations. Independence of the mean-field predictions with respect to the particular version of the Gogny energy density functional employed is demonstrated by comparing results based on the D1S and D1M parameter sets. Correlations beyond mean field are taken into account in the framework of the angular momentum projected generator coordinate method calculation. It is shown that N = 126 remains a robust neutron magic number when dynamical effects are included. The analysis of the collective wave functions, average deformations and excitation energies indicate that, with increasing neutron number, the zero-point quantum corrections lead to dominant prolate configurations in the 0{1/+}, 0{2/+}, 2{1/+} and 2{2/+} states of the studied nuclei. Moreover, those dynamical deformation effects provide an enhanced stability that further supports the mean-field predictions, corroborating a shift of the r-process path to higher neutron numbers. Beyond mean-field calculations provide a smaller shell gap at N = 126 than the mean-field one in good agreement with previous theoretical studies. However, the shell gap still remains strong enough in the two-neutron drip lines.

  1. 49 CFR 180.503 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    .... Interior heater system means a piping system located within the tank shell that uses a fluid medium to heat... the service equipment, may react to produce heat, gases, and/or pressure which could substantially....517(b). Safety system means one or more of the following: Thermal protection systems, insulation...

  2. 49 CFR 180.503 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    .... Interior heater system means a piping system located within the tank shell that uses a fluid medium to heat... the service equipment, may react to produce heat, gases, and/or pressure which could substantially....517(b). Safety system means one or more of the following: Thermal protection systems, insulation...

  3. 49 CFR 180.503 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    .... Interior heater system means a piping system located within the tank shell that uses a fluid medium to heat... the service equipment, may react to produce heat, gases, and/or pressure which could substantially....517(b). Safety system means one or more of the following: Thermal protection systems, insulation...

  4. DOT-105/111/112/114 Tank Cars Shell Cracking and Structural Integrity Assessment: Task Force Report

    DOT National Transportation Integrated Search

    1986-02-01

    In August 1985, the FRA Associate Administrator for Safety asked the DOT Transportation Systems Center to make a preliminary technical assessment of the adequacy of the manufacturer's inspection and repair procedures. The Center formed a task force f...

  5. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    Covered are: analytical laboratory operations (ALO) sample receipt and control, ALO data report/package preparation review and control, single shell tank (PST) project sample tracking system, sample receiving, analytical balances, duties and responsibilities of sample custodian, sample refrigerator temperature monitoring, security, assignment of staff responsibilities, sample storage, data reporting, and general requirements for glassware.

  6. NRC Waste Incidental to Reprocessing Program: Overview of Consultation and Monitoring Activities at the Idaho National Laboratory and the Savannah River Site - What We Have Learned - 12470

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Suber, Gregory

    2012-07-01

    In 2005 the U.S. Nuclear Regulatory Commission (NRC) began to implement a new set of responsibilities under the Ronald W. Reagan National Defense Authorization Act (NDAA) of Fiscal Year 2005. Section 3116 of the NDAA requires the U.S. Department of Energy (DOE) to consult with the NRC for certain non-high level waste determinations and also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2005, the NRC staff began consulting with DOE and completed reviews of draft waste determinations for salt waste at the Savannah River Site. In 2006, a second review was completed onmore » tank waste residuals including sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center Tank Farm at the Idaho National Laboratory. Monitoring Plans were developed for these activities and the NRC is actively monitoring disposal actions at both sites. NRC is currently in consultation with DOE on the F-Area Tank Farm closure and anticipates entering consultation on the H-Area Tank Farm at the Savannah River Site. This paper presents, from the NRC perspective, an overview of how the consultation and monitoring process has evolved since its conception in 2005. It addresses changes in methods and procedures used to collect and develop information used by the NRC in developing the technical evaluation report and monitoring plan under consultation and the implementation the plan under monitoring. It will address lessons learned and best practices developed throughout the process. The NDAA has presented significant challenges for the NRC and DOE. Past and current successes demonstrate that the NDAA can achieve its intended goal of facilitating tank closure at DOE legacy defense waste sites. The NRC believes many of the challenges in performing the WD reviews have been identified and addressed. Lessons learned have been collected and documented throughout the review process. Future success will be contingent on each agencies commitment to consistently apply the lessons learned and continue to create an open and collaborative work environment to maintain the process of continuous improvement. (authors)« less

  7. PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    JOHNSTON GA

    2008-01-15

    Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site.more » The 241-Z D&D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D&D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and Liability Act of 1980' (CERCLA). The project completed TPA Milestone M-083-032 to 'Complete those activities required by the 241-Z Treatment and Storage Unit's RCRA Closure Plan' four years and seven months ahead of this legally enforceable milestone. In addition, the project completed TPA Milestone M-083-042 to 'Complete transition and dismantlement of the 241-2 Waste Treatment Facility' four years and four months ahead of schedule. The project used an innovative approach in developing the project-specific RCRA closure plan to assure clear integration between the 241-Z RCRA closure activities and ongoing and future CERCLA actions at PFP. This approach provided a regulatory mechanism within the RCRA closure plan to place segments of the closure that were not practical to address at this time into future actions under CERCLA. Lessons learned from th is approach can be applied to other closure projects within the DOE Complex to control scope creep and mitigate risk. A paper on this topic, entitled 'Integration of the 241-Z Building D and D Under CERCLA with RCRA Closure at the PFP', was presented at the 2007 Waste Management Conference in Tucson, Arizona. In addition, techniques developed by the 241-Z D&D Project to control airborne contamination, clean the interior of the waste tanks, don and doff protective equipment, size-reduce plutonium-contaminated process piping, and mitigate thermal stress for the workers can be applied to other cleanup activities. The project-management team developed a strategy utilizing early characterization, targeted cleanup, and close coordination with PFP Criticality Engineering to significantly streamline the waste- handling costs associated with the project . The project schedule was structured to support an early transition to a criticality 'incredible' status for the 241-Z Facility. The cleanup work was sequenced and coordinated with project-specific criticality analysis to allow the fissile material waste being generated to be managed in a bulk fashion, instead of individual waste packages. This approach negated the need for real-time assay of individual waste packages, greatly improving the efficiency of the cleanup operation. The cleanup and stabilization of the 241-2 Liquid Effluent Treatment Facility reduced radiological risks to the environment and Hanford site workers. It was recognized as a success by regulatory agencies, the media, the DOE-client, and stakeholders. The 241-Z D&D Project demonstrated management excellence in adapting to significant changes in project direction, fostered a safety culture that amassed impressive results on this high-hazard job, maintained excellent communications with the client and stakeholders, and developed and implemented unique cleanup techniques.« less

  8. Development of Automotive Liquid Hydrogen Storage Systems

    NASA Astrophysics Data System (ADS)

    Krainz, G.; Bartlok, G.; Bodner, P.; Casapicola, P.; Doeller, Ch.; Hofmeister, F.; Neubacher, E.; Zieger, A.

    2004-06-01

    Liquid hydrogen (LH2) takes up less storage volume than gas but requires cryogenic vessels. State-of-the-art applications for passenger vehicles consist of double-wall cylindrical tanks that hold a hydrogen storage mass of up to 10 kg. The preferred shell material of the tanks is stainless steel, since it is very resistant against hydrogen brittleness and shows negligible hydrogen permeation. Therefore, the weight of the whole tank system including valves and heat exchanger is more than 100 kg. The space between the inner and outer vessel is mainly used for thermal super-insulation purposes. Several layers of insulation foils and high vacuums of 10-3 Pa reduce the heat entry. The support structures, which keep the inner tank in position to the outer tank, are made of materials with low thermal conductivity, e.g. glass or carbon fiber reinforced plastics. The remaining heat in-leak leads to a boil-off rate of 1 to 3 percent per day. Active cooling systems to increase the stand-by time before evaporation losses occur are being studied. Currently, the production of several liquid hydrogen tanks that fulfill the draft of regulations of the European Integrated Hydrogen Project (EIHP) is being prepared. New concepts of lightweight liquid hydrogen storage tanks will be investigated.

  9. Effects of cluster-shell competition and BCS-like pairing in 12C

    NASA Astrophysics Data System (ADS)

    Matsuno, H.; Itagaki, N.

    2017-12-01

    The antisymmetrized quasi-cluster model (AQCM) was proposed to describe α-cluster and jj-coupling shell models on the same footing. In this model, the cluster-shell transition is characterized by two parameters, R representing the distance between α clusters and Λ describing the breaking of α clusters, and the contribution of the spin-orbit interaction, very important in the jj-coupling shell model, can be taken into account starting with the α-cluster model wave function. Not only the closure configurations of the major shells but also the subclosure configurations of the jj-coupling shell model can be described starting with the α-cluster model wave functions; however, the particle-hole excitations of single particles have not been fully established yet. In this study we show that the framework of AQCM can be extended even to the states with the character of single-particle excitations. For ^{12}C, two-particle-two-hole (2p2h) excitations from the subclosure configuration of 0p_{3/2} corresponding to a BCS-like pairing are described, and these shell model states are coupled with the three α-cluster model wave functions. The correlation energy from the optimal configuration can be estimated not only in the cluster part but also in the shell model part. We try to pave the way to establish a generalized description of the nuclear structure.

  10. Many-molecule encapsulation by an icosahedral shell

    PubMed Central

    Perlmutter, Jason D; Mohajerani, Farzaneh; Hagan, Michael F

    2016-01-01

    We computationally study how an icosahedral shell assembles around hundreds of molecules. Such a process occurs during the formation of the carboxysome, a bacterial microcompartment that assembles around many copies of the enzymes ribulose 1,5-bisphosphate carboxylase/ oxygenase and carbonic anhydrase to facilitate carbon fixation in cyanobacteria. Our simulations identify two classes of assembly pathways leading to encapsulation of many-molecule cargoes. In one, shell assembly proceeds concomitantly with cargo condensation. In the other, the cargo first forms a dense globule; then, shell proteins assemble around and bud from the condensed cargo complex. Although the model is simplified, the simulations predict intermediates and closure mechanisms not accessible in experiments, and show how assembly can be tuned between these two pathways by modulating protein interactions. In addition to elucidating assembly pathways and critical control parameters for microcompartment assembly, our results may guide the reengineering of viruses as nanoreactors that self-assemble around their reactants. DOI: http://dx.doi.org/10.7554/eLife.14078.001 PMID:27166515

  11. Multifunctional polymer-capped mesoporous silica nanoparticles for pH-responsive targeted drug delivery.

    PubMed

    Niedermayer, Stefan; Weiss, Veronika; Herrmann, Annika; Schmidt, Alexandra; Datz, Stefan; Müller, Katharina; Wagner, Ernst; Bein, Thomas; Bräuchle, Christoph

    2015-05-07

    A highly stable modular platform, based on the sequential covalent attachment of different functionalities to the surface of core-shell mesoporous silica nanoparticles (MSNs) for targeted drug delivery is presented. A reversible pH-responsive cap system based on covalently attached poly(2-vinylpyridine) (PVP) was developed as drug release mechanism. Our platform offers (i) tuneable interactions and release kinetics with the cargo drug in the mesopores based on chemically orthogonal core-shell design, (ii) an extremely robust and reversible closure and release mechanism based on endosomal acidification of the covalently attached PVP polymer block, (iii) high colloidal stability due to a covalently coupled PEG shell, and (iv) the ability to covalently attach a wide variety of dyes, targeting ligands and other functionalities at the outer periphery of the PEG shell. The functionality of the system was demonstrated in several cell studies, showing pH-triggered release in the endosome, light-triggered endosomal escape with an on-board photosensitizer, and efficient folic acid-based cell targeting.

  12. Coulomb Excitation of n-rich nuclei along the N = 50 shell closure

    NASA Astrophysics Data System (ADS)

    Padilla-Rodal, E.; Galindo-Uribarri, A.; Batchelder, J. C.; Beene, J. R.; Bingham, C.; Brown, B. A.; Lagergren, K. B.; Mueller, P. E.; Radford, D. C.; Stracener, D. W.; Urrego-Blanco, J. P.; Varner, R. L.; Yu, C.-H.

    2008-04-01

    Recently, we have been investigating characteristics of nuclear states around the neutron-rich mass A=80 region [1]. Using the Radioactive Ion Beams (RIBs) produced at HRIBF, we have successfully measured the B(E2) values for ^78,80,82Ge , using Coulomb excitation in inverse kinematics. For the germanium isotopes, these data allow a study of the systematic trend between the subshell N= 40 and the N=50 shell. Using the same technique, we have measured the B(E2) value of various nuclei along the N=50 shell including the radioactive nucleus ^84Se. This value together with our previously measured ^82Ge, and the recent result on ^80Zn from ISOLDE [2] are providing basic experimental information needed for a better understanding of the neutron-rich nuclei around A˜80. We report the new results and compare with shell model calculations. [1] E. Padilla-Rodal et al., Phys. Rev. Lett. 94 (2005) 122501. [2] J. Van de Walle et al., Phys. Rev. Lett. 99 (2007) 142501.

  13. Project W-211 initial tank retrieval systems year 2000 compliance assessment project plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BUSSELL, J.H.

    1999-08-24

    This assessment describes the potential Year 2000 (Y2K) problems and describes the methods for achieving Y2K Compliance for Project W-211, Initial Tank Retrieval Systems (ITRS). The purpose of this assessment is to give an overview of the project. This document will not be updated and any dates contained in this document are estimates and may change. The scope of project W-211 is to provide systems for retrieval of radioactive wastes from ten double-shell tanks (DST). systems will be installed in tanks 102-AP, 104-AP, 105-AN, 104-AN, 102-AZ, 101-AW, 103-AN, 107-AN, 102-AY, and 102-SY. The current tank selection and sequence supports phasemore » I feed delivery to privatized processing plants. A detailed description of system dates, functions, interfaces, potential Y2K problems, and date resolutions can not be described since the project is in the definitive design phase. This assessment will describe the methods, protocols, and practices to assure that equipment and systems do not have Y2K problems.« less

  14. Electrical Resistivity Imaging Below Nuclear Waste Tank Farms at the Hanford Site

    NASA Astrophysics Data System (ADS)

    Rucker, D. F.; Levitt, M. T.

    2006-12-01

    The Hanford Site, a Department of Energy nuclear processing facility in eastern Washington, contains a complex series of radiological liquid waste disposal and storage facilities. The primary method of interim storage is the use of large single-shelled steel tanks with capacities of up to 3790 m3 (1 million gallons). The tanks are organized below ground into tank farms, with about 12 tanks per farm. The liquid waste within the tanks is primarily comprised of inorganic salts with minor constituents of heavy metals and radiological metals. The electrical properties of the radiological waste are significantly different to that of the surrounding engineered fill and native geologic formations. Over the past 60 years since the earliest tanks have been in use, many have been known to leak. An electrical resistivity survey was conducted within a tank farm to map the extent of the plumes resulting from historic leaks. Traditional surface-based electrical resistivity surveys resulted in unusable data due to the significant subsurface infrastructure that included a network of delivery pipes, wells, fences, and electrical discharge sources . HGI adapted the resistivity technique to include the site infrastructure as transceivers to augment data density and geometry. The results show a distribution of low resistivity values within the farm in areas that match known historic leak sites. The addition of site infrastructure as sensors demonstrates that the electrical resistivity technique can be used in highly industrial sites.

  15. Thermal modeling of tanks 241-AW-101 and 241-AN-104 with the TEMPEST code

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Antoniak, Z.I.; Recknagle, K.P.

    The TEMPEST code was exercised in a preliminary study of double-shell Tanks 241 -AW-101 and 241-AN-104 thermal behavior. The two-dimensional model used is derived from our earlier studies on heat transfer from Tank 241-SY-101. Several changes were made to the model to simulate the waste and conditions in 241-AW-101 and 241-AN-104. The nonconvective waste layer was assumed to be 254 cm (100 in.) thick for Tank 241-AW-101, and 381 cm (150 in.) in Tank 241-AN-104. The remaining waste was assumed, for each tank, to consist of a convective layer with a 7.6-cm (3-inch) crust on top. The waste heat loadsmore » for 241-AW-101 and 241-AN-104 were taken to be 10 kW (3.4E4 Btu/hr) and 12 kW (4.0E4 Btu/hr), respectively. Present model predictions of maximum and convecting waste temperatures are within 1.7{degrees}C (3{degrees}F) of those measured in Tanks 241-AW-101 and 241-AN-104. The difference between the predicted and measured temperature is comparable to the uncertainty of the measurement equipment. These models, therefore, are suitable for estimating the temperatures within the tanks in the event of changing air flows, waste levels, and/or waste configurations.« less

  16. Analysis report for 241-BY-104 Auger samples

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Beck, M.A.

    1994-11-10

    This report describes the analysis of the surface crust samples taken from single-shell tank (SST) BY-104, suspected of containing ferrocyanide wastes. This sampling and analysis will assist in ascertaining whether there is any hazard due to combustion (burning) or explosion of these solid wastes. These characteristics are important to future efforts to characterize the salt and sludge in this type of waste tank. This report will outline the methodology and detail the results of analyses performed during the characterization of this material. All analyses were performed by Westinghouse Hanford Company at the 222-S laboratory unless stated otherwise.

  17. 49 CFR 178.346-2 - Material and thickness of material.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Baffles When Used as Tank Reinforcement) Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel (SS), or Aluminum (AL)—Expressed in Decimals of an Inch After Forming Material... Thickness of Shell Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel...

  18. 49 CFR 178.346-2 - Material and thickness of material.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Baffles When Used as Tank Reinforcement) Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel (SS), or Aluminum (AL)—Expressed in Decimals of an Inch After Forming Material... Thickness of Shell Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel...

  19. 49 CFR 178.346-2 - Material and thickness of material.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Baffles When Used as Tank Reinforcement) Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel (SS), or Aluminum (AL)—Expressed in Decimals of an Inch After Forming Material... Thickness of Shell Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel...

  20. 49 CFR 178.346-2 - Material and thickness of material.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Baffles When Used as Tank Reinforcement) Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel (SS), or Aluminum (AL)—Expressed in Decimals of an Inch After Forming Material... Thickness of Shell Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel...

  1. Prospects for making carbide-free bainitic thick steel plate by means of controlled quenching : a first estimate

    DOT National Transportation Integrated Search

    1995-11-12

    Materials used for the shells of pressurized railroad tank cars : must be strong and inexpensive, yet also easily weldable and : resistant to fracture. The high costs associated with special alloy : compositions have made it difficult in the past to ...

  2. 46 CFR 151.15-10 - Cargo gauging devices.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ..., sonic depth gauge (without penetration of tank shell), pipe flow meter. (e) All gauging devices and... shall be designed for the pressure and temperature of the cargo in accordance with the requirements of... the operating temperatures, of not less than one-half inch in thickness and adequately protected by a...

  3. 46 CFR 151.15-10 - Cargo gauging devices.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ..., sonic depth gauge (without penetration of tank shell), pipe flow meter. (e) All gauging devices and... shall be designed for the pressure and temperature of the cargo in accordance with the requirements of... the operating temperatures, of not less than one-half inch in thickness and adequately protected by a...

  4. 46 CFR 151.15-10 - Cargo gauging devices.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ..., sonic depth gauge (without penetration of tank shell), pipe flow meter. (e) All gauging devices and... shall be designed for the pressure and temperature of the cargo in accordance with the requirements of... the operating temperatures, of not less than one-half inch in thickness and adequately protected by a...

  5. 46 CFR 151.15-10 - Cargo gauging devices.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ..., sonic depth gauge (without penetration of tank shell), pipe flow meter. (e) All gauging devices and... shall be designed for the pressure and temperature of the cargo in accordance with the requirements of... the operating temperatures, of not less than one-half inch in thickness and adequately protected by a...

  6. DOE Office of Scientific and Technical Information (OSTI.GOV)

    King, W. D.

    In order to appropriately model and predict the chemical integrity and performance of cementitious materials used for waste immobilization at the Savannah River Site (SRS), it is critical to understand the I-129 solubility and distribution within the tank farm. Iodine in radioactive waste and in environmental media is typically highly mobile and long lived. Iodine is ubiquitous in SRS tank waste and waste forms. The iodine is assumed to be soluble and present at low levels in Performance Assessments (PAs) for SRS Tank Farms, and is one of the dose drivers in the PAs for both the SRS Salt Disposalmore » Facility (SDF) and the H-Area Tank Farm (HTF). Analysis of tank waste samples is critical to understanding the Tank Farm iodine inventory and reducing disposal uncertainty. Higher than expected iodine levels have recently been observed in residual solids isolated from some SRS tanks prior to closure, indicating uncertainty regarding the chemical species involved. If the iodine inventory uncertainty is larger than anticipated, future work may be necessary to reduce the uncertainty. This memorandum satisfies a portion of the work scope identified in Task Plan SRNL-RP-2016-00651. A separate memorandum issued previously, reported historical unpublished I-129 data, a significant portion of which was below detectable analytical limits. This memorandum includes iodine and general chemical analysis results for six archived SRNL samples which were previously reported to have I-129 concentrations below detectable limits. Lower sample dilution factors were used for the current analyses in order to obtain concentrations above detection. The samples analyzed included surface and depth samples from SRS tanks 30, 32, and 39.« less

  7. Corrective Action Decision Document/Closure Report for Corrective Action Unit 560: Septic Systems, Nevada Test Site, Nevada, Revision 0

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Grant Evenson

    2010-04-01

    Corrective Action Unit 560 comprises seven corrective action sites (CASs): •03-51-01, Leach Pit •06-04-02, Septic Tank •06-05-03, Leach Pit •06-05-04, Leach Bed •06-59-03, Building CP-400 Septic System •06-59-04, Office Trailer Complex Sewage Pond •06-59-05, Control Point Septic System The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation for closure of CAU 560 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from October 7, 2008, through February 24, 2010, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 560: Septic Systems, Nevada Test Site, Nevada, and Recordmore » of Technical Change No. 1. The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective (DQO) process: •Determine whether contaminants of concern (COCs) are present. •If COCs are present, determine their nature and extent. •Provide sufficient information and data to complete appropriate corrective actions. The CAU 560 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels (FALs) established in this document. The following contaminants were determined to be present at concentrations exceeding their corresponding FALs: •No contamination exceeding the FALs was identified at CASs 03-51-01, 06-04-02, and 06-59-04. •The soil at the base of the leach pit chamber at CAS 06-05-03 contains arsenic above the FAL of 23 milligrams per kilogram (mg/kg) and polychlorinated biphenyl (PCBs) above the FAL of 0.74 mg/kg, confined vertically from a depth of approximately 5 to 20 feet (ft) below ground surface. The contamination is confined laterally to the walls of the leach pit chamber and leach rock. The contamination present at CAS 06-05-03 within the leach pit was not feasible to remove. •The surface and subsurface soils within and surrounding the septic system at CAS 06-05-04 contained PCB concentrations above the FAL of 0.74 mg/kg. The lateral and vertical extent of COCs was determined for this CAS. Contaminated soils were removed up to within 18 ft of the building. The remaining contamination is confined to subsurface soils adjacent to and beneath Building CP-162 and was not feasible to remove. •The solid materials within the septic tank and soils immediately surrounding the inlet end of the tank at CAS 06-59-03 contained benzo(a)pyrene above the FAL of 0.21 mg/kg. The soils, tank contents, and tank were removed. Materials remaining at this CAS do not contain contamination exceeding FALs. •The solids contained within the septic tank and inlet pipe at CAS 06-59-05 contained the following contaminants above their respective FALs: PCBs, arsenic, lead, benzo(a)pyrene, and pesticides. The tank and inlet pipe contents were removed. Materials remaining at this CAS do not contain contamination exceeding FALs. Therefore, the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) provides the following corrective action recommendations: •No further action for CASs 03-51-01, 06-04-02, and 06-59-04, as no contaminants of potential concern were present that exceed FALs. •Closure in place for CAS 06-05-03 under a corrective action with a use restriction (UR) for remaining PCB- and arsenic-impacted potential source material (PSM). The UR form and map have been filed in the NNSA/NSO Facility Information Management System, the FFACO database, and NNSA/NSO CAU/CAS files. •Closure in place for CAS 06-05-04 under a corrective action with a UR for remaining PCBs in soil adjacent to and beneath Building CP-162. The UR form and map have been filed in the NNSA/NSO Facility Information Management System, the FFACO database, and NNSA/NSO CAU/CAS files. •No further action for CAS 06-59-03, as the COC of benzo(a)pyrene in soil and PSM have been removed. •No further action for CAS 06-59-05, as the COCs in PSM within the septic tank and inlet piping have been removed and the tank was filled with concrete.« less

  8. Effects of hydrated lime on radionuclides stabilization of Hanford tank residual waste.

    PubMed

    Wang, Guohui; Um, Wooyong; Cantrell, Kirk J; Snyder, Michelle M V; Bowden, Mark E; Triplett, Mark B; Buck, Edgar C

    2017-10-01

    Chemical stabilization of tank residual waste is part of a Hanford Site tank closure strategy to reduce overall risk levels to human health and the environment. In this study, a set of column leaching experiments using tank C-104 residual waste were conducted to evaluate the leachability of uranium (U) and technetium (Tc) where grout and hydrated lime were applied as chemical stabilizing agents. The experiments were designed to simulate future scenarios where meteoric water infiltrates through the vadose zones into the interior of the tank filled with layers of grout or hydrated lime, and then contacts the residual waste. Effluent concentrations of U and Tc were monitored and compared among three different packing columns (waste only, waste + grout, and waste + grout + hydrated lime). Geochemical modeling of the effluent compositions was conducted to determine saturation indices of uranium solid phases that could control the solubility of uranium. The results indicate that addition of hydrated lime strongly stabilized the uranium through transforming uranium to a highly insoluble calcium uranate (CaUO 4 ) or similar phase, whereas no significant stabilization effect of grout or hydrated lime was observed on Tc leachability. The result implies that hydrated lime could be a great candidate for stabilizing Hanford tank residual wastes where uranium is one of the main concerns. Published by Elsevier Ltd.

  9. Mussel Shell Evaluation as Bioindicator For Heavy Metals

    NASA Astrophysics Data System (ADS)

    Andrello, Avacir Casanova; Lopes, Fábio; Galvão, Tiago Dutra

    2010-05-01

    Recently, in Brazil, it has appeared a new and unusual "plague" in lazer and commercial fishing. It is caused by the parasitic larval phase of certain native bivalve mollusks of fresh water known as "Naiades" and its involves the presence of big bivalve of fresh water, mainly Anodontites trapesialis, in the tanks and dams of the fish creation. These bivalve mollusks belong to the Unionoida Order, Mycetopodidae Family. The objective of the present work was to analyze the shells of these mollusks to verify the possibility of use as bioindicators for heavy metals in freshwater. The mollusks shells were collected in a commercial fishing at Londrina-PR. A qualitative analysis was made to determine the chemical composition of the shells and verify a possible correlation with existent heavy metals in the aquatic environment. In the inner part of the shells were identified the elements Ca, P, Fe, Mn and Sr and in the outer part were identified Ca, P, Fe, Mn, Sr and Cu. The Ca ratio of the outer part by inner part of the analyzed shells is around of 1, as expected, because Ca is the main compound of mollusks shells. The ratio of P, Fe, Mn, and Sr to the Ca were constant in all analyzed shells, being close to 0.015. The ratio Cu/Ca varied among the shells, showing that this mollusk is sensitive to concentration of this element in the aquatic environment.

  10. Analysis of stress-strain state of RVS-20000 tank under non-axisymmetric wind load action

    NASA Astrophysics Data System (ADS)

    Tarasenko, A. A.; Chepur, P. V.; Gruchenkova, A. A.

    2018-03-01

    In modern reference documentation, it is customary to set the wind load as uniformly distributed pressure over the area and wall of the tank. Experimental studies in the wind tunnel for various designs of the VST carried out under the guidance of professors V.E. Shutov and V.L. Berezin showed that when wind acts on the shell, there occur rarefaction zones, which must be taken into account during strain analysis of tanks. A finite-element model of the RVS-20000 tank was developed to calculate the wind load in a non-axisymmetric setting, taking into account the array of differentiated values of the aerodynamic coefficient. The distribution of stresses and strains of RVS-20000 metal structures under the effect of unevenly distributed wind pressure with a normal value of Qn = 600 Pa is obtained. It is established that the greatest strains and stresses occur at the interface of the wall and the fixed floor.

  11. Corrosion probe. Innovative technology summary report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    Over 253 million liters of high-level waste (HLW) generated from plutonium production is stored in mild steel tanks at the Department of Energy (DOE) Hanford Site. Corrosion monitoring of double-shell storage tanks (DSTs) is currently performed at Hanford using a combination of process knowledge and tank waste sampling and analysis. Available technologies for corrosion monitoring have progressed to a point where it is feasible to monitor and control corrosion by on-line monitoring of the corrosion process and direct addition of corrosion inhibitors. The electrochemical noise (EN) technique deploys EN-based corrosion monitoring probes into storage tanks. This system is specifically designedmore » to measure corrosion rates and detect changes in waste chemistry that trigger the onset of pitting and cracking. These on-line probes can determine whether additional corrosion inhibitor is required and, if so, provide information on an effective end point to the corrosion inhibitor addition procedure. This report describes the technology, its performance, its application, costs, regulatory and policy issues, and lessons learned.« less

  12. 242-A Evaporator quality assurance plan. Revision 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Basra, T.S.

    1995-05-04

    The purpose of this quality assurance project plan (Plan) is to provide requirements for activities pertaining to sampling, shipping, and analyses associated with candidate feed tank samples for the 242-A Evaporator project. The purpose of the 242-A Evaporator project is to reduce the volume of aqueous waste in the Double Shell Tank (DST) System and will result in considerable savings to the disposal of mixed waste. The 242-A Evaporator feed stream originates from DSTs identified as candidate feed tanks. The 242-A Evaporator reduces the volume of aqueous waste contained in DSTs by boiling off water and sending the condensate (calledmore » process condensate) to the Liquid Effluent Retention Facility (LEPF) storage basin where it is stored prior to treatment in the Effluent Treatment Facility (ETF). The objective of this quality assurance project plan is to provide the planning, implementation, and assessment of sample collection and analysis, data issuance, and validation activities for the candidate feed tanks.« less

  13. One System Integrated Project Team: Retrieval And Delivery Of The Hanford Tank Wastes For Vitrification In The Waste Treatment Plant

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Harp, Benton J.; Kacich, Richard M.; Skwarek, Raymond J.

    The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enablemore » the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank wastes and for building and operating the WTP. The tank wastes are the result of Hanford's nearly fifty (50) years of plutonium production. In the intervening years, waste characteristics have been increasingly better understood. However, waste characteristics that are uncertain and will remain as such represent a significant technical challenge in terms of retrieval, transport, and treatment, as well as for design and construction ofWTP. What also is clear is that the longer the waste remains in the tanks, the greater the risk to the environment and the people of the Pacific Northwest. The goal of both projects - tank operations and waste treatment - is to diminish the risks posed by the waste in the tanks at the earliest possible date. About two hundred (200) WTP and TOC employees comprise the IPT. Individual work groups within One System include Technical, Project Integration & Controls, Front-End Design & Project Definition, Commissioning, Nuclear Safety & Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH&QA). Additional functions and team members will be added as the WTP approaches the operational phase. The team has undertaken several initiatives since its formation to collaborate on issues: (1) alternate scenarios for delivery of wastes from the tank farms to WTP; (2) improvements in managing Interface Control Documents; (3) coordination on various technical issues, including the Defense Nuclear Facilities Nuclear Safety Board's Recommendation 2010-2; (4) deployment of the SmartPlant Foundation-configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan.« less

  14. Probable alpha and 14C cluster emission from hyper Ac nuclei

    NASA Astrophysics Data System (ADS)

    Santhosh, K. P.

    2013-10-01

    A systematic study on the probability for the emission of 4He and 14C cluster from hyper {Λ/207-234}Ac and non-strange normal 207-234Ac nuclei are performed for the first time using our fission model, the Coulomb and proximity potential model (CPPM). The predicted half lives show that hyper {Λ/207-234}Ac nuclei are unstable against 4He emission and 14C emission from hyper {Λ/217-228}Ac are favorable for measurement. Our study also show that hyper {Λ/207-234}Ac are stable against hyper {Λ/4}He and {Λ/14}C emission. The role of neutron shell closure ( N = 126) in hyper {Λ/214}Fr daughter and role of proton/neutron shell closure ( Z ≈ 82, N = 126) in hyper {Λ/210}Bi daughter are also revealed. As hyper-nuclei decays to normal nuclei by mesonic/non-mesonic decay and since most of the predicted half lives for 4He and 14C emission from normal Ac nuclei are favourable for measurement, we presume that alpha and 14C cluster emission from hyper Ac nuclei can be detected in laboratory in a cascade (two-step) process.

  15. 49 CFR 178.346-2 - Material and thickness of material.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... Bulkheads and Baffles When Used as Tank Reinforcement) Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel (SS), or Aluminum (AL)—Expressed in Decimals of an Inch After Forming... Thickness of Shell Using Mild Steel (MS), High Strength Low Alloy Steel (HSLA), Austenitic Stainless Steel...

  16. 49 CFR 177.837 - Class 3 materials.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... through an open filling hole, one end of a bond wire shall be connected to the stationary system piping or integrally connected steel framing, and the other end to the shell of the cargo tank to provide a continuous... after the last filling hole has been closed. Additional bond wires are not needed around All-Metal...

  17. 49 CFR 177.837 - Class 3 materials.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... through an open filling hole, one end of a bond wire shall be connected to the stationary system piping or integrally connected steel framing, and the other end to the shell of the cargo tank to provide a continuous... after the last filling hole has been closed. Additional bond wires are not needed around All-Metal...

  18. A study of fluid-structure problems

    NASA Astrophysics Data System (ADS)

    Lam, Dennis Kang-Por

    The stability of structures with and without fluid load is investigated. A method is developed for determining the fluid load in terms of added structural mass. Finite element methods are employed to study the buckling of a cylindrical shell under axial compression and liquid storage tanks under hydrodynamic load. Both linear and nonlinear analyses are performed. Diamond modes are found to be the possible postbuckling shapes of the cylindrical shell. Local buckling including elephant-foot buckle and diamond buckle are found for the liquid storage tank models. Comparison between the linear and nonlinear results indicates a substantial difference in buckling mode shapes, though the buckling loads are close to each other. The method for determining the hydrodynamic mass is applied to the impeller stage of a centrifugal pump. The method is based on a linear perturbation technique which assumes that the disturbance in the flow boundaries and velocities caused by the motion of the structure is small. A potential method is used to estimate the velocity flow field. The hydrodynamic mass is then obtained by calculating the total force which results from the pressure induced by a perturbation of the structure.

  19. 1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fort, J.A.; Bamberger, J.A.; Bates, J.M.

    1993-01-01

    Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surface of the supernatant liquid. The supernatant is more commonly referred to as the convectivemore » layer and the slurry as the non-convective layer. Accumulation of gas (partly hydrogen) in the non-convective layer is suspected to be the key mechanism behind the gas burp phenomena, and several mitigation schemes are being developed to encourage a more uniform gas release rate (Benegas 1992). To support the full-scale hydraulic mitigation test, scaled experiments were performed to satisfy two objectives: 1. provide an experimental database for numerical- model validation; 2. establish operating parameter values required to mobilize the settled solids and maintain the solids in suspension.« less

  20. 1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation. Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fort, J.A.; Bamberger, J.A.; Bates, J.M.

    1993-01-01

    Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surface of the supernatant liquid. The supernatant is more commonly referred to as the convectivemore » layer and the slurry as the non-convective layer. Accumulation of gas (partly hydrogen) in the non-convective layer is suspected to be the key mechanism behind the gas burp phenomena, and several mitigation schemes are being developed to encourage a more uniform gas release rate (Benegas 1992). To support the full-scale hydraulic mitigation test, scaled experiments were performed to satisfy two objectives: 1. provide an experimental database for numerical- model validation; 2. establish operating parameter values required to mobilize the settled solids and maintain the solids in suspension.« less

  1. Systematics of first 2+ state g factors around mass 80

    NASA Astrophysics Data System (ADS)

    Mertzimekis, T. J.; Stuchbery, A. E.; Benczer-Koller, N.; Taylor, M. J.

    2003-11-01

    The systematics of the first 2+ state g factors in the mass 80 region are investigated in terms of an IBM-II analysis, a pairing-corrected geometrical model, and a shell-model approach. Subshell closure effects at N=38 and overall trends were examined using IBM-II. A large-space shell-model calculation was successful in describing the behavior for N=48 and N=50 nuclei, where single-particle features are prominent. A schematic truncated-space calculation was applied to the lighter isotopes. The variations of the effective boson g factors are discussed in connection with the role of F -spin breaking, and comparisons are made between the mass 80 and mass 180 regions.

  2. B Plant Complex preclosure work plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    ADLER, J.G.

    1999-02-02

    This preclosure work plan describes the condition of the dangerous waste treatment storage, and/or disposal (TSD) unit after completion of the B Plant Complex decommissioning Transition Phase preclosure activities. This description includes waste characteristics, waste types, locations, and associated hazards. The goal to be met by the Transition Phase preclosure activities is to place the TSD unit into a safe and environmentally secure condition for the long-term Surveillance and Maintenance (S&M) Phase of the facility decommissioning process. This preclosure work plan has been prepared in accordance with Section 8.0 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement)more » (Ecology et al. 1996). The preclosure work plan is one of three critical Transition Phase documents, the other two being: B Plant End Points Document (WHC-SD-WM-TPP-054) and B Plant S&M plan. These documents are prepared by the U.S. Department of Energy, Richland Operations Office (DOE-RL) and its contractors with the involvement of Washington State Department of Ecology (Ecology). The tanks and vessels addressed by this preclosure work plan are limited to those tanks end vessels included on the B Plant Complex Part A, Form 3, Permit Application (DOE/RL-88-21). The criteria for determining which tanks or vessels are in the Part A, Form 3, are discussed in the following. The closure plan for the TSD unit will not be prepared until the Disposition Phase of the facility decommissioning process is initiated, which follows the long-term S&M Phase. Final closure will occur during the Disposition Phase of the facility decommissioning process. The Waste Encapsulation Storage Facility (WESF) is excluded from the scope of this preclosure work plan.« less

  3. In-Tank Elutriation Test Report And Independent Assessment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Burns, H. H.; Adamson, D. J.; Qureshi, Z. H.

    2011-04-13

    The Department of Energy (DOE) Office of Environmental Management (EM) funded Technology Development and Deployment (TDD) to solve technical problems associated with waste tank closure for sites such as Hanford Site and Savannah River Site (SRS). One of the tasks supported by this funding at Savannah River National Laboratory (SRNL) and Pacific Northwest Laboratory (PNNL) was In-Tank Elutriation. Elutriation is the process whereby physical separation occurs based on particle size and density. This report satisfies the first phase of Task WP_1.3.1.1 In-Tank Elutriation, which is to assess the feasibility of this method of separation in waste tanks at Hanford Sitemore » and SRS. This report includes an analysis of scoping tests performed in the Engineering Development Laboratory of SRNL, analysis of Hanford's inadvertent elutriation, the viability of separation methods such as elutriation and hydrocyclones and recommendations for a path forward. This report will demonstrate that the retrieval of Hanford salt waste tank S-112 very successfully decreased the tank's inventories of radionuclides. Analyses of samples collected from the tank showed that concentrations of the major radionuclides Cs-136 and Sr-90 were decreased by factors of 250 and 6 and their total curie tank inventories decreased by factors of 60,000 and 2000. The total tank curie loading decreased from 300,000 Ci to 55 Ci. The remaining heel was nearly all innocuous gibbsite, Al(OH){sub 3}. However, in the process of tank retrieval approximately 85% of the tank gibbsite was also removed. Significant amounts of money and processing time could be saved if more gibbsite could be left in tanks while still removing nearly all of the radionuclides. There were factors which helped to make the elutriation of Tank S-112 successful which would not necessarily be present in all salt tanks. 1. The gibbsite particles in the tank were surprisingly large, as much as 200 {micro}m. The gibbsite crystals had probably grown in size over a period of decades. 2. The radionuclides were apparently either in the form of soluble compounds, like cesium, or micrometer sized particles of actinide oxides or hydroxides. 3. After the initial tank retrieval the tank contained cobble which is not conducive to elutriation. Only after the tank contents were treated with thousands of gallons of 50 wt% caustic, were the solids converted to sand which is compatible with elutriation. Discussions between SRNL and PNNL resulted in plans to test elutriation in two phases; in Phase 1 particles would be separated by differences in settling velocity in an existing scaled tank with its associated hardware and in Phase 2 additional hardware, such as a hydrocyclone, would be added downstream to separate slow settling partciels from liquid. Phase 1 of in-tank elutriation was tested for Proof of Principle in theEngineering Development Laboratory of SRNL in a 41" diameter, 87 gallon tank. The tank had been previously used as a 1/22 scale model of Hanford Waste Tank AY-102. The objective of the testing was to determine which tank operating parameters achieved the best separation between fast- and slow-settling particles. For Phase 1 testing a simulated waste tank supernatant, slow-settling particles and fast-settling particles were loaded to the scaled tank. Because this was a Proof of Principle test, readily available solids particles were used that represented fast-settling and slow-settling particles. The tank contents were agitated using rotating mixer jet pumps (MJP) which suspended solids while liquids and solids were drawn out of the tank with a suction tube. The goal was to determine the optimum hydraulic operating conditions to achieve clean separation in which the residual solids in the tank were nearly all fast-settling particles and the solids transferred out of the tank were nearly all slow-settling particles. Tests were conducted at different pump jet velocities, suction tube diameters and suction tube elevations. Testing revealed that the most important variable was jet velocity which translates to a downstream fluid velocity in the vicinity of the suction tube which can suspend particles and potentially allow their removal from the tank. The optimum jet velocity in the vicinity of the sucti9on tube was between 1.5 and 2 ft/s (4-5 gpm). During testing at lower velocities a significant amount of slow-settling particles remained in the tank. At higher velocities a significant amount of fast-settling particles were elutriated from the tank. It should be noted that this range of velocities is appropriate for this particular geometry and particles. However, the principle of In-Tank Elutriation was proved. In-tank elutriation has the potential to save much money in tank closure. However, more work, both analytical and experimental, must be done before an improved version of the process could be applied to actual waste tanks. It is recommended that testing with more prototypic simulants be conducted. Also, scale-up criteria for elutriation and the resulting size of pilot scale test equipment require investigation during future research. In addition, it is recommended that the use of hydrocyclones be pursued in Phase 2 testing. Hydrocyclones are a precise and efficient separation tool that are frequently used in industry.« less

  4. DOE Office of Scientific and Technical Information (OSTI.GOV)

    G. N. Doyle

    Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in themore » early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.« less

  5. Damage detection in hazardous waste storage tank bottoms using ultrasonic guided waves

    NASA Astrophysics Data System (ADS)

    Cobb, Adam C.; Fisher, Jay L.; Bartlett, Jonathan D.; Earnest, Douglas R.

    2018-04-01

    Detecting damage in storage tanks is performed commercially using a variety of techniques. The most commonly used inspection technologies are magnetic flux leakage (MFL), conventional ultrasonic testing (UT), and leak testing. MFL and UT typically involve manual or robotic scanning of a sensor along the metal surfaces to detect cracks or corrosion wall loss. For inspection of the tank bottom, however, the storage tank is commonly emptied to allow interior access for the inspection system. While there are costs associated with emptying a storage tank for inspection that can be justified in some scenarios, there are situations where emptying the tank is impractical. Robotic, submersible systems have been developed for inspecting these tanks, but there are some storage tanks whose contents are so hazardous that even the use of these systems is untenable. Thus, there is a need to develop an inspection strategy that does not require emptying the tank or insertion of the sensor system into the tank. This paper presents a guided wave system for inspecting the bottom of double-shelled storage tanks (DSTs), with the sensor located on the exterior side-wall of the vessel. The sensor used is an electromagnetic acoustic transducer (EMAT) that generates and receives shear-horizontal guided plate waves using magnetostriction principles. The system operates by scanning the sensor around the circumference of the storage tank and sending guided waves into the tank bottom at regular intervals. The data from multiple locations are combined using the synthetic aperture focusing technique (SAFT) to create a color-mapped image of the vessel thickness changes. The target application of the system described is inspection of DSTs located at the Hanford site, which are million-gallon vessels used to store nuclear waste. Other vessels whose exterior walls are accessible would also be candidates for inspection using the described approach. Experimental results are shown from tests on multiple mockups of the DSTs being used to develop the sensor system.

  6. Curvature-Induced Instabilities of Shells

    NASA Astrophysics Data System (ADS)

    Pezzulla, Matteo; Stoop, Norbert; Steranka, Mark P.; Bade, Abdikhalaq J.; Holmes, Douglas P.

    2018-01-01

    Induced by proteins within the cell membrane or by differential growth, heating, or swelling, spontaneous curvatures can drastically affect the morphology of thin bodies and induce mechanical instabilities. Yet, the interaction of spontaneous curvature and geometric frustration in curved shells remains poorly understood. Via a combination of precision experiments on elastomeric spherical shells, simulations, and theory, we show how a spontaneous curvature induces a rotational symmetry-breaking buckling as well as a snapping instability reminiscent of the Venus fly trap closure mechanism. The instabilities, and their dependence on geometry, are rationalized by reducing the spontaneous curvature to an effective mechanical load. This formulation reveals a combined pressurelike term in the bulk and a torquelike term in the boundary, allowing scaling predictions for the instabilities that are in excellent agreement with experiments and simulations. Moreover, the effective pressure analogy suggests a curvature-induced subcritical buckling in closed shells. We determine the critical buckling curvature via a linear stability analysis that accounts for the combination of residual membrane and bending stresses. The prominent role of geometry in our findings suggests the applicability of the results over a wide range of scales.

  7. Cost Effectiveness Study of Wastewater Management Systems for Selected U.S. Coast Guard Vessels. Volume 3. Installation Analysis. Part 5. White Sage (133 Feet)

    DTIC Science & Technology

    1977-02-01

    located in a wire mesh enclosure in the center of the hold. The cargo boom hydraulic tank is located in the port aft corner of the hold. The rcmainder...2, there may be minor modifications required to the shelving on the starboard side (along the I shell of the vessel) and the wire mesh eculosure...along the shell of the vessel) and the wire mesh enclosure for the ship’s dry stores on the centerline of the vessel (between Frames 9 and 10). 24 NOW oI

  8. Removal of 137Cs from Dissolved Hanford Tank Saltcake by Treatment with IE-911

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rapko, Brian M.; Sinkov, Serguei I.; Levitskaia, Tatiana G.

    2003-04-10

    The U.S. Department of Energy's Richland Operations Office plans to accelerate the cleanup of the Hanford Site. Testing new technology for the accelerated cleanup will require dissolved saltcake from single-shell tanks. However, the 137Cs will need to be removed from the saltcake to alleviate radiation hazards. A saltcake composite constructed from archived samples from Hanford Single Shell Tanks 241-S-101, 241-S-109, 241-S-110, 241-S-111, 241-U-106, and 241-U-109 was dissolved in water, adjusted to 5 M Na, and transferred from the 222-S building to the Radiochemical Processing Laboratory (RPL). At the RPL, the approximately 5.5 liters of solution was passed through a 0.2-micronmore » polyethersulfone filter, collected, and homogenized. The filtered solution then was passed through an ion exchange column containing approximately 150 mL IONSIV IE-911, an engineered form of crystalline silicotitanate available from UOP, at approximately 200 mL/hour in a continuous operation until all of the feed solution had been run through the column. An analysis of the 137Cs concentrations in the initial feed solution and combined column effluent indicates that> 99.999 percent of the Cs in the feed solution was removed by this operation. This report describes the Cs-depletion operations together with a partial analysis of the as-received solution and a more extensive characterization of the Cs-depleted solution.« less

  9. Interim Basis for PCB Sampling and Analyses

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BANNING, D.L.

    2001-01-18

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the US. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposalmore » approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QAlG4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1 A, Vol. IV, Section 4.16 (Banning 1999).« less

  10. Interim Basis for PCB Sampling and Analyses

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BANNING, D.L.

    2001-03-20

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the U.S. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposalmore » approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QA/G4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1A, Vol. IV, Section 4.16 (Banning 1999).« less

  11. 86. ARAIII. GCRE reactor building (ARA608) showing mechanical loop pit ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    86. ARA-III. GCRE reactor building (ARA-608) showing mechanical loop pit after building shell had been erected. Beyond pit are demineralized water surge tank and heat exchanger. Camera facing northeast. December 22, 1958. Ineel photo no. 58-6427. Photographer: Ken Mansfield. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  12. 49 CFR 178.345-8 - Accident damage protection.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... accidental loss of lading. The device must break at no more than 70 percent of the load that would be... major radius of the tank shell. The device must break at no more than 70 percent of the load that would... requirements of this section and the applicable individual specification to minimize the potential for the loss...

  13. 49 CFR 178.345-8 - Accident damage protection.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... accidental loss of lading. The device must break at no more than 70 percent of the load that would be... major radius of the tank shell. The device must break at no more than 70 percent of the load that would... requirements of this section and the applicable individual specification to minimize the potential for the loss...

  14. 49 CFR 178.345-8 - Accident damage protection.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... accidental loss of lading. The device must break at no more than 70 percent of the load that would be... major radius of the tank shell. The device must break at no more than 70 percent of the load that would... requirements of this section and the applicable individual specification to minimize the potential for the loss...

  15. 49 CFR 178.345-8 - Accident damage protection.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... accidental loss of lading. The device must break at no more than 70 percent of the load that would be... major radius of the tank shell. The device must break at no more than 70 percent of the load that would... requirements of this section and the applicable individual specification to minimize the potential for the loss...

  16. 29 CFR 1910.106 - Flammable and combustible liquids.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... venting devices shall be not less than that derived from Table H-10 except as provided in subdivision (e... 30 feet above grade of the exposed shell area of a vertical tank. Table H-10—Wetted Area Versus Cubic... determined in accordance with Table H-10, except that when the exposed wetted area of the surface is greater...

  17. Degradation and Reinforcement of Industrial Gas Tank Support Structures. Thirty-Year Long Monitoring

    NASA Astrophysics Data System (ADS)

    Krentowski, Janusz R.; Knyziak, Piotr

    2017-10-01

    An analysis of reinforced concrete supporting structures of more than a dozen liquid gas tanks mounted on tower support structures located at different sites on Poland’s territory is presented. Stability testing of the degraded structures was carried out over a period of 30 years and pointed out significant defects that prevented safe operation of the tanks containing hazardous medium. Analysing complex stress states, as well as displacements of shell structure components, the authors developed a concept of strengthening the structures. Initial repair works, which had been carried out without proper supervision, failed to meet the mandatory requirements and were not compatible with the original design solutions. After several years of operation of the reinforced structures, their degradation states were assessed again. The next stage of repair works was carried out under the supervision of the authors together with authorized representatives of the investors.

  18. Solar heating and hot water system installed at Saint Louis, Missouri

    NASA Technical Reports Server (NTRS)

    1980-01-01

    The solar heating and hot water system installed at the William Tao & Associates, Inc., office building in St. Louis, Missouri is described, including maintenance and construction problems, final drawings, system requirements, and manufacturer's component data. The solar system was designed to provide 50 percent of the hot water requirements and 45 percent of the space heating needs for a 900 sq ft office space and drafting room. The solar facility has 252 sq ft of glass tube concentrator collectors and a 1000 gallon steel storage tank buried below a concrete slab floor. Freeze protection is provided by a propylene glycol/water mixture in the collector loop. The collectors are roof mounted on a variable tilt array which is adjusted seasonally and is connected to the solar thermal storage tank by a tube-in-shell heat exchanger. Incoming city water is preheated through the solar energy thermal storage tank.

  19. Using Encapsulated Phase Change Material in Thermal Energy Storage for Baseload Concentrating Solar Power (EPCM-TES)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mathur, Anoop

    2013-12-15

    Terrafore successfully demonstrated and optimized the manufacturing of capsules containing phase-changing inorganic salts. The phase change was used to store thermal energy collected from a concentrating solar-power plant as latent heat. This latent heat, in addition to sensible heat increased the energy density (energy stored per unit weight of salt) by over 50%, thus requiring 40% less salt and over 60% less capsule container. Therefore, the cost to store high-temperature thermal energy collected in a concentrating solar power plant will be reduced by almost 40% or more, as compared to conventional two-tank, sensible-only storage systems. The cost for thermal energymore » storage (TES) system is expected to achieve the Sun Shot goal of $15 per kWh(t). Costs associated with poor heat-transfer in phase change materials (PCM) were also eliminated. Although thermal energy storage that relies on the latent heat of fusion of PCM improves energy density by as much as 50%, upon energy discharge the salt freezes and builds on the heat transfer surfaces. Since these salts have low thermal conductivity, large heat-transfer areas, or larger conventional heat-exchangers are needed, which increases costs. By encapsulating PCM in small capsules we have increased the heat transfer area per unit volume of salt and brought the heat transfer fluid in direct contact with the capsules. These two improvements have increased the heat transfer coefficient and boosted heat transfer. The program was successful in overcoming the phenomenon of melt expansion in the capsules, which requires the creation of open volume in the capsules or shell to allow for expansion of the molten salt on melting and is heated above its melting point to 550°C. Under contract with the Department of Energy, Terrafore Inc. and Southwest Research Institute, developed innovative method(s) to economically create the open volume or void in the capsule. One method consists of using a sacrificial polymer coating as the middle layer between the salt prill and the shell material. The selected polymer decomposes at temperatures below the melting point of the salt and forms gases which escape through the pores in the capsule shell thus leaving a void in the capsule. We have demonstrated the process with a commonly used inorganic nitrate salt in a low-cost shell material that can withstand over 10,000 high-temperature thermal cycles, or a thirty-year or greater life in a solar plant. The shell used to encapsulate the salt was demonstrated to be compatible with molten salt heat transfer fluid typically used in CSP plants to temperatures up to 600 °C. The above findings have led to the concept of a cascaded arrangement. Salts with different melting points can be encapsulated using the same recipe and contained in a packed bed by cascading the salt melting at higher melting point at the top over the salt melting at lower melting point towards the bottom of the tank. This cascaded energy storage is required to effectively transfer the sensible heat collected in heat transfer fluids between the operating temperatures and utilize the latent heat of fusion in the salts inside the capsule. Mathematical models indicate that over 90% of the salts will undergo phase change by using three salts in equal proportion. The salts are selected such that the salt at the top of the tank melts at about 15°C below the high operating-temperature, and the salt at the bottom of the tank melts 15°C above the low operating-temperature. The salt in the middle of tank melts in-between the operating temperature of the heat transfer fluid. A cascaded arrangement leads to the capture of 90% of the latent-heat of fusion of salts and their sensible heats. Thus the energy density is increased by over 50% from a sensible-only, two-tank thermal energy storage. Furthermore, the Terrafore cascaded storage method requires only one tank as opposed to the two-tanks used in sensible heat storage. Since heat is transferred from the heat transfer fluid by direct contact with capsules, external heat-exchangers are not required for charging storage. Thus, the cost of the thermal storage system is reduced due to smaller containers and less salt. The optimum salt proportions, their melting temperature and the number of salts in the cascade are determined by raw materials costs and the mathematical model. We estimate the processing cost of the encapsulation to be low, where the major cost of the capsule will be the cost of the phase-change salt(s). Our economic analyses show that the cost of EPCM-TES is about $17.98 per kWh(t), which is about 40% lower than the $28.36 per kWh(t) for a two-tank sensible heat TES for a large scale CSP-TES design. Finally, additional improvements in the heat-transfer fluids, currently in development elsewhere will further improve the energy density to achieve the SunShot goal of $15 per kWh(t).« less

  20. Calculating Depth of Closure Using WIS Hindcast Data

    DTIC Science & Technology

    2016-03-01

    revised the Hallermeier (1978, 1981) equations using data from the Duck , NC, U.S. Army Corps of Engineers (USACE) Field Research Facility. Many studies ... Study (WIS) hindcast stations along the United States coastlines. The results summarized in this CHETN are available in the form of a spreadsheet on...theoretical definition of DOC came from a study by Hallermeier (1978, 1981) using wave tank and field data. Initially, the DOC was related to the critical

  1. NUCLEAR CLEANUP: Progress Made at Rocky Flats, but Closure by 2006 Is Unlikely, and Costs May Increase

    DTIC Science & Technology

    2001-02-01

    liquids or residues from process pipes and tanks. The contractor also dismantled plutonium - processing furnaces, stripped out contaminated process...Soil Cleanup Levels on the Scope and Cost of the 903 Pad Cleanup 30 Figures Figure 1: Workers in Protective Clothing Handling Plutonium - Contaminated ...activities—shipping nuclear materials such as plutonium - contaminated metals and powders—is expected to be completed in 2002. Another activity

  2. NRC Perspectives on Waste Incidental to Reprocessing Consultations and Monitoring - 13398

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    McKenney, Christepher A.; Suber, Gregory F.; Felsher, Harry D.

    2013-07-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities inmore » the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but largely NRC's role will change from doing both consultation and monitoring to being focused on monitoring activities within NDAA. DOE has identified other activities at the Hanford Nuclear Reservation that would continue consultation activities but outside of the NDAA in the future. During the past seven years of consultations and monitoring a number of lessons learned about the process, communication issues, and technical guidance have been identified. With the change in focus from reviewing initial performance assessments and draft waste determinations to long-term monitoring (e.g., individual waste tank closure, at F Tank Farm or complete tank farm closure at INTEC expected in the near future), the NRC is going to revise and update its guidance over the next few years to reflect the lessons learned and the change in focus. In addition to the lessons learned, improvements in the guidance will have to account possible rule and guidance changes underway within Part 61. This paper will discuss the initial plans, approaches, and time lines to revise the guidance within NUREG-1854, including opportunities for public involvement. (authors)« less

  3. Shell evolution above Z ,N =50 within Skyrme density functional theory: The impact of deformation and tensor interactions

    NASA Astrophysics Data System (ADS)

    Shi, Yue

    2017-03-01

    Background: Recent years have seen considerable effort in associating the shell evolution (SE) for a chain of isotones or isotopes with the underlying nuclear interactions. In particular, it has been fairly well established that the tensor part of the Skyrme interaction is indispensable for understanding certain SE above Z ,N =50 shell closures, as a function of nucleon numbers. Purpose: The purpose of the present work is twofold: (1) to study the effect of deformation due to blocking on the SE above Z ,N =50 shell closures and (2) to examine the optimal parametrizations in the tensor part which gives a proper description of the SE above Z ,N =50 shell closures. Methods: I use the Skyrme-Hartree-Fock-Bogoliubov (SHFB) method to compute the even-even vacua of the Z =50 isotopes and N =50 isotones. For Sb and odd-A Sn isotopes, I perform calculations with a blocking procedure which accounts for the polarization effects, including deformations. Results: The blocking SHFB calculations show that the light odd-A Sb isotopes, with only one valence proton occupying down-sloping Ω =11 /2- and Ω =7 /2+ Nilsson orbits, assume finite oblate deformations. This reduces the energy differences between 11 /2- and 7 /2+ states by about 500 keV for 51Sb56 -66 , bringing the energy-difference curve closer to the experimental one. With une2t1 energy density functional (EDF), which differs from unedf2 parametrization by tensor terms, a better description of the slope of Δ e (π 1 h11 /2-π 1 g7 /2) as a function of neutron number has been obtained. However, the trend of Δ e (π 1 g7 /2-π 2 d5 /2) curve is worse using une2t1 EDF. Δ e (ν 3 s1 /2-ν 2 d5 /2) and Δ e (ν 1 g7 /2-ν 2 d5 /2) curve for N =50 isotones using une2t1 seems to be consistent with experimental data. The neutron SE of Δ e (ν 1 h11 /2-ν 1 g7 /2) and Δ e (ν 1 g7 /2-ν 2 d5 /2) for Sn isotopes are shown to be sensive to αT tensor parameter. Conclusions: Within the Skyrme self-consistent mean-field model, the deformation degree of freedom has to be taken into account for Sb isotopes, N =51 isotones, and odd-A Sn isotopes when discussing variation of quantities like shell gap etc. The tensor terms are important for describing the strong variation of Δ E (Ωπ=11 /2--7 /2+) in Sb isotopes. The SE of 1 /2+ and 7 /2+ states in N =51 isotones may show signature for the existence of tensor interaction. The experimental excitation energies of 11 /2- and 7 /2+ states in odd-A Sn isotopes close to 132Sn give prospects for constraining the αT parameter.

  4. State Waste Discharge Permit Application: Electric resistance tomography testing

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1994-04-01

    This permit application documentation is for a State Waste Discharge Permit issued in accordance with requirements of Washington Administrative Code 173-216. The activity being permitted is a technology test using electrical resistance tomography. The electrical resistance tomography technology was developed at Lawrence Livermore National Laboratory and has been used at other waste sites to track underground contamination plumes. The electrical resistance tomography technology measures soil electrical resistance between two electrodes. If a fluid contaminated with electrolytes is introduced into the soil, the soil resistance is expected to drop. By using an array of measurement electrodes in several boreholes, the arealmore » extent of contamination can be estimated. At the Hanford Site, the purpose of the testing is to determine if the electrical resistance tomography technology can be used in the vicinity of large underground metal tanks without the metal tank interfering with the test. It is anticipated that the electrical resistance tomography technology will provide a method for accurately detecting leaks from the bottom of underground tanks, such as the Hanford Site single-shell tanks.« less

  5. Bench Scale Saltcake Dissolution Test Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BECHTOLD, D.B.; PACQUET, E.A.

    A potential scenario for retrieving saltcake from single shell tanks is the ''Rainbird{reg_sign} sprinkler'' method. Water is distributed evenly across the surface of the saltcake and allowed to percolate by gravity through the waste. The salt dissolves in the water, forming a saturated solution. The saturated liquid is removed by a saltwell pump situated near the bottom of the tank. By this method, there is never a large inventory of liquid in the tank that could pose a threat of leakage. There are many variables or factors that can influence the hydrodynamics of this retrieval process. They include saltcake porosity;more » saltwell pumping rate; salt dissolution chemistry; factors that could promote flow channeling (e.g. tank walls, dry wells, inclusions or discontinuities in the saltcake); method of water distribution; plug formation due to crystal formations or accumulation of insoluble solids. A brief literature search indicates that very little experimental data exist on these aspects of saltcake dissolution (Wiersma 1996, 1997). The tests reported here were planned (Herting, 2000) to provide preliminary data and information for planning future, scaled-up tests of the sprinkler method.« less

  6. FULL SCALE TESTING TECHNOLOGY MATURATION OF A THIN FILM EVAPORATOR FOR HIGH-LEVEL LIQUID WASTE MANAGEMENT AT HANFORD - 12125

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    TEDESCHI AR; CORBETT JE; WILSON RA

    2012-01-26

    Simulant testing of a full-scale thin-film evaporator system was conducted in 2011 for technology development at the Hanford tank farms. Test results met objectives of water removal rate, effluent quality, and operational evaluation. Dilute tank waste simulant, representing a typical double-shell tank supernatant liquid layer, was concentrated from a 1.1 specific gravity to approximately 1.5 using a 4.6 m{sup 2} (50 ft{sup 2}) heated transfer area Rototherm{reg_sign} evaporator from Artisan Industries. The condensed evaporator vapor stream was collected and sampled validating efficient separation of the water. An overall decontamination factor of 1.2E+06 was achieved demonstrating excellent retention of key radioactivemore » species within the concentrated liquid stream. The evaporator system was supported by a modular steam supply, chiller, and control computer systems which would be typically implemented at the tank farms. Operation of these support systems demonstrated successful integration while identifying areas for efficiency improvement. Overall testing effort increased the maturation of this technology to support final deployment design and continued project implementation.« less

  7. Dangerous Waste Characteristics of Contact-Handled Transuranic Mixed Wastes from the Hanford Tanks

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

    2004-08-31

    This report summarizes existing analytical data from samples taken from the Hanford tanks designated as potentially containing transuranic mixed process wastes. Process knowledge of the wastes transferred to these tanks has been reviewed to determine whether the dangerous waste characteristics now assigned to all Hanford underground storage tanks are applicable to these particular wastes. Supplemental technologies are being examined to accelerate the Hanford tank waste cleanup mission and accomplish waste treatment safely and efficiently. To date, 11 Hanford waste tanks have been designated as potentially containing contact-handled (CH) transuranic mixed (TRUM) wastes. The CH-TRUM wastes are found in single-shell tanksmore » B-201 through B-204, T-201 through T-204, T-104, T-110, and T-111. Methods and equipment to solidify and package the CH-TRUM wastes are part of the supplemental technologies being evaluated. The resulting packages and wastes must be acceptable for disposal at the Waste Isolation Pilot Plant (WIPP). The dangerous waste characteristics being considered include ignitability, corrosivity, reactivity, and toxicity arising from the presence of 2,4,5-trichlorophenol at levels above the dangerous waste threshold. The analytical data reviewed include concentrations of sulfur, sulfate, cyanide, 2,4,5-trichlorophenol, total organic carbon, and oxalate; the composition of the tank headspace, pH, and mercury. Differential scanning calorimetry results were used to determine the energetics of the wastes as a function of temperature.« less

  8. Design and Analysis of Subscale and Full-Scale Buckling-Critical Cylinders for Launch Vehicle Technology Development

    NASA Technical Reports Server (NTRS)

    Hilburger, Mark W.; Lovejoy, Andrew E.; Thornburgh, Robert P.; Rankin, Charles

    2012-01-01

    NASA s Shell Buckling Knockdown Factor (SBKF) project has the goal of developing new analysis-based shell buckling design factors (knockdown factors) and design and analysis technologies for launch vehicle structures. Preliminary design studies indicate that implementation of these new knockdown factors can enable significant reductions in mass and mass-growth in these vehicles. However, in order to validate any new analysis-based design data or methods, a series of carefully designed and executed structural tests are required at both the subscale and full-scale levels. This paper describes the design and analysis of three different orthogrid-stiffeNed metallic cylindrical-shell test articles. Two of the test articles are 8-ft-diameter, 6-ft-long test articles, and one test article is a 27.5-ft-diameter, 20-ft-long Space Shuttle External Tank-derived test article.

  9. Colossal Tooling Design: 3D Simulation for Ergonomic Analysis

    NASA Technical Reports Server (NTRS)

    Hunter, Steve L.; Dischinger, Charles; Thomas, Robert E.; Babai, Majid

    2003-01-01

    The application of high-level 3D simulation software to the design phase of colossal mandrel tooling for composite aerospace fuel tanks was accomplished to discover and resolve safety and human engineering problems. The analyses were conducted to determine safety, ergonomic and human engineering aspects of the disassembly process of the fuel tank composite shell mandrel. Three-dimensional graphics high-level software, incorporating various ergonomic analysis algorithms, was utilized to determine if the process was within safety and health boundaries for the workers carrying out these tasks. In addition, the graphical software was extremely helpful in the identification of material handling equipment and devices for the mandrel tooling assembly/disassembly process.

  10. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mukherjee, G.; Pai, H.

    High spin states in Bismuth and Thallium nuclei near the Z = 82 shell closure and Cesium nuclei near the N = 82 shell closure in A = 190 and A = 130 regions, respectively, have been experimentally investigated using heavy-ion fusion evaporation reaction and by detecting the gamma rays using the Indian National Gamma Array (INGA). Interesting shape properties in these transitional nuclei have been observed. The results were compared with the neighboring nuclei in these two regions. The total Routhian surface (TRS) calculations have been performed for a better understanding of the observed properties. In mass region Amore » = 190, a change in shape from spherical to deformed has been observd around neutron number N = 112 for the Bi (Z = 83) isotopes with proton number above the magic gap Z = 82, whereas, the shape of Tl (Z = 81) isotopes with proton number below the magic gap Z = 82 remains stable as a function of neutron number. An important transition from aplanar to planar configuration of angular momentum vectors leading to the occurance of nuclar chirality and magnetic rotation, respectively, has been proposed for the unique parity πh{sub 11/2}⊗νh{sub 11/2} configuration in Cs isotopes in the mass region A ∼ 130 around neutron number N = 79. These results are in commensurate with the TRS calculations.« less

  11. 49 CFR 178.345-8 - Accident damage protection.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... accidental loss of lading. The device must break at no more than 70 percent of the load that would be... major radius of the tank shell. The device must break at no more than 70 percent of the load that would... for the loss of lading due to an accident. (1) Any dome, sump, or washout cover plate projecting from...

  12. 75 FR 11169 - AES Sparrows Point LNG, LLC; Mid-Atlantic Express, LLC; Notice of Availability of the Revised...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-10

    ... LNG storage tanks; A closed-loop shell and tube heat exchanger vaporization system; Various ancillary..., there are three methods you can use to submit your comments to the Commission. In all instances please... encourages electronic filing of comments and has dedicated eFiling expert staff available to assist you at...

  13. 46 CFR 154.235 - Cargo tank location.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... specified in Table 172.180 of this chapter; and (3) 30 inches (760 mm) from the shell plating. (b) For type... for grounding penetration specified in Table 172.180 of this chapter; and (2) 30 inches (760 mm) from... bottom height or 13.8 in. (350 mm). [CGD 74-289, 44 FR 26009, May 3, 1979, as amended by CGD 79-023, 48...

  14. 49 CFR 179.220-17 - Gauging devices, top loading and unloading devices, venting and air inlet devices.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... good welding quality in conjunction with the metal of the tank shell. When the sump or siphon bowl is... cylinder of revolution must have walls of such thickness and must be so reinforced that the stresses in the walls caused by a given internal pressure are not greater than the circumferential stress which would...

  15. 49 CFR 179.220-17 - Gauging devices, top loading and unloading devices, venting and air inlet devices.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... good welding quality in conjunction with the metal of the tank shell. When the sump or siphon bowl is... cylinder of revolution must have walls of such thickness and must be so reinforced that the stresses in the walls caused by a given internal pressure are not greater than the circumferential stress which would...

  16. 49 CFR 179.220-17 - Gauging devices, top loading and unloading devices, venting and air inlet devices.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... good welding quality in conjunction with the metal of the tank shell. When the sump or siphon bowl is... cylinder of revolution must have walls of such thickness and must be so reinforced that the stresses in the walls caused by a given internal pressure are not greater than the circumferential stress which would...

  17. 49 CFR 179.220-17 - Gauging devices, top loading and unloading devices, venting and air inlet devices.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... good welding quality in conjunction with the metal of the tank shell. When the sump or siphon bowl is... cylinder of revolution must have walls of such thickness and must be so reinforced that the stresses in the walls caused by a given internal pressure are not greater than the circumferential stress which would...

  18. 49 CFR 179.220-17 - Gauging devices, top loading and unloading devices, venting and air inlet devices.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... good welding quality in conjunction with the metal of the tank shell. When the sump or siphon bowl is... cylinder of revolution must have walls of such thickness and must be so reinforced that the stresses in the walls caused by a given internal pressure are not greater than the circumferential stress which would...

  19. Proposed Closure of Los Angeles Air Force Base, California and Relocation of Space Systems Division

    DTIC Science & Technology

    1990-07-01

    rendered temporarily out of service in accordance with state and federal regulations. Aboveground ground tanks associated with Building 130 would...Lowell, and Charles R. Smith 1978 Gabrielino. In Handbook of North American Indians-California, edited by Robert F.3 Heizer . Smithsonian Institution...8, California, edited3 by R.F. Heizer , p. 575-587. Smithsonian Institution, Washington DC. Bean, L.J. and F. Shipek 1978 Luiseno. In The Handbook of

  20. The Cementitious Barriers Partnership Experimental Programs and Software Advancing DOE’s Waste Disposal/Tank Closure Efforts – 15436

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Burns, Heather; Flach, Greg; Smith, Frank

    2015-01-27

    The U.S. Department of Energy Environmental Management (DOE-EM) Office of Tank Waste Management-sponsored Cementitious Barriers Partnership (CBP) is chartered with providing the technical basis for implementing cement-based waste forms and radioactive waste containment structures for long-term disposal. DOE needs in this area include the following to support progress in final treatment and disposal of legacy waste and closure of High-Level Waste (HLW) tanks in the DOE complex: long-term performance predictions, flow sheet development and flow sheet enhancements, and conceptual designs for new disposal facilities. The DOE-EM Cementitious Barriers Partnership is producing software and experimental programs resulting in new methods andmore » data needed for end-users involved with environmental cleanup and waste disposal. Both the modeling tools and the experimental data have already benefited the DOE sites in the areas of performance assessments by increasing confidence backed up with modeling support, leaching methods, and transport properties developed for actual DOE materials. In 2014, the CBP Partnership released the CBP Software Toolbox –“Version 2.0” which provides concrete degradation models for 1) sulfate attack, 2) carbonation, and 3) chloride initiated rebar corrosion, and includes constituent leaching. These models are applicable and can be used by both DOE and the Nuclear Regulatory Commission (NRC) for service life and long-term performance evaluations and predictions of nuclear and radioactive waste containment structures across the DOE complex, including future SRS Saltstone and HLW tank performance assessments and special analyses, Hanford site HLW tank closure projects and other projects in which cementitious barriers are required, the Advanced Simulation Capability for Environmental Management (ASCEM) project which requires source terms from cementitious containment structures as input to their flow simulations, regulatory reviews of DOE performance assessments, and Nuclear Regulatory Commission reviews of commercial nuclear power plant (NPP) structures which are part of the overall US Energy Security program to extend the service life of NPPs. In addition, the CBP experimental programs have had a significant impact on the DOE complex by providing specific data unique to DOE sodium salt wastes at Hanford and SRS which are not readily available in the literature. Two recent experimental programs on cementitious phase characterization and on technetium (Tc) mobility have provided significant conclusions as follows: recent mineralogy characterization discussed in this paper illustrates that sodium salt waste form matrices are somewhat similar to but not the same as those found in blended cement matrices which to date have been used in long-term thermodynamic modeling and contaminant sequestration as a first approximation. Utilizing the CBP generated data in long-term performance predictions provides for a more defensible technical basis in performance evaluations. In addition, recent experimental studies related to technetium mobility indicate that conventional leaching protocols may not be conservative for direct disposal of Tc-containing waste forms in vadose zone environments. These results have the potential to influence the current Hanford supplemental waste treatment flow sheet and disposal conceptual design.« less

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